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	abstract	An object of the invention is to realize a method and an apparatus for processing and observing a minute sample which can observe a section of a wafer in horizontal to vertical directions with high resolution, high accuracy and high throughput without splitting any wafer which is a sample. In an apparatus of the invention, there are included a focused ion beam optical system and an electron optical system in one vacuum container, and a minute sample containing a desired area of the sample is separated by forming processing with a charged particle beam, and there are included a manipulator for extracting the separated minute sample, and a manipulator controller for driving the manipulator independently of a wafer sample stage.
042345553	description	EXAMPLE I The invention was tested by mixing selected quantities of particulate CaF.sub.2 in six 0.200-liter samples of an aqueous HF solution containing 120 ppm uranium. The solution comprised 20 wt-% HF. The CaF.sub.2 powder was acid-grade fluorspar, manufactured by Allied Chemical Corporation. This powder had a nitrogen surface area of 1.6 m.sup.2 /g (based on the well-known B.E.T. measurement). Tyler-sieve data for the powder were as follows: 45% of the powder passed through a 325-mesh screen and 15% was retained by the screen; 27% was retained on a 200-mesh screen; 9% was retained on a 100-mesh screen; and 4% was retained on a 65-mesh screen. Each of the samples containing particulate CaF.sub.2 was stirred at room temperature for an hour. Following stirring, the resulting slurries were either filtered promptly or the supernate was separated by decanting. The resulting solutions were analyzed for uranium by gamma-spectrometry and for calcium by atomic absorption. The accompanying table shows the CaF.sub.2 -to-uranium weight ratios employed in each of the six tests, together with the results obtained. It will be noted that removal of 50% of the uranium was accomplished at a CaF.sub.2 /U ratio of 8 and that removal of 92% of the uranium was accomplished at ratios exceeding 37. As shown, the product solutions contained very little calcium--only 9 ppm if the solution was not filtered, and less than 0.2 ppm if it was filtered. Thus, the process was found to remove uranium effectively while avoiding contamination of the product solution. __________________________________________________________________________ Lbs CaF.sub.2 Initial Final Final Sample per 13,500 CaF.sub.2 /U U Conc., U Conc., U Removal, Ca.sup.++ Conc., No. Gal. Solution by Weight ppm ppm % ppm __________________________________________________________________________ 1 56 4 120 72 40 <0.2 2 84 6 120 71 41 <0.2 3 112 8 120 60 50 <0.2 4* 112 8 120 59 51 9 5 500 37 120 10 92 <0.2 6 1000 74 120 10 92 <0.2 __________________________________________________________________________ *Sample 4 was allowed to stand overnight before decanting. All other samples were filtered before analysis. EXAMPLE II A 67,000-pound batch of aqueous 20%-HF solution containing 74 ppm uranium was admitted to a railroad tank car which previously had been used to recover uranium in accordance with this invention. The rubber-linked tank contained a heel of CaF.sub.2 /U slurry remaining from the previous recovery operation. The tank car was provided with means for sparging with air. With the sparging means energized, approximately 400 pounds of particulate CaF.sub.2 (identified in Example I) was added to the solution to provide a total CaF.sub.2 /U weight ratio of 159 to 1. After three days of air agitation and then four hours of sedimentation (both conducted at room temperature), the solution was analyzed. The analysis was as follows: HF, .about.20 wt-%, uranium, 7 ppm; calcium, >0.2 ppm. Following analysis, the solution was decanted for sale. As indicated above, this method for recovery of uranium has significant advantages. For example, it entails comparatively simple process operations and requires only readily available equipment. Again, uranium removal is effected without introducing a contaminant into the product solution. Furthermore, a wide variety of CaF.sub.2 powders may be employed, such as powders having nitrogen surface areas in the range of from about 1 to 200 m.sup.2 /g. The method is believed effective for reducing the uranium content of both dilute and concentrated aqueous HF solutions containing a trace amount of uranium. By "trace amount" is meant in the range of from a few ppm to thousands of ppm. In general, appreciable uranium carry-down may be obtained if the CaF.sub.2 /U weight ratio is in the range of from about 8 to 75. It will be understood that the process parameters cited in Examples I and II, above, are not necessarily the optimum. For example, even higher percentages of uranium might have been removed if the runs had been conducted with (a) higher-surface-area CaF.sub.2, (b) a tank having a more suitable geometry with respect to mixing, or (c) more efficient mixing means--e.g., a propeller-type mixer. Given the teachings herein, one versed in the art will be able to determinne the preferred process parameters (e.g., CaF.sub.2 powder surface areas, CaF.sub.2 /U weight ratios) for a given application of this invention by merely routine experimentation, as by testing on a laboratory scale. The foregoing examples are provided for the purpose of illustration only, and it will be understood that the scope of the invention is to be interpreted in terms of the following claims.
	abstract	An automated X-ray imaging system and method for producing a plurality of X-ray imaging signals having selectively enhanced volumetric image resolutions, e.g., for magnifying the field of view and providing a volumetric display image having features not otherwise visible to an unaided human eye. Successive doses of X-ray radiation are applied to a portion of the subject to produce corresponding volumetric image signals. Such doses of X-ray radiation are controlled by controlling X-ray radiation characteristics, such as intensity, focal spot size, focal spot location, focal spot shape, or collimation, to cause a subsequent volumetric image signal to differ from a prior volumetric image signal in one or more volumetric image characteristics, such as volumetric image resolution.
	claims	1. A remotely operated vehicle for inspecting a core shroud with an axis and an outside surface, comprising:an abdomen with a first side; anda first wing swingly connected through a first hinge to the first side of the abdomen;wherein the first hinge has an axis that is substantially parallel to the axis of the core shroud;wherein each of the abdomen and the first wing has a curved profile that is configured to conform to the outside surface of the core shroud; andwherein the first wing further comprises a rail and a gimbal attached to the rail through a linear bearing. 2. The remotely operated vehicle of claim 1, further comprising:a set of horizontal wheels that are configured to move the remotely operated vehicle around the outside surface of the core shroud; anda set of vertical wheels that are configured to move the remotely operated vehicle along the axis of the core shroud. 3. The remotely operated vehicle of claim 2, wherein at least one of the sets of wheels is configured to be retracted as not to be in contact with the outside surface of the core shroud. 4. The remotely operated vehicle of claim 1, comprising:an ultrasonic probe; anda probe positioning system that is configured to translate and rotate the ultrasonic probe. 5. The remotely operated vehicle of claim 1, further comprising a handle that is configured to guide an installation arm to a flat middle portion of the handle. 6. The remotely operated vehicle of claim 5, the handle comprising raised outer edges that are slanted toward the flat middle portion. 7. The remotely operated vehicle of claim 1, comprising a vacuum system that is configured to adhere the remotely operated vehicle to the surface of the core shroud, the vacuum system comprising:a venturi valve that is configured to draw water from a void in the remotely operated vehicle; anda pump configured to supply water pressure to the venturi valve. 8. The remotely operated vehicle of claim 7, the vacuum system comprising a sealing ring that defines the void. 9. The remotely operated vehicle of claim 8, the sealing ring comprising a foam ring and a cover over the foam ring. 10. The remotely operated vehicle of claim 1, wherein the first hinge is spring loaded to bias the first wing toward the outside surface of the core shroud. 11. The remotely operated vehicle of claim 10, wherein the spring loaded hinge includes a torsion spring. 12. The remotely operated vehicle of claim 1, wherein the rail is substantially parallel to the axis of the core shroud. 13. The remotely operated vehicle of claim 12, further comprising a motion driving mechanism connected to the gimbal for moving the gimbal along the rail. 14. The remotely operated vehicle of claim 1, wherein the curved profile of each of the abdomen and the first wing has a curvature that is a function of an outer radius of the core shroud. 15. The remotely operated vehicle of claim 1, wherein the abdomen includes a second side opposite the first side;wherein a second wing is swingly connected through a second hinge to the second side of the abdomen;wherein the second hinge has an axis that is substantially parallel to the axis of the core shroud; andwherein the second wing has a curved profile that is configured to conform to the outside surface of the core shroud. 16. The remotely operated vehicle of claim 15, wherein the curved profile of each of the abdomen, the first wing, and the second wing has a curvature that is a function of an outer radius of the core shroud. 17. The remotely operated vehicle of claim 15, wherein the first hinge is spring loaded to bias the first wing toward the outside surface of the core shroud and the second hinge is spring loaded to bias the second wing toward the outside surface of the core shroud.
	abstract	A sealing member is provided to create a sealed region about an annulus formed between an inner body, such as a thermal sleeve, and an outer body, such as a control rod drive housing nozzle. Liquid is introduced into the sealed region to create a flooded region, which is pressurized to a desired level. A nozzle is provided into the flooded region, the nozzle being configured to fit within the annulus. Pressurized fluid is ejected from the nozzle, causing the formation of cavitation bubbles. The nozzle flow causes the cavitation bubbles to settle on the surfaces forming the annulus. The collapsing impact of the cavitation bubbles imparts compressive stress in the materials of the surfaces forming the annulus.
	abstract	The invention concerns a device (1) for controlling the exterior aspect of fuel rods (2) for nuclear reactors, said device comprising optical means (40) having at least one camera (42, 42′) and linked to an image acquisition and processing system (48) capable of detecting geometric defects present on each rod (2) to be controlled, and further comprising a roughness tester (50) controlled in such a way as to measure the depth of each geometric defect detected by the image acquisition and processing system (48).
	claims	1. A surface illuminator comprising:a surface lighting light guide member having a light emitting first major surface, a second major surface opposed to the first major surface and at least one light receiving side surface;an elongated light guide member having a linear or nonlinear elongated member, at least one surface and at least one light receiving portion;at least one point light source optically communicated with the at least one light receiving portion;a channel light guide member having a plurality of optical core channel elements and a plurality of optical clads alternately aligned to form an elongated fiber optic channel array having a plurality of light entrance core surfaces and a plurality of exit core surfaces opposed to the light entrance core surfaces;wherein the channel light guide member is interposed between the surface lighting light guide member and the elongate light guide member;wherein the optical clads comprise light reflecting material composed of substantially transparent solid material having a refractive index lower than the refractive index of the cores and/or light reflecting metallic material; andwherein each width of the optical core channel elements and/or a pitch between the adjacent optical core channel elements is changed along the elongated optical channel array in such a way that the width increases in accordance with a distance from the point light source and/or the pitch decreases in accordance with a distance from the point light source. 2. The surface illuminator according to claim 1, wherein light from the at least one point light source enters the elongated light guide member and the light transmits therein toward at least one substantially lengthwise direction thereof. 3. The surface illuminator according to claim 1, wherein the light entrance core surfaces and the light exit core surfaces are disposed to be in contact with, connected with and/or in close vicinity to the at least one surface of the elongate light guide member and the at least one side surface of the surface lighting light guide member respectively in that order. 4. The surface illuminator according to claim 1, wherein the surface lighting light guide member, the channel light guide member and the elongated light guide member are disposed respectively in that order. 5. The surface illuminator according to claim 1, wherein the surface lighting light guide member, the channel light guide member and the elongate light guide member are connected to one another in that order to form an integrated light guide unit. 6. The surface illuminator according to claim 1, wherein light enters from the light entrance core surfaces exits from the light exit core surface and the light is received in the at least one light side surface to transmit within the surface lighting light guide member for outputting from the light emitting surface. 7. The surface illuminator according to claim 1,wherein light from the at least one point light source enters the elongated light guide member from at least one opposed reflecting surfaces thereof, at least one end surface thereof and/or at least one corner surface thereof to transmit toward at least one substantially lengthwise direction thereof. 8. The surface illuminator according to claim 1, each of the optical clads comprise the light reflecting material composed of a substantially transparent solid film having a refractive index lower than the refractive index of the cores and/or a light reflecting metallic film disposed on the substantially transparent solid film. 9. The surface illuminator according to claim 1, wherein an area of each of the light entrance surfaces is the same as the size of an area of each of the light exit surfaces. 10. The surface illuminator according to claim 1, wherein an area of each of the light entrance surfaces is smaller than an area of each of the light exit surfaces. 11. The surface illuminator according to claim 1, wherein each width of the optical core channel elements and/or a pitch between the adjacent optical core channel elements is substantially unchanged along the elongated optical channel array. 12. The surface illuminator according to claim 1, wherein the elongated light guide member and/or the channel light guide member comprise a nonlinear shaped configuration as a whole having the shape selected from the group consisting of substantially “O” shape, flame-like shape, loop-like shape and ring-like shape. 13. The surface illuminator according to claim 1, wherein the elongated fiber optic channel array is composed of a linear shaped configuration as a whole so as to face one of the at least one light receiving side surface of the surface lighting light guide member. 14. The surface illuminator according to claim 1, the elongated light guide member further comprising: at least one reflector, each of the at least one reflector having opposed reflecting surfaces disposed relative to the at least one light receiving portion. 15. The surface illuminator according to claim 1,wherein each of the optical core channel elements comprises a substantially rectangular shape in such a manner that each of the light exit core surfaces has an area size equal to the area size of each of the light entrance core surfaces; orwherein each of the optical core channel elements comprises a substantially trapezoidal shape in such a manner that each of the light exit core surfaces has an area size larger than the area size of each of the light entrance core surfaces. 16. A surface illuminator comprising:a surface lighting light guide member having a light emitting first major surface, a second major surface opposed to the first major surface and at least one light receiving side surface;an elongated light guide member having a linear or nonlinear elongated member, at least one surface and at least one light receiving portion;at least one point light source optically communicated with the at least one light receiving portion;a channel light guide member having a plurality of optical core channel elements and a plurality of optical clads alternately aligned to form an elongated fiber optic channel array having a plurality of light entrance core surfaces and a plurality of exit core surfaces opposed to the light entrance core surfaces;wherein the channel light guide member is interposed between the surface lighting light guide member and the elongate light guide member; andwherein the elongated fiber optic channel array comprise a nonlinear shaped configuration as a whole having a substantially “L” or “U” shape so as to face two or more of the light receiving side surfaces of the surface lighting light guide member. 17. The surface illuminator according to claim 16:wherein each width of the optical core channel elements and/or a pitch between the adjacent optical core channel elements is changed along the elongated optical channel array in such a way that the width increases in accordance with a distance from the point light source and/or the pitch decreases in accordance with a distance from the point light source. 18. A surface illuminator comprising:a surface lighting light guide member having a light emitting first major surface, a second major surface opposed to the first major surface and at least one light receiving side surface;an elongated light guide member having a linear or nonlinear elongated member, at least one surface and at least one light receiving portion;at least one point light source optically communicated with the at least one light receiving portion;a channel light guide member having a plurality of optical core channel elements and a plurality of optical clads alternately aligned to form an elongated fiber optic channel array having a plurality of light entrance core surfaces and a plurality of exit core surfaces opposed to the light entrance core surfaces;wherein the channel light guide member is interposed between the surface lighting light guide member and the elongate light guide member;wherein the optical clads comprise light a reflecting material composed of substantially transparent solid material;wherein the substantially transparent solid material having a refractive index lower than the refractive index of the cores; andwherein the substantially transparent solid material contains a plurality of light diffusing particles dispersed therein. 19. The surface illuminator according to claim 18:wherein each width of the optical core channel elements and/or a pitch between the adjacent optical core channel elements is changed along the elongated optical channel array in such a way that the width increases in accordance with a distance from the point light source and/or the pitch decreases in accordance with a distance from the point light source. 20. The surface illuminator according to claim 18:wherein the elongated fiber optic channel array comprise a nonlinear shaped configuration as a whole having a substantially “L” or “U” shape so as to face two or more of the light receiving side surfaces of the surface lighting light guide member.
	claims	1. A computer-implemented method for determining a mask pattern to be used on a photo-mask in a lithography process, comprising:receiving at least a portion of a first mask pattern including first regions that violate pre-determined rules associated with the photo-mask; anddetermining, using the computer, a second mask pattern based on at least the portion of the first mask pattern, wherein the second mask pattern includes second regions that are estimated to comply with the pre-determined rules;wherein the second regions correspond to the first regions;wherein the second mask pattern is determined using a different technique than that used to determine the first mask pattern;wherein at least the portion of the first mask pattern further includes third regions that surround corresponding first regions;wherein the third regions are unchanged during the determination of the second mask pattern; andwherein a size of the third regions corresponds to an interaction range associated with the lithographic process. 2. The method of claim 1, further comprising:analyzing the first mask pattern using the pre-determined rules to identify the first regions; andextracting at least the portion of the first mask pattern. 3. The method of claim 2, wherein the analysis of the first mask pattern involves verification. 4. The method of claim 3, wherein the verification is image-based. 5. The method of claim 2, wherein identification of the first regions involves identifying locations associated with violations of the pre-determined rules, and wherein the extraction of at least the portion of the first mask pattern involves calculating the first regions based on one or more geometric relationships for shapes surrounding the locations. 6. The method of claim 5, wherein the one or more geometric relationships include overlapping shapes or adjacent shapes that contact each other along an edge. 7. The method of claim 6, wherein the shapes include polygons. 8. The method of claim 5, wherein the extraction of at least the portion of the first mask pattern involves aggregating the calculated first regions. 9. The method of claim 1, wherein receiving involves accessing at least the portion of the first mask pattern in a computer-readable memory. 10. The method of claim 1, further comprising applying optical proximity correction to at least the portion of the first mask pattern prior to the determination of the second mask pattern. 11. The method of claim 1, further comprising merging the second mask pattern with a remainder of the first mask pattern, wherein the remainder of the first mask pattern excludes the first regions. 12. The method of claim 1, wherein the first regions include hotspots. 13. The method of claim 1, wherein the pre-determined rules include manufacturing rules associated with the photo-mask. 14. The method of claim 1,wherein a first portion of the third regions are unchanged during the determination of the second mask pattern;wherein a second portion of the third regions are changed during the determination of the second mask pattern; andwherein the second portion of the third regions is a transition region between the second regions and the first portion of the second regions. 15. The method of claim 14, wherein an optical characteristic of the second portion of the third regions is approximately unchanged or is improved relative to the optical characteristic of the second portion of the third regions in at least the portion of the first mask pattern. 16. The method of claim 15, wherein the optical characteristic includes intensity, contrast, depth of focus, or a mask error enhancement factor. 17. The method of claim 1, wherein the first mask pattern includes multiple subsets that are to be processed by a group of processors, and wherein the portion of the first mask pattern includes those multiple subsets that are proximate to the first regions. 18. The method of claim 1, further comprising analyzing the second mask pattern using the pre-determined rules to confirm that the second regions comply with the pre-determined rules. 19. The method of claim 18, wherein the analysis of the second mask pattern involves verification. 20. The method of claim 1, wherein in the determination of the second mask pattern involves an inverse lithographic calculation that includes a projection of a target pattern at an image plane in a photolithographic process to an object plane in the photolithographic process. 21. The method of claim 1, wherein the determination of the second mask pattern involves image-based or pixel-based correction. 22. The method of claim 1, wherein at least the portion of the first mask pattern is included in a file that is compatible with a GDSII format. 23. A computer-program product for use in conjunction with a computer system, the computer-program product comprising a non-transitory computer-readable storage medium and a computer-program mechanism embedded therein for determining a mask pattern to be used on a photo-mask in a lithography process, the computer-program mechanism including:instructions for receiving at least a portion of a first mask pattern including first regions that violate pre-determined rules associated with the photo-mask; andinstructions for determining a second mask pattern based on at least the portion of the first mask pattern, wherein the second mask pattern includes second regions that are estimated to comply with the pre-determined rules;wherein the second regions correspond to the first regions;wherein the second mask pattern is determined using a different technique than that used to determine the first mask pattern;wherein at least the portion of the first mask pattern further includes third regions that surround corresponding first regions;wherein the third regions are unchanged during the determination of the second mask pattern; andwherein a size of the third regions corresponds to an interaction range associated with the lithographic process. 24. A computer system to determine a mask pattern to be used on a photo-mask in a lithography process, comprising:at least one processor;at least one memory; andat least one program module, the program module stored in the memory and configured to be executed by the processor, at least the program module including:instructions for receiving at least a portion of a first mask pattern including first regions that violate pre-determined rules associated with the photo-mask; andinstructions for determining a second mask pattern based on at least the portion of the first mask pattern, wherein the second mask pattern includes second regions that are estimated to comply with the pre-determined rules;wherein the second regions correspond to the first regions;wherein the second mask pattern is determined using a different technique than that used to determine the first mask pattern;wherein at least the portion of the first mask pattern further includes third regions that surround corresponding first regions;wherein the third regions are unchanged during the determination of the second mask pattern; andwherein a size of the third regions corresponds to an interaction range associated with the lithographic process.
052456439	abstract	Part length water regions are located above part length fuel rods in boiling water nuclear reactor fuel bundles. The part length water regions include discrete containers having entry ports at the top of the part length water regions for capturing water, and vent ports for permitting internally generated steam to escape. The advantages of improved neutron moderation in the upper portion of the fuel assembly are maintained while the uranium fuel removal requirements are minimized.
	summary
051981823	claims	1. The method of making a section of a neutron-absorbing tube, comprising the steps of a. forming an elongate, generally rectangular metal ingot having a hollow interior, b. installing at least one elongate metal divider in said interior to form at least two chambers in said interior, c. filling said chambers with a substantially uniformly dispersed mixture of a finely divided neutron-absorbing boron compound and a finely divided metal powder, d. soaking the ingot to bring it to an elevated temperature below the melting temperature of the metal powder, e. hot rolling the ingot to reduce its thickness to form a thin, rigid neutron-absorbing sheet having opposite metal edge portions and an elongated metal spacer portion at each metal divider, and f. longitudinally bending the sheet at each spacer portion. a. forming a pair of elongate, generally rectangular metal ingots having a hollow interior, b. installing an elongate metal divider in the hollow interior of each ingot to form two chambers in the interior of each ingot, c. filling said chambers with a substantially uniformly dispersed mixture of a finely divided neutron-absorbing boron compound and a finely divided metal powder, d. soaking each ingot to bring it to an elevated temperature below the melting temperature of the metal powder, e. hot rolling each ingot to reduce its thickness to form a thin, rigid neutron-absorbing sheet having opposite metal edge portions and an elongated metal spacer portion at each metal divider, f. longitudinally bending each sheet at the spacer portion to an L-shaped cross section, and g. joining the bent sheets at said metal edge portions to form a tube. a. forming an elongate, generally rectangular metal ingot having a hollow interior, b. installing a series of elongate metal dividers in said interior to form at least four chambers in said interior, c. filling said chambers with a substantially uniformly dispersed mixture of a finely divided neutron-absorbing boron compound and a finely divided metal powder, d. soaking the ingot to bring it to an elevated temperature below the melting temperature of the metal powder, e. hot rolling the ingot to reduce its thickness to form a thin, rigid neutron-absorbing sheet having opposite metal edge portions and an elongated metal spacer portion at each metal divider, f. longitudinally bending the sheet at each spacer portion, and g. joining said metal edge portions to form a tube. 2. A method according to claim 1 in which method step "b" includes installing one metal divider and method step "f" includes longitudinally bending the sheet to an L-shaped cross section. 3. A method according to claim 2 including the step of making a second substantially identical section and joining said sections at said metal edge portions to form a tube. 4. A method according to claim 2 in which method step "f" further includes bending one of said metal edge portions to an L-shaped cross section. 5. A method according to claim 4 including the step of making a second substantially identical section and joining said sections at said metal edge portions to form a tube. 6. A neutron-absorbing tube made in accordance with the method of claim 1 in which the tube comprises a pair of sections each of which is bent to an L-shaped cross section at the metal spacer portion, said sections being welded at their edge portions to form a hollow tube. 7. The method of making a neutron-absorbing tube, comprising the steps of 8. A method according to claim 7 in which method step "f" includes the step of bending one of the metal edge portions of each sheet to an L-shaped cross section. 9. A method according to claim 8 in which method step "g" includes joining the bent edge portion of each sheet to the other edge portion of the other sheet. 10. A method according to claim 9 in which joining is by welding. 11. A method according to claim 9 in which method step "e" includes forming each sheet to have one metal edge portion of greater width than the other edge portion. 12. A method according to claim 11 in which method step "f" includes the step of bending the one metal edge portion of each sheet to an L-shaped cross section. 13. A method according to claim 12 in which method step "g" includes joining the bent edge portion of each sheet to the other edge portion of the other sheet. 14. A neutron-absorbing tube made in accordance with the method of claim 7 in which the tube comprises a pair of sheets each of which is bent to an L-shaped cross section at the metal spacer portion, said sheets being welded at their edge portions to form a hollow tube. 15. The method of making a neutron-absorbing tube, comprising the steps of 16. A method according to claim 15 in which method step "b" includes installing four metal dividers and method step "f" includes longitudinally bending the sheet to an L-shaped cross section at each metal spacer portion. 17. A method according to claim 16 in which method step "f" further includes bending one of said metal edge portions to an L-shaped cross section. 18. A method according to claim 17 in which method step "e" includes the step of forming one metal edge portion of greater width than the other edge portion. 19. A method according to claim 18 in which method step "f" includes the step of bending the one metal edge portion to an L-shaped cross section. 20. A method according to claim 19 in which method step "g" includes joining the bent edge portion to the other edge portion by welding.
047330929	summary	BACKGROUND OF THE INVENTION The invention relates generally to radiation shielding or attenuating systems and more particularly to a method and system which enables workers to work in an enclosed radioactive workspace safely for long periods with freedom of movement in the workspace. In nuclear power plants, steam generators typically are utilized as heat exchangers between the reactor and a power generating steam turbine. The steam generators have hundreds or thousands of heat exchange tubes in single pass or double pass loop tubes inside the generator housing, which typically are sixty feet high. The tubes carry contaminated water, at high temperature and pressure from the reactor, through the generators, which in turn transfers heat to water around the tubes, creating steam to drive the turbine. Periodically, typically during a reactor refueling outage, or if a leak occurs, the tubes are checked to make sure they are not leaking or stressing to the point where they will leak contaminated water into the steam. The tubes are checked by running a tester, typically an eddy current tester, over the length of each tube to be checked. Typically, unless a leak has occurred, some predetermined number of the thousands of tubes are checked during each outage so that during a period of time all the tubes are checked. The testers are operated and repairs or sealing off of leaking tubes are sometimes performed by workers physically climbing into the steam generators through a manway or portal into the bottom of the generator housing. The bottom of the generator housing or the workspace is typically called the channel head and generally is a quarter of a sphere (a half of a bowl) with a diameter of nine to twelve feet. The interior of the channel head presents workers with a main problem of a high radiation environment and a secondary problem of contact contamination with radioactive airborne particles which are on the interior surfaces of the housing and channel head and are dislodged by the workers themselves from the tubes and surfaces. Due to the fact that the interior or workspace of the generator channel head is a high radiation environment, the workers are only permitted to be inside the generator for a few minutes at a time. The checking and repairs, therefore may require hundreds of entrances and exits. Many attempts to shield the radiation of the interior walls and tubes of the generator have been attempted with limited success. Most of these shielding approaches are very expensive and create radioactive wastes. Further, the problem of contact contamination within the workspace requires respiratory protection for the workers, as well as causing surface contamination of the workers garments, which contamination is then brought out of the generator when the workers climb out of the portal. Each worker typically is attired in several layers of clothing covered by a plastic outer layer and a self contained breathing apparatus or supplied-air respirator. This makes it difficult to pass through the portals, which usually are small on the order of sixteen inches in diameter, and the clothing itself is cumbersome to work in. Further, each time the worker leaves the generator at least the outer clothing which has radioactive contaminants on it has to be removed and disposed of. The area around the portal becomes contaminated and must be cleaned. The workers outside the generator are exposed to the contaminants brought out on the clothing and the worker himself is further exposed because the contaminants are in physical contact with the clothing and remain there while the clothing is further handled and disposed of. The invention permits the workers to work in a radiation attenuated environment and with a decrease in the physical contact with the surfaces of the workspace once the system is assembled. The workers can work in the enclosed workspace of the steam generator channel head inside the system of the invention with a decrease in the physical exposure to the contaminants and a decrease in the carrying of contaminants outside the workspace. The radiation emitted by the surfaces and tubes of the generator, particularly the lower end portion of the tubes, is absorbed by a radiation attenuating medium of the system except where exposed for work on the generator. Thus, the shielding greatly reduces the radiation exposure per unit of time and also can reduce the contamination of workers and outside areas. SUMMARY OF THE INVENTION The above and other disadvantages of prior art contaminant control techniques and systems are overcome in accordance with the present invention by providing a radioactive attenuation or shielding system for an internal radioactive work environment. The system shields the workers from a major portion of the radiation, thereby increasing the length of time the worker can remain in the work environment. The system includes a frame forming a skeleton around the periphery of the internal radioactive work environment, such as the channel head workspace inside a nuclear power plant steam generator. The frame includes a plurality of segments which interlock with one another and can be rapidly assembled to minimize the exposure of the worker in the radioactive work environment. The frame includes supports for radiation attenuating panels or pads or blankets which are supported by the frame and which provide the radiation attenuation for the system. The top of the workspace can be a semicircular area and the radiation attenuating panels can be formed in panels supported by the frame which can be moved in a fan type arrangement adjacent the top of the workspace. The panels can be moved to one side to expose areas to be worked upon. The frame also includes a support for radiation attenuation pads to be hung around the sides of the workspace.
	claims	1. A system comprising:a treatment station for particle beam treatment of a patient;a particle accelerator configured to generate a particle beam;three or more particle beam paths through which the particle beam can be delivered to the patient at the treatment station, the three or more particle beam paths including at least two particle beam paths significantly greater than or less than 90 degrees apart; anda transport system configured to automatically move a particle beam nozzle from a nozzle storage to one of the three or more particle beam paths. 2. The system of claim l, wherein the three or more particle beam paths are configured such that a first angle exists between a first pair of the three of more particle beam paths and a second different angle exists between a second pair of the three or more particle beam paths. 3. The system of claim 1, wherein the three or more particle beam paths are configured such that a first angle exists between a first pair of the three or more particle beam paths and a second different angle exists between a second pair of the three or more particle beam paths. 4. The system of claim 1, wherein the transport system is further configured to automatically move the particle beam nozzle from one of the three or more particle beam paths to an other of the three or more particle beam paths. 5. The system of claim 1, further including a particle transparent vacuum seal along at least one of the three or more particle beam paths, and a shutter disposed to protect the particle transparent vacuum seal when a particle beam nozzle is absent from the at least one of the three or more particle beam paths. 6. The system of claim 1, further including a processing unit configured to replace a first particle beam nozzle located along one of the three or more particle beam paths with a second particle beam nozzle. 7. The system of claim 1, wherein at least one of the three or more particle beam paths is configured to deliver the particle beam to the patient from underneath the patient. 8. A system comprising:a treatment station for particle beam treatment of a patient;a particle accelerator configured to generate a particle beam for treatment of the patient; andthree or more particle beam paths through which the particle beam can be delivered to the patient at the treatment station, the three or more particle beam paths configured such that a first particle beam path is located outside of a plane including a second particle beam path and a third particle beam path. 9. The system of claim 8, wherein the three or more particle beam paths include two particle beam paths that are oriented significantly greater than 90 degrees apart. 10. The system of claim 8, further including a transport system configured to automatically move a particle beam nozzle between a first of the three or more particle beam paths and a second of the three or more particle beam paths. 11. The system of claim 8, further including a particle transparent vacuum seal along at least one of the three or more particle beam paths, and a shutter disposed to protect the particle transparent vacuum seal when a particle beam nozzle is absent from the at least one of the three or more particle beam paths. 12. The system of claim 8, further including a processing unit configured to replace a first particle beam nozzle located along one of the three or more particle beam paths with a second particle beam nozzle. 13. The system of claim 8, wherein the treatment station includes an opening configured to receive the particle beam from underneath the patient. 14. A method of treating a patient, the method comprising:generating a particle beam of high-energy particles;directing the particle beam of high-energy particles along a first beam path;treating the patient using the particle beam of high-energy particles directed along the first particle beam path;selecting a second particle beam path from among a plurality of alternative particle beam paths different from the first particle beam path, the first particle beam path lying outside of a plane defined by two of the plurality of alternative particle beam paths; anddirecting the particle beam of high-energy particles along the second particle beam path. 15. The method of claim 14, further including selecting a third particle beam path, directing the particle beam of high energy particles along the third particle beam path, and treating the patient using the particle beam of high energy particles directed along the third particle beam path. 16. The method of claim 14, wherein at least one of the plurality of alternative particle beam paths is disposed beneath the patient. 17. The method of claim 14, further including moving a particle beam nozzle from the first particle beam path to the second particle beam path under control of a processing unit. 18. The method of claim 14, further including moving the patient between the steps of directing the particle beam of high-energy particles along a first particle beam path and directing the particle beam of high-energy particles along the second particle beam path. 19. The method of claim 14, wherein the second particle beam path is approximately co-linear with the first particle beam path at a treatment station, and the second particle beam path is configured to direct the particle beam of high energy particles in a different direction than the first particle beam path. 20. The method of claim 14, wherein the first particle beam path and the second particle beam path have approximately equal path lengths. 21. The method of claim 14, wherein the particle beam of high-energy particles includes protons. 22. The method of claim 14, wherein the first particle beam path and at least two of the plurality of alternative particle beam paths are each approximately 90 degrees from each other.
048030392	abstract	The operator of a complex process facility is aided in executing step by step procedures by a computer based system which incorporates monitored plant data and interactive plant operator responses to prompts to progress step by step through selected procedures. At each procedure step the plant status is evaluated and a recommended course of action is identified. The results are displayed on a visual display device to provide operator guidance for executing the procedure in effect. Parallel process monitoring visually alerts the user to conditions not considered by the current step of the active procedure, and where the seriousness of the other condition warrants, provides procedure-based recommendations for priority action. The system can be accessed by multiple users at separate locations for coordinated execution of a single procedure or simultaneous execution of two different procedures. A permanent chronological record of the step by step execution of the selected procedures including the pertinent plant conditions and operator responses, and the parallel monitored status tree conditions is also generated by the system for subsequent review and analysis.
	description	This application is a National Stage of International Application No. PCT/EP2006/010164, filed Oct. 20, 2006, and which claims the benefit of German Patent Application No. 102005051470.7, filed Oct. 21, 2005, the disclosures of both applications being incorporated herein by reference. The invention relates to an activation device for temperature-sensitive and/or time-sensitive indicators activatable by UV light for product labeling, comprising a UV light source device. The invention further relates to a device for the provision of activated temperature-sensitive and/or time-sensitive indicators for product labeling. The invention furthermore relates to a method for the activation of a temperature-sensitive and/or time-sensitive indicator activatable by UV light for product labeling. A substrate is known from DE 198 03 208 C2 for the packaging of or for the application onto aging-sensitive and temperature-sensitive products having a time/temperature indicator arranged in the region of the substrate, with the time/temperature indicator being a time/temperature indicator whose starting time can be set as desired defined by light radiation, with the indicator containing a matrix and at least one reversible, rechargeable crystalline indicator which is embedded therein and which has photochromic properties on the basis of transfer reactions. After the activation of the time/temperature indicator via light, and in particular UV light, the color of the indicator changes in dependence on the time and on the temperature. A product labeling can thereby be provided, with the color of the indicator corresponding to the freshness and the quality of the product. It is an underlying object of the present invention to provide an activation device of the initially named kind with which activated indicators can be provided in a simple manner. This object is satisfied in accordance with the invention with the activation device of the initially named kind in that a control/regulation device is provided via which the radiation time and/or the radiation strength of the UV light source device can be controlled and/or regulated. The time dependence and/or temperature dependence of the “deenergizing” after the activation can be set by the control/regulation of the radiation time and/or radiation strength. Time integrator properties or time/temperature integrator properties of the indicator can thereby be set via the activation device. An adaptation to a product to be labeled is thereby possible. For example, products which spoil faster can be provided with correspondingly activated indicators which deenergize “faster”. The aging and/or any contamination of the UV light source device with respect to the UV light radiation can also be taken into account by the control/regulation device. A feedback loop can be realized via which the radiation strength and/or radiation time of the UV light source device can be readjusted such that the aging and/or contamination is compensated. The object is furthermore satisfied in accordance with the invention in that the UV light source device includes at least one UV light emitting diode. UV light emitting diodes can be controlled in a simple manner and have low space requirements. The activation device can thereby be designed in a space-saving manner. It can thereby be integrated, for example, into a labeling device and in particular a hand-held labeling device. Furthermore, UV light emitting diodes have a relatively low electrical energy consumption. The radiated light can furthermore be focused in a simple manner. Indicators can be activated in a simple manner in a continuous process. It is generally possible for the control of the radiation time and/or radiation strength to take place via diaphragms which are moved mechanically. It is advantageous for the light generation at the UV light source device to be able to be controlled and/or regulated by the control/regulation device. No mechanical elements then have to be provided. Such a control/regulation of the light generation can be carried out in a simple manner when the UV light source device includes UV light emitting diodes. It is favorable for the electrical action on the UV light source device to be able to be controlled and/or regulated by the control/regulation device. The electrical action can be varied in a simple manner. When the UV light source device includes UV light emitting diodes, the radiation strength can thereby be set in a simple manner (by the current) and the radiation time can be set in a simple manner (by being acted on or by not being acted on). The radiation time can in be particular be adjusted between 0.05 s and 20 s, and preferably between 0.1 s and 10 s, by the control/regulation device. The indicator properties of an activated indicator can thereby be set directly. For the same reason, it is favorable if the radiation strength can be adjusted by the control/regulation device between 25 mW/cm2 and 400 mW/cm2 and in particular between 50 mW/cm2 and 200 mW/cm2. Provision can be made for the UV light source device to radiate UV light in the wavelength range between 300 nm and 430 nm and in particular in the wavelength range between 350 nm and 380 nm. Known indicator materials can thereby be activated in a reliable manner. It is favorable for a plurality of UV light emitting diodes to be arranged in one or more rows. A large areal region can thereby be illuminated with the UV light emitting diodes. An indicator can thereby in turn be activated reliably over its total surface and/or a plurality of indicators can be activated simultaneously. It is favorable when at least one photo sensor is provided. This photo sensor can determine the radiation strength or radiation time of the UV light source device. It is thereby made possible to calibrate the UV light source device, for example. An exact control/regulation of the radiation strength/radiation time is thereby in turn also achievable over a long period. The at least one photo sensor is in particular arranged facing the UV light source device and/or a reference light source device to enable an effective detection of radiated light. A reference light source device can be provided which, for example, has the same light emitting diode type as the UV light source device; in a parallel aging process and/or with equal contamination of the light emitting diodes, the UV light source device can be calibrated with reference to the measurement results for the reference light source device. It is favorable when the UV light source device and the at least one photo sensor are arranged such that indicators to be activated can be passed between them. The at least one photo sensor can be arranged such that it is itself not shaded by indicators or by a carrier of indicators. It can also be arranged such that it only becomes effective (i.e. is radiated) when no indicators (which are in particular arranged at labels) are passed through. A calibration procedure and/or checking procedure of the UV light source device can then be carried out, for example, before insertion of a new label tape. It is preferred for the UV light source device and/or a reference light source device to have memory means for the storage of the operating time of the UV light source device and/or of the reference light source device, in particular for the storage of the operating hour count. The memory means can, for example, be non-volatile memory means, in particular a memory module arranged on a board, preferably an EEPROM. An advanced aging of the UV light source device and/or of the reference light source device can thereby be recognized on which a readjustment is no longer sensible. The memory means and the UV light source device and/or the reference light source device are preferably arranged on a common board so that, on a defect in the UV light source device and/or in the reference light source device or on the reaching of a specific and/or maximum desired operating time, the memory means and the UV light source device and/or the reference light device can be replaced together. It is particularly preferred for the control/regulation device to be arranged on a board and for the UV light source device and/or a reference light source device to be arranged on a further board separate therefrom. It is favorable for at least one checking sensor to be provided for the testing of the activation of indicators. A check can thereby be made whether an indicator was actually activated or was activated “properly” after passing through the activation device. The calibration and the function of the UV light source device can in turn thereby be checked. A feedback loop for the control/regulation of the UV light source device can be realized based on the measurement results of the checking sensor. The at least one checking sensor is in particular arranged after the UV light source device to enable an effective check. If the indicator has photochromic properties, the at least one checking sensor is preferably a color sensor. A check can be made via a color sensor whether an indicator has reached the desired color after the activation. The conditions of specific color valencies (for example RGB values) and the color density can in particular be measured by a color sensor. It is favorable for an indicator to adopt a specific color by activation, with the color varying in dependence on the time and/or the temperature after the activation. Corresponding indicator materials are described in DE 198 03 208 C2, to which reference is expressly made. The activation result can then be checked in a simple manner by a color sensor. It is furthermore an underlying object of the invention to provide a device for the provision of activated temperature-sensitive and/or time-sensitive indicators for product labeling which has a simple structure. This object is satisfied in accordance with the invention in that an activation device in accordance with the invention is provided. The activation device is in particular an application device for a UV protection filter. As a rule, indicator materials are reversible with respect to the UV light activation. The total system is made irreversible by the application of a UV protection filter onto an activated indicator since a subsequent UV light activation is no longer possible. The corresponding indicator thereby becomes secure against manipulation; that is, the time integrator properties or temperature integrator properties or time/temperature integrator properties can no longer subsequently be influenced by UV light radiation. It is favorable when a receiver is provided for a stock of activatable indicators. It is thereby made possible to activate a large number of indicators in a short time period to provide indicators for product labeling, which are activated, in a simple and fast manner. The indicators can be activated in a continuous process. The receiver is in particular designed to hold a roll. The roll is in particular a label roll. It includes, for example, a carrier tape on which labels with indicators are arranged or the roll itself is formed by a label tape, with indicators being arranged on the label tape. The labels can be self-adhesive. The indicators are in particular arranged at labels. Self-adhesive or non-self-adhesive labels can thereby be provided by means of which products can be labeled. It is favorable in this process for the labels to be able to be printed and in particular to be able to be printed outside an indicator. Additional data such as product data can thereby also be printed on the labels. The labels can, for example, be printed via thermal printing; they can be printable via thermal transfer or via direct thermal printing. Other printing methods such as ink jet printing are also possible, for example. The labels are in particular formed at a label tape or on a carrier tape. The labels are, for example, arranged at a label tape without carrier (linerless tape). For this purpose, the labels must be provided with a corresponding non-stick coating if they have an adhesive side. A UV protection filter must be able to stick to the non-stick coating. It is also possible to arrange adhesive labels on a carrier tape (liner). It is favorable if a dispensing device is provided for the dispensing of labels. Labels which are provided with an activated indicator can thereby be removed from the device or be provided by it in a simple manner. An applicator device for the application of labels to a product/product packaging can be arranged downstream of the dispensing device. The labels can then be attached, in particular automatically, to products/product packaging, for example, which are moved past on a conveyor belt. It is furthermore an object of the invention to provide a method of the initially named kind which permits variability with respect to the use of the product labeling. This object is satisfied in accordance with the invention in that the indicator is radiated with UV light and in that the radiation time and/or radiation strength is controlled and/or regulated for the setting of the temperature sensitivity and/or time sensitivity of the indicator. An operator can then set the time integrator properties or temperature integrator properties or time/temperature integrator properties of indicators, adapted to the product to be labeled, via influencing a control/regulation device. An indicator material can then be activated variably at least within specific limits. It is favorable when the indicator is illuminated via at least one UV light emitting diode. The method can thereby be carried out in a simple manner. The electrical action on the at least one light emitting diode is in particular controlled and/or regulated for the control/regulation of the radiation time and/or radiation strength. The light generation at the light emitting diode can thereby be set in a simple manner. It is furthermore favorable for the emission of the UV light source to be measured by at least one photo sensor. The system can thereby be calibrated in order thus in turn to be able to carry out a precisely adjusted activation of an indicator. It is furthermore favorable for an activation of the indicator to be checked by a checking sensor. In particular a color of the indicator is checked after the activation. A readjustment of a light source for the UV radiation can also be carried out, i.e. a calibration can be carried out, via the detection result of the checking sensor. The following description of preferred embodiments serves for the more detailed explanation of the invention in conjunction with the drawing. A first embodiment of a device for the provision of activated temperature-sensitive and/or time-sensitive indicators for product labeling, which is shown in FIG. 1 and is designated there by 10, comprises an activation device 12 for the activation of indicators. The activation device 12 has a UV light source device 14 by which indicators to be activated can be illuminated by UV light. The UV light source device 14 is formed by means of UV light emitting diodes 16 (FIG. 3). The light emitting diodes 16 are arranged in one or more rows 18a, 18b, 18c. The UV light emitting diodes 16 are preferably arranged on a straight line 20 within a row. Different rows 18a, 18b, 18c are preferably aligned parallel to one another. The UV light source device 14 is arranged such that a specific areal region can be illuminated by the UV light source device 14. Indicators 22 can be guided through this areal region. The indicators 22 are in particular arranged at a carrier 24, with the carrier 24 preferably being a (printable) label 26. A label 26 can already be printed with one or more comparison fields for an indicator 22; a comparison field is, for example, designed as a comparison color field. It is possible in this connection for the labels 26 to be separate or to form a contiguous label tape. It is furthermore possible for the carriers 24 for the indicators 22 again to be arranged on a carrier tape 28 themselves. The labels 26 are, for example, self-adhesive and the carrier tape 28 forms a liner. It is generally also possible for the labels 26 to be made free of carrier tape as linerless labels. The activation device 12 comprises a control/regulation apparatus 30 by which the light emission of the UV light source device 14 can be controlled and/or regulated with respect to radiation time and radiation strength (intensity). The control/regulation device 30 in particular controls and/or regulates the light generation at the UV light emitting diodes 16 themselves. For this purpose, the current acting on the UV light source device 14 is controlled or regulated to be able to set the intensity of radiation and the radiation time. Provision is made in this connection for the radiation time to be adjustable at least for a period between 0.05 s and 20 s, and preferably between 0.1 s and 10 s, and for the intensity of radiation furthermore to be adjustable at least in a range between 25 mW/cm2 and 400 mW/cm2, and preferably between 50 mW/cm2 up to 200 mW/cm2. The wavelength of the light which is emitted by the UV light emitting diodes 16 preferably lies between 350 nm and 380 nm. At least one UV light sensitive photo sensor 32 is associated with the UV light source device 14. This at least one photo sensor 32 is arranged opposite the UV light source device 14, with the indicators 22 being able to be guided through between the UV light source device 14 and the photo sensor 32. The radiation intensity/radiation time of the UV light source device 14 can be checked by the photo sensor 32. A calibration of the activation apparatus 12 can thereby be carried out, for example, before the insertion of a new label tape. A check can also be made by the photo sensor 32 (for example before insertion of a new label tape) whether light is being emitted at all from the UV light source device 14. A problem with the UV light source device 14 can thereby be recognized. A reference light source device 33 can also be provided which is preferably controlled in the same manner as the UV light source device 14. The reference light source device 14 in particular has one or more UV light emitting diodes of the same construction as the light source device 14. A photo sensor 35 is associated with the reference light source device 35 and is radiated by it. The photo sensor 35 and the reference light source device 33 are arranged such that the beam acting on the photo sensor 35 is not shadowed by labels being led through. For this purpose, at least the photo sensor 35 or at least the reference light source device 33 is arranged to the side of the carrier tape 28 so that UV radiation emitted by the reference light source device 33 in the direction of the photo sensor 35 is not blocked by the carrier tape 28. Since the reference light source device 33 substantially has the same properties as the UV light source device 14, the latter can be monitored—indirectly—constantly by the photo sensor 35 and can be readjusted as necessary. Generally, a photo sensor 35 arranged to the side of the carrier tape 28 can, however, also be associated with the UV light source device 14 itself, which must then be designed and arranged such that an at least small portion of the emitted light is not incident onto the carrier tape 28, but onto the photo sensor 35. The activation device 12 furthermore comprises at least one checking sensor 34 which is arranged, with respect to the carrier or carriers 24 for the indicators 22, on the same side as the UV light source device 14. This checking sensor 34 is in particular a color sensor. A check can be made by it after the UV light source device 14 whether an activation actually took place and in the required degree, that is, whether the desired energy transfer to the indicators 22 has actually taken place. Defective and/or incorrectly exposed indicators 22 can hereby be recognized and eliminated. An automatically working or manually operable external checking sensor can also be provided, instead of or in addition to the checking sensor 34 disposed downstream of the UV light source device 14, to check the correct activation at least randomly. It is generally also possible for a checking sensor to be integrated into a printing device explained in more detail in the following. For example, a control loop can be realized with the help of the photo sensor 32 and/or 35 and the control/regulation device 30, and the aging and/or a contamination of the light sources of the UV light source device 14 (that is, the UV light emitting diodes 16) is automatically eliminated by it in that the intensity of radiation and/or the radiation time is readjusted automatically in accordance with the aging and/or the contamination. It is generally also possible for no photo sensor 32 or 35 and only one checking sensor 34 to be provided which, together with the control/regulation device 30, forms a control loop via which the aging and/or a contamination of the light sources of the UV light source device 14 is automatically eliminated. The photo sensor 32 (and optionally the photo sensor 35) and the checking sensor 34 transfer their sensor signals to the control/regulation device 30 via corresponding lines. This transmits its control signals or regulation signals to the UV light source device 14 via a corresponding line. The device 10 comprises a receiver 36 to hold a roll 38. The roll 38 is, for example, a carrier tape roll with a carrier tape 28 which can be unwound and on which the indicators 22 are arranged at corresponding carriers 24 (for example labels 26). The carrier tape 28 is guided between the UV light source device 14 and the photo sensor 32 and is guided past the checking sensor 34. The receiver 36 comprises a holding mandrel 40 for the roll 38, for example. Generally, different types of indicators can be provided which in particular differ with respect to their color and/or the radiation energy required for the activation. Different types of indicators can, for example, be used for different types of meat. Indicators of one kind can in each case be wound up on a roll 38, with different kinds of rolls differing by the type of their indicators. It can then be ensured by means of the photo sensor 32 or 35 or of the photo sensors 32, 35 that the energy transfer desired for the respective indicator type takes place. It is made possible by the combination of one or two photo sensors 32, 35 and a checking sensor 34 to determine whether a “correct” roll was inserted for the product to be labeled in each case with the corresponding indicators 22. It can initially be ensured in this connection by means of the photo sensor or photo sensors 32, 35 that the energy transfer desired for the respective indicator type takes place. After the activation, a coloration and/or intensity value of the indicators 22 can be determined by means of the checking sensor 34, for example. If the value found differs from the expected value for the respective indicator type, it can be concluded, in particular if other error sources are eliminated, that an “incorrect” roll had been inserted. A holding device 42 can be provided which in particular comprises a holding mandrel 44 by which a roll 46 with a wound-on carrier band is held. The device 10 comprises a guide element 48 via which the carrier tape 28 is guided to the holding device 42. A dispenser device 50 for labels is formed at or in the proximity of the guide element 48. Labels 51 can be peeled off the carrier tape 28 at the dispenser device 50 and can be removed from the device 10. (The device 10 is then a labeling device.) The dispenser device 50, for example, comprises a wedge-shaped element 52 with a dispensing edge 54. The roll 46 is formed by a label-free carrier tape, that is, a carrier tape, which is label-free due to peeling off of labels 51 at the dispenser device 50. An applicator device 55 can be arranged after the dispensing device 50 and labels 51 can be applied to products or product packaging via it. An automatic label application can thereby be realized. Labels (with activated indicators 22) are, for example, automatically applied to products/product packaging which are guided on a conveyor belt. The applicator device 55 is made, for example, as a blow applicator, plunger applicator or pressing applicator. Provision can be made for the holding device 42 to be driven by a drive 56 to wind up the carrier tape accordingly. It is also possible for the labels themselves to form a tape so that no carrier tape is provided (linerless labels). The guidance of the corresponding label tape in the device 10 is then made such that elements of the guide, which come into contact with an adhesive side of the label tape if the labels are self-adhesive, are provided with an anti-stick coating. The device 10 comprises at least one printing device 58. The printing device 58 itself has a print head 60 and a mating element and in particular a print roll. The guide element 48 is in particular made as a print roll. The device 10 moreover has an application device 62 by which a UV protective filter can be applied to an indicator 22 after its activation. A protection of an indicator against manipulation is achieved by the UV protective filter; an indicator 22 cannot be activated again after application of the protective filter so that the device 10 provides irreversibly activated indicators 22. A UV protective filter can be applied to an indicator 22 via a tape 64 via the application device 62, with the tape having corresponding UV protective filter properties. The application device 62 comprises for this purpose a tape guiding device 66 via which the tape 64 can be guided such that UV protective filters can be applied to the activated indicators 22. The tape 64 comprises, for example, a UV protective filter and is made transparent; it can also be self-adhesive. It is applied to respective applicators 22 in part elements (as labels) or continuously. The tape guiding device 66, for example, comprises a first roll holder 68 and a second roll holder 70. A tape roll can be placed onto the first roll holder 68 and the tape can be unwound from there. A roll can be wound up via the second roll holder 70. The second roll holder 70 is driven, for example. The device 10 can be made in compact form. It is made as a hand-held device, for example. It can also be integrated into a labeler with an applicator device 55. Labels can then be provided having activating indicators 22 and can be applied automatically to products/product packaging. In a second embodiment of a device in accordance with the invention, which is shown in FIG. 2 and is designated by 72 there, an activation device 12 is provided which is generally configured the same as the activation device 12 of the device 10. The same reference numerals are therefore used for this activation apparatus of the device 72. The receiver for a roll 38 is likewise made the same so that the same reference numerals are used. The dispenser device is also generally made the same as described above. The device 72 comprises a tape guiding device 74 for a transfer tape 76. The transfer tape 76 is a thermal transfer tape, for example. The tape guiding device 74 has a first roll holder 78 and a second roll holder 80 between which the transfer tape 76 is guided. The transfer tape 76 is in particular unwound from a roll which is seated at the first roll holder 78 and can be wound up at a roll which is seated on the second roll holder 80. The second roll holder 80 is driven by a drive 82, for example. The device 72 comprises a printing device 84 having a print head 86 and a print roll as a mating element 88. Labels 26 at a label tape or on a carrier tape 28 are guided between the print head 86 and the mating element 88. The tape guiding device 74 is made such that the transfer tape 76 is led past the print head 86. The transfer tape 76 comprises a UV protective filter material. It can then be applied to corresponding activated indicators 22 by the print head 86. The print head 86 can be controlled such that UV protective filter material can be applied directly onto the indicator 22 in accordance with its geometrical dimensions. It is generally possible in this connection (if the transfer tape 76 is suitable for it) also to print corresponding labels 26 with information such as product information outside the indicator 22 by the printing device 84. It is also possible for a second printing device 90 to be provided in addition to the printing device 84 (first printing device) which can be arranged between the printing device 84 and the activation device 12 or can be arranged downstream of the printing device 84. The second printing device 90 in particular comprises a print head 92 and a mating element 94. Information can be printed on labels 26 by the second printing device 90 independently of the printing device 84. Provision can also be made for the device 72 to provide labels having indicators 22 which are activated, provided with UV protective filters and are coupled into a labeling apparatus with a printing device in order to print the labels outside the indicators 22 with information such as product data. It is favorable in this case for the apparatus 72 not to provide individual labels, but a tape such as a label tape or a carrier tape 28 with non-peeled labels. The apparatus 10 and 72 work as follows: An indicator 22 is made from a material which can be activated by UV light and is temperature-sensitive and time-sensitive; that is, after the material has been stimulated, the deenergizing depends on the time after the stimulation and on the temperature. The indicator 22 is in particular a time/temperature indicator having an integration effect with respect to time and temperature. The starting time is determined by the activation time. Examples for indicator materials are rechargeable, crystalline indicators embedded into a matrix and having photochromic properties based on transfer reactions. Such materials are described, for example, in DE 198 03 208 C2, to which reference is expressly made. An indicator can, for example, have different colors depending on the time and on the temperature. Provision can be made for at least one fixed comparison color field to be arranged at an indicator 96 (FIG. 4) so that the status can immediately be recognized with the eyes. For example, a first dark color field 98 is provided which indicates the color directly after the activation. A second color field 100 can be provided which indicates the color after a medium time period—under the same temperature conditions. A third color field 102 can be provided which indicates the color after a longer time period—under the same temperature conditions. The colors of the color fields 98, 100 and 102 are fixed. The color of the first color field, for example, symbolizes a “fresh” state; the color of the second color field 100 a “medium” state; and the color of the third color field 102 symbolizes a “no longer fresh” state, for example. If only one comparison color field is provided, it symbolizes a state “to be used”, for example. The color-changing indicator 96 is, for example, circular with the color fields 98, 100 and 102 surrounding the indicator in the manner of a ring segment. The color of the indicator 96 changes in accordance with the activation time/temperature integral, as indicated in FIG. 4. At higher temperatures, the color of the indicator 96 changes faster than at lower temperatures with time. Such an activated indicator 96 can be used for product labeling. After application of a corresponding product labeling with an indicator 96, this indicator 96 runs through the same time development and temperature development as the product labeled by the indicator 96; that is, it is subject to the same time conditions and temperature conditions. The state of the product and in particular the degree of freshness of the product can thereby be visualized by the temperature-sensitive and time-sensitive indicator 96. Foodstuffs can thereby, for example, be labeled with respect to their degree of freshness. The start time is set by the time of activation. The indicators 96 are supplied to the activation apparatus 12 for this purpose, where an activation by UV light takes place. Due to the activation by UV light, transfer reactions are, for example, photochemically induced in the indicator material, with fading times of different lengths being able to be achieved in dependence on the bonding strength of an acceptor of the transferred species in the acceptor material (cf. DE 198 03 208 C2). The intensity of radiation and/or the radiation time of the radiation with UV light of corresponding indicators 22, 96 can be set by the control/regulation device 30. The time sensitivity and/or temperature sensitivity of an activated indicator 22 can thereby be set in at least a certain range. For example, with an increased intensity of radiation, a longer fading time can be achieved (with respect to the same temperature conditions). An operator can therefore set the desired properties via the control/regulation device 30. A calibration of the UV light source device 14 can be carried out via the photo sensor 32 and a monitoring can be made of whether a defect is present with respect to the lighting. A check can be made via the checking sensor 34, which is in particular a color sensor, of whether an indicator 22 has reached the desired color by the activation. A UV protective filter is applied to an activated indicator 22 by the application device 62 or the printing device 84 (which serves as an application device). The indicator 22 is thereby made safe against manipulation since a repeated activation by UV light is no longer possible; that is, the activation is made irreversible by the UV protective filter. A repeated UV light activation would only be possible by removal of the UV protective filter (which results in a destruction of the indicator 22). Provision can also be made for a UV protective filter to be applied to the comparison color field or fields. The color comparability can in particular thereby be optimized when a UV protective filter is not completely transparent for light in the visible spectrum. The UV protective filter is applied to the indicators 22 via a tape, with the tape being able to be applied directly or (as described with reference to the apparatus 72) with a transfer of UV protective filter material taking place from the transfer tape 76 to an activated indicator 22. The transfer tape 76 is in particular a thermal transfer tape, such as a carbon tape, on which corresponding UV protective filter material is arranged. It is transferred onto the indicator 22 via the printing device 84 having the print head 86. The print head 86 can be controlled such that UV protective filter material is “printed” onto the indicator 22 in accordance with the geometrical dimensions thereof. The present components of a labeling apparatus having a thermal transfer printing apparatus can thereby be used to arrange a UV protective filter on indicators 22. The indicators 22 are arranged on carriers 24 such as labels 26. The labels 26 are in turn arranged on a carrier tape 28 or are themselves formed on a label tape. The indicators 22 are guided past the UV light source device 14 for activation. The UV protective filter material is applied after activation. Provision can be made for the corresponding labels 26 to be printed with information such as product data outside the indicators 22. This printing can take place by the apparatus 72 itself (by the second printing device 90 there) or outside the apparatus 72. It is generally also possible, if a suitable transfer tape 76 is present, for a printing of the labels 26 to take place outside the indicators 22 by the printing device 84. It is also possible for labels 26 provided by the device 72 and provided with activated indicators 22 to be supplied to a labeling device in which they are printed.
	description	The present application is a continuation of and claims priority to U.S. application Ser. No. 11/553,625, filed Oct. 27, 2006 (now allowed), which is hereby incorporated by reference in its entirety. The present invention relates to systems, devices, and methods for filling capsules and other types of containers with radioactive and/or other types of potentially hazardous materials. A number of scientific uses require relatively small aliquots of radioactive materials. For example, nuclear medicine employs solutions of radioisotopes, such as Technetium-99m, Iodine-123, Iodine-125, Iodine-131, Phosphorous-32, Indium-111, Cobalt-57, and Chromium-51, as radiopharmaceuticals or as radioactive tracers. These radioisotopes typically are measured and dispensed for use. However, for safety reasons, it is highly desirable that the technician responsible for measuring and dispensing radioisotopes be exposed to minimal radioactivity. It is also desirable in some instances that the actual radioisotope doses be empirically determined in terms of radioactivity. Thus, techniques for dispensing small volumes of radioactive materials are needed. In one aspect, the present invention provides systems for filling containers with radioactive and/or other types of potentially hazardous materials. Preferred systems are those that deposit one or more radioactive materials in relatively small containers such as capsules or small vials. Such systems typically comprise a shielding material that substantially defines a chamber and, preferably, substantially blocks radioactivity, a conduit extending through the shielding material into the chamber, and a securing unit that is disposed in the chamber proximal to the conduit and is adapted to receive a container through the conduit. The systems of the present invention can further comprise filling devices, at least one solution delivery device that is disposed in the chamber and adapted to meter an aliquot from a radioactive stock solution and inject the aliquot into the container; at least one of a logic device that controls the solution delivery device, and/or a tapered guide lid that is positioned over the radioactive stock solution. The present invention also provides filling methods that involve, for example, using the conduit to place a first container in the securing unit, metering an aliquot from a radioactive stock solution, and injecting the aliquot into the container. The present invention provides systems for filling containers with radioactive and/or other types of potentially hazardous materials. Potentially hazardous materials according to the invention are those that present or are suspected to present one or more types of health risks to a human who is exposed to the material. Representative materials according to the invention include chemicals and biological agents including but not limited to poisons, toxins, mutagens, and teratogens. Materials of particular interest with respect to the present invention are those that emit one or more radioactive species. Containers according to the invention are vessels that can contain or substantially contain a potentially hazardous material of interest. Vessels that contain the material include sufficient structure to surround it; vessels that substantially contain the material bound it with sufficient structure to restrict its movement in one or more directions. Containers of particular interest with respect to the present invention are those (such as capsules, tubes, ampoules, and vials) that are relatively small (i.e., have a volume less than about 10 mL, more preferably less than about 1 mL. The systems of the invention include a shielding material that substantially defines a chamber. Any of a wide variety of shield materials can be used that provide an effective barrier to the potentially hazardous material and are either capable of forming a substantially closed surface shape that substantially defines a chamber or being disposed upon a substantially closed-surface shape that substantially defines chamber. Thus, a shielding material that substantially defines a chamber need not do so alone. Representative shielding materials include metals, alloys, and/or polymers; shield materials of particular interest are those (such as lead, tungsten, and other suitable metals and alloys) that provide an effective barrier to radioactive species. Preferably, the shielding material is at least as effective as lead. Chambers according to the invention can have virtually any shape, although substantially rectangular chambers and substantially cylindrical chambers are probably most common. The systems of the invention include a conduit extending through the shield material into the chamber. Conduits according to the invention are substantially hollow structures that supply a pathway for introducing containers to the chamber. The conduit may be made from any suitable material such as, for example, lead, tungsten, and other metals and allows that provide an effective barrier to radioactive species. In cross-section, the conduit may have any shape, provided that the shape allows the container to pass through the conduit. Preferably, the shape of the conduit substantially corresponds to the shape of the container. In certain embodiments of the invention, conduits can be interchangeable such that each is adapted for use with specific containers. Conduits according to the invention can optionally include a device or other structure that permits manipulation objects within the chamber. One such representative device is a tamping rod that engages and helps seal the container. The systems of the invention also include a securing unit that is disposed in the chamber proximal to the conduit and is adapted to receive a container through the conduit. Securing units according to the invention generally are capable of receiving at least one container and, preferably, more than one container. The portion of the securing unit that receives the container preferably has a shape that corresponds to the shape of the container. In embodiments in which the securing unit receives more than one container, the securing unit can be capable of being indexed, that is, of moving each container sequentially past a given work area. Indexing is useful for allowing the securing unit to receive further containers, to allow the containers to be filled, and/or to move the containers to an area where they may be removed from the securing unit. Preferably, the securing unit is a carousel, but all shapes that allow indexing, for example, a rectangle with an array of ports, are contemplated. FIG. 1 shows one representative filling system 10 according to the invention having a shield material 12 and a window 14 disposed therein for viewing the chamber. The window 14 may be formed from any substantially transparent, radiation-shielding material, such as leaded glass, in any of the many known configurations. For example, the window 14 may a single layer of leaded glass or a plurality of layers having an inert gas or a shielding oil disposed between them. The system shown in FIG. 1 also includes a plurality of doors 16-18 for accessing the chamber. These doors may be constructed of any suitable shielding material, and may comprise handles, hinges, locks, or other features typically found on doors. It is understood that the number of doors and windows may be varied within the spirit of the invention. A plurality of rods 20-26 extend through shield 12 and into the chamber that it defines. At least one of the rods 20-26 is hollow, and thus can serve as a conduit through which a container can pass into the chamber. A removable tamper 27 can be disposed in the conduit to minimize or prevent radiation leakage and provide a structure that can be used to move or otherwise contact a container that has been placed in the chamber. In embodiments in which capsules are placed in the chamber, the rod can be used to tamp a cap upon the capsule. At least one of the rods 20-26 is rotatable to provide movement of components disposed inside the chamber, as will be described with regard to FIG. 2. The system 10 is optionally placed on a table 28 or some other type of support. Table 28 has a plurality of legs 30-33, a top 34, and a base 36. Although not depicted, table 28 may further comprise at least two wheels to provide mobility, preferably four wheels. In the particular embodiment shown in FIG. 1, an optional dose calibrator 38 having a stand 40 is associated with system 10. The dose calibrator 38 is provided with the necessary logic and components to measure the radioactivity of the dispensed materials to confirm dosage. Dose calibrators are commercially available from Capintec Inc., Ramsey, N.J., USA. Turning now to FIGS. 2 and 3, the chamber contains a securing unit 50 having a plurality of ports 52 to receive a plurality of containers 54. Although the securing unit 50 is depicted as a carousel, those skilled in the art will appreciate that other designs are contemplated. In the embodiment depicted, the container 54 is a capsule, although all type of containers can be used. Suitable capsules are well known to those skilled in radiopharmaceutical preparations, and include those commercially available from Capsugel, Greenwood, S.C., USA. In this embodiment, containers 54 are introduced to the ports 52 via a conduit formed in the rod 23, as will be described with reference to FIG. 3. It is understood that the conduit has a sufficient diameter to allow the container to pass. In certain embodiments of the invention, the conduit is treated (as, for example, with a lubricant) to reduce friction. A locator 56 is provided in the chamber for placement of a stock solution container 58 of radioactive materials to be dispensed. The stock solution container 58 preferably is made of lead or tungsten. As will be further described with respect to FIG. 4, a guide 60 is attached to the rod 26 and disposed proximal to the locator 56. A solution delivery device 62 rotates around an axis substantially defined by rod 25 and is movable between a position proximal to the securing unit 50 and a position proximal to the stock solution container 58. The solution delivery device 62 is used to fill container 54 with stock solution. As depicted, the solution delivery device 62 is a syringe. Suitable syringes and other types of devices for filling containers are well known to those skilled in radiopharmaceutical preparations, and include those commercially available from Becton Dickson, Franklin Lakes, N.J. USA or Qosina, Edgewood, N.Y., USA. A relatively long 22G needle is suitable for piercing a capsule such as described above. An optional guide (see structure 108 in FIG. 5) can be used to guide the needle of the solution delivery device 62 to container 54. The solution delivery device 62 is associated with dispensing controls to allow accurate dispensing of the radioactive materials in selected volumes. Although doses may be determined in terms of radioactivity, it is helpful to accurately dispense certain volumes of stock solution to attain the desired radioactivity. In one embodiment, the volume of a dispensed aliquot of stock solution is about 1 μL to about 10,000 μL. Preferably, the volume of the aliquot is about 1 μL to about 500 μL, more preferably about 2 μL to about 200 μL. In one embodiment, the volume of the aliquot is less than about 1000 μL. Those skilled in the art will understand that term “filling” as used herein includes placing any volume of solution in a container, and does not require placing therein a volume that that corresponds to the container's capacity. Metering of the aliquot can be effected through operation of a computer control means. Control means amenable to the practice of this invention include computing devices such as microprocessors, microcontrollers, capacitors, switches, circuits, logic gates, or equivalent logic devices. In one embodiment, the controls provide a plurality of volumes from which to select. Alternatively, the controls can provide for data entry to specify the volume desired. The controls may also be used to achieve a certain dosage. For example, if the concentration of stock solution is provided, the controls may calculate the volume required to attain a certain radioactive dose. Moreover, if a dosage of a certain radioactivity will be required for administration later, for example, two days later, the controls can account for the radioactive decay rate by dispensing an aliquot which has a radioactivity greater than the desired dosage by an amount representing the decay factors occurring over the time between dispensing and administration. Those skilled in the art will readily appreciate these and other desirable features of the controls based on the foregoing, as well as how to obtain them, such as by programming. For use in dispensing radiopharmaceuticals or other types of potentially hazardous material, the solution delivery device 62 may require rinsing or sterilizing. A plurality of optional holding containers 64-66 are provided for receiving the needle of the solution delivery device. These holding containers 64-66 may contain conventional rinse or sterilization solutions. In certain embodiments, the rinse solution is water or isopropyl alcohol. A second locator 68 is provided in the chamber for indicating placement of a shipping container 70 for receiving a shipping vial 71. The shipping container 70 preferably is made of lead, tungsten, alloys, or any material with a density greater than or equal to lead, provided it substantially blocks radioactivity. The shipping vial 71 is necessarily smaller than the shipping container and is the vessel in which the container(s) are actually placed. The shipping vial preferably is plastic. The shipping container 70 and the shipping vial 71 have substantially similar shapes at their interface. The shapes cooperate to prevent the shipping vial 71 from rotating when capped or uncapped. In one embodiment, the distal end of the rod 21 (not depicted) is adapted to grasp the cap of the shipping vial. This rod 21 assembly can also lift the shipping vial 71 for visual inspection. A container transfer assembly 72 is attached to the rod 24 and includes a receiver (118, FIG. 6) that is adapted to engage a container and remove it from the securing unit 50. The transfer assembly 72 then places the container 54 in the shipping vial 71. In one embodiment, the transfer assembly 72 operates by creating a snug fit between receiver (118, FIG. 6) and container 54. The container may be released applying a force to the container sufficient to overcome the snug fit, as will be discussed with reference to FIG. 6. A vial transfer assembly 74 is attached to the rod 20 and includes a receiver that is adapted to engage the shipping vial 71 and remove it from the shipping container 70. The vial transfer assembly 74 then places the shipping vial 71 in the dose calibrator 38 (FIG. 1) via an access port 76. The access port 76 can be brought closer to the dose calibrator by an optional actuator 78 such as a pneumatic cylinder with associated controls. The vial transfer assembly 74 can be used to recapture the shipping vial 71 after the dose calibrator 38 (FIG. 1) determines the dosage and to place the shipping vial back in the shipping container 70. The capped shipping vial may receive an aluminum seal to indicate it has been secured. In certain embodiments, the aluminum seal is crimped on the capped shipping vial. The capped shipping vial may alternatively receive a screw cap or a snap cap to indicate it has been secured. Referring to FIG. 3, the securing unit 50 is rotatable around the axis substantially defined by rod 22, as depicted by double headed arrow A, to allow the various ports 52 to come proximal to rod 23. Each port 52 may comprise a bore 80 and a port insert 82 disposed within the bore. A variety of shapes are contemplated for the port inserts 82, provided that the shapes have complementary surfaces to accommodate the desired container. In operation, a container, such as a capsule, is passed down the conduit 84 of the rod 23 along an axis C and received in the port 52 proximal to the distal end of the rod. The securing unit 50 is then indexed in either direction indicated by arrow A, to bring an empty port 52 proximal to rod 23 to receive another container. Alternatively, the securing unit could remain stationary and the rod 23 could be provided to move around the securing unit to allow indexing. In certain embodiments, the rod 23 is lowered to the securing unit 50, as depicted by double headed arrow B, to dispose the container in the port 52. This allows the container to be properly aligned. Thus, in embodiments where the rod 23 can be lowered to the securing unit 50, the securing unit and the conduit are adapted to move with respect to each other in a first plane and a second plane. A rod that is adapted to pass through the conduit 84 and engage the container may be provided. This rod may be used to tamp a cap on a filled capsule, for example. Turning now to FIG. 4, the stock solution container 58 surrounds a vial 86 of a stock solution such as, for example, Technetium-99m, Iodine-125, Iodine-131, Phosphorous-32, Indium-111, Cobalt-57, and/or Chromium-51. Stock solution vials conventionally are capped with an aluminum layer 88 and a rubber septum 90. A guide lid 92 according to certain embodiments of the present invention is adapted to be placed on the stock solution container 58 to guide the solution delivery device 62 to the stock solution vial 86. The guide lid 92 may be formed from, for example, lead or tungsten, and has a generally tapered inner wall 94 that can direct objects placed therein to the central portion of the area that the wall defines. Those skilled in the art will recognize that this inner wall need not have the continuously sloping surface depicted in FIG. 4, but simply should taper to the extent necessary to direct objects placed therein to its central portion. In certain embodiments, the guide 60, attached to the rod 26 via a plate 96, is also provided to guide the solution delivery device 62 to the stock solution vial 86. The guide 60 can include a relatively thick 16G needle 98 suitable for piercing the aluminum layer 88 and the rubber septum 90 of the stock solution vial. The gauge of the needle 98 should generally be sufficiently large to allow a needle 100 of the solution delivery device 62 to pass through it, thus allowing the needle 100 to reach the stock solution to draw an aliquot as described above. Referring to FIG. 5, a filling guide 102 is provided comprising a rod 104, a plate 106 attached to the rod 104, and a tapered guide member 108 attached to the plate. The solution delivery device 62 typically retains an amount of stock solution 109. The generally tapered guide member 108 reinforces the needle 100 of the solution delivery device 62 to facilitate piercing of the container 54 to deliver the aliquot and directs the needle to the central portion of the guide member. In certain embodiments, the plate 106 acts as a stop to prevent the needle 100 from protruding too far into container 54. Turning to FIG. 6, container transfer assembly 72 is shown having a first plate 110 and a second plate 112 attached to the rod 24. A pin 114 is disposed between the plates 110 and 112, and is actuated by an actuator 116. The pin 114 is optional, as the transfer assembly 72 could be tapped against the shipping vial to remove the container or a pneumatic force could be used in place of the pin and actuator. A flexible plastic apron 118 is disposed in the transfer assembly 72 to engage a container in a snug fit. The fit should be sufficient tight to allow the container to be lifted from the port 52, but not so tight as to damage the container upon application of a force required to release it from the apron 118. The transfer assembly 72 engages the container, removing it from the securing unit 50, and can be used to place the container in a shipping vial 71. In operation, a container is placed in the securing unit via the conduit and an aliquot from a radioactive stock solution is metered out and injected into the container. The securing unit may be indexed and another container injected with an aliquot from a radioactive stock solution. The radioactive stock solutions can be the same or different, and the volumes of the aliquots can be the same or different. Referring to FIG. 7, a system is depicted comprising a filling system 10, a logic device 120, a data entry device 122, and traces 124 for electrically connecting the components are provided. The filling system 10 is described above. The logic device 120 may be the same or different as the control means described above, and includes computing devices such as microprocessors, microcontrollers, capacitors, switches, circuits, logic gates, or equivalent logic devices. The data entry device 122 may be a keyboard, a notepad, a dial, or a series of setting switches. Certain features are, for clarity, described herein in the context of separate embodiments, but may also be provided in combination in a single embodiment. Conversely, various features that are, for brevity, described in the context of a single embodiment, may also be provided separately or in any subcombination. Further, reference to values stated in ranges include each and every value within that range. After reading the concepts that have been described with reference to specific embodiments, skilled artisans will appreciate that other aspects, modifications, changes, and embodiments are possible without departing from the scope of the invention as set forth in the claims below. Accordingly, the specification and figures are to be regarded in an illustrative rather than a restrictive sense, and all such modifications are intended to be included within the scope of invention. Many aspects and embodiments have been described above and are merely exemplary and not limiting. Benefits, advantages, solutions to problems, and any feature that may cause the same to occur are not to be construed as a critical, required, or essential feature of any or all the claims.
	abstract	Provided are an ion implanter for compensating for a wafer cut angle and an ion implantation method using the same. The ion implanter may include an orienter for rotating a wafer mounted on an alignment stage thereof to align a notch of the wafer and a wafer stage for mounting thereon the wafer whose notch has been aligned. The ion implanter may further include an ion implantation angle adjustment unit for adjusting an angle of the wafer stage, a cut angle measurement unit for measuring the wafer cut angle while the wafer is mounted and rotated on the alignment stage, and a controller for controlling the ion implantation angle adjustment unit to compensate for the measured wafer cut angle.
	description	This application claims priority to the benefit of U.S. Provisional Application No. 61/085,106, filed on Jul. 31, 2008, the entire content of which is incorporated herein by reference. 1. Field This application relates to products, such as flood sources, that are used to calibrate radiation detection devices, such as gamma cameras. 2. Background of Related Art Radiation detection devices, such as gamma cameras, often require testing and/or calibration to ensure that their sensitivity is uniform over the area that they detect. Devices that produce a uniform cross-section of radiation, such as a flood source, are commonly used for this purpose. A flood source typically includes a flat surface, such as a sheet of paper, on which radioactive isotopes are printed. For obvious safety and other reasons, paper that has been impregnated with radioactive isotopes must be readily identifiable as having an active area. One approach for achieving this has been to mix a radioactive isotope solution with ink before it is printed on the paper, such as is described in U.S. Pat. No. 7,172,799, the entire content of which is incorporated herein by reference. The ink in the active area on the paper remains visible after the mixture is printed, thus signaling that the paper has an active area and where it is. Mixing ink with the radioactive isotope solution, however, may adversely affect the uniformity of the isotope in the solution. This approach may also require a substantial amount of ink, which may be costly. A radioactive carrier solution may be printed on paper without a pigment, such as ink. A visible border, such as a border made of ink, may be printed around this active area. The radioactive isotopes and the ink may be printed at substantially the same time on the same plotter, but through separate print heads. An embodiment of the present invention provides a method for forming a radiation flood source. The method includes the steps of preparing a radioactive isotope carrier solution; loading the radioactive isotope carrier solution into a radioactive isotope carrier solution cartridge; loading a separate border cartridge into a plotter; selecting and configuring a shape of an active area; setting a border to be placed around the active area; printing the active area by utilizing the radioactive isotope carrier solution cartridge on a sheet substrate; and printing the border by utilizing the separate border cartridge on the sheet substrate. In one embodiment, the method further includes the steps of laminating the printed sheet substrate to block radioactive isotopes on the active area from separating from the active area; and placing the laminated printed sheet substrate in a protective housing. In one embodiment, the method further includes the steps of cutting an active sheet around the printed border from the printed sheet substrate; laminating the active sheet to block radioactive isotopes on the active area from separating from the active area; and placing the laminated active sheet in a protective housing. In one embodiment, the method further includes the steps of cutting an active sheet around the printed border from the printed sheet substrate; laminating the active sheet to block radioactive isotopes on the active area from separating from the active area; testing the laminated active sheet to verify an integrity of the active area; and placing the tested active sheet in a protective housing. In one embodiment, the step of preparing the radioactive isotope carrier solution includes: drying a radioactive isotope solution to form dried radioactive isotopes; and mixing the dried radioactive isotopes with a pigmentless carrier solution to prepare the radioactive isotope carrier solution. In one embodiment, the active area is printed only by the radioactive isotope carrier cartridge, and the border is printed only by the border cartridge. In one embodiment, the radioactive isotope carrier solution includes an active material composed of radioactive isotopes selected from the group consisting of Cobalt 57, Iodine 125, Palladium 103, Barium 133, Carbon 14, Gadolinium 153, Phosphorus 33, Tellurium 99, and combinations thereof. The radioactive isotope carrier solution may be formulated with a pigmentless carrier solution comprising cobalt chloride, ethylene glycol, glycerin, and hydrochloric acid and to have a viscosity adapted for being inkjet printed on the sheet substrate. The pigmentless carrier solution may be composed of a mixture of 600 mg of cobalt chloride, 10 ml ethylene glycol, 10 ml glycerin, and 80 ml of 0.1M hydrochloric acid. In one embodiment, the radioactive isotope carrier solution is a pigmentless radioactive isotope carrier solution; the step of printing the active area includes printing the active area by utilizing only the pigmentless radioactive isotope carrier solution; the separate border cartridge is composed of a pigmented ink solution; and the step of printing the border includes printing the border around the area by utilizing only the pigmented ink solution. Another embodiment of the present invention provides a plotting system for forming a radiation flood source. The plotting system includes a sheet substrate supply, a radioactive isotope carrier solution cartridge, a separate border cartridge, and a controller. Here, the sheet substrate supply is configured to provide a sheet substrate. The radioactive isotope carrier solution cartridge contains a radioactive isotope carrier solution and is configured to print an active area onto the sheet substrate. The separate border cartridge is configured to print a border around the active area on the sheet substrate, and the controller is configured to control the radioactive isotope carrier solution cartridge to print the active area onto the sheet substrate and the separate border cartridge to print the border around the active area on the sheet substrate. In one embodiment, the radioactive isotope carrier solution cartridge is an inkjet cartridge. In one embodiment, the radioactive isotope carrier solution is a mixture of dried radioactive isotopes and a pigmentless carrier solution. In one embodiment, the active area is printed only by the radioactive isotope carrier cartridge, and the border is printed only by the border cartridge. In one embodiment, the radioactive isotope carrier solution includes an active material composed of radioactive isotopes selected from the group consisting of Cobalt 57, Iodine 125, Palladium 103, Barium 133, Carbon 14, Gadolinium 153, Phosphorus 33, Tellurium 99, and combinations thereof. In one embodiment, the radioactive isotope carrier solution is formulated with a pigmentless carrier solution comprising cobalt chloride, ethylene glycol, glycerin, and hydrochloric acid and to have a viscosity adapted for being inkjet printed on the sheet substrate. The pigmentless carrier solution may be composed of a mixture of 600 mg of cobalt chloride, 10 ml ethylene glycol, 10 ml glycerin, and 80 ml of 0.1M hydrochloric acid. In one embodiment, the separate border cartridge contains a pigmented solution composed of color pigments selected from the group consisting of black pigments, cyan pigments, yellow pigments, magenta pigments, and combinations thereof. Another embodiment of the present invention provides a radiation flood source that includes a paper sheet; a pigmentless radioactive fill printed on the paper sheet and comprising radioactive isotopes selected from the group consisting of Cobalt 57, Iodine 125, Palladium 103, Barium 133, Carbon 14, Gadolinium 153, Phosphorus 33, Tellurium 99, and combinations thereof; and a pigmented border printed on the paper sheet and around the pigmentless radioactive fill. In one embodiment, the radiation flood source further includes a first protective sheet laminated with the paper sheet with the radioactive isotopes therebetween. Here, the radiation flood source may also include a second protective sheet and the paper sheet being laminated between the first protective sheet and the second protective sheet. In one embodiment, the radiation flood source further includes a housing having an interior space housing the paper sheet with the pigmentless radioactive fill. Here, the radiation flood source may also include a spacer also housed in the interior space of the housing and between an interior side of the housing facing the paper sheet and the paper sheet. In one embodiment, the pigmentless radioactive fill further includes a pigmentless carrier material. In one embodiment, the pigmented border includes color pigments selected from the group consisting of black pigments, cyan pigments, yellow pigments, magenta pigments, and combinations thereof. In one embodiment, the pigmentless radioactive fill is transparent to visible light. These, as well as other components, steps, features, objects, benefits, and advantages, will now become clear from a review of the following detailed description of illustrative embodiments, the accompanying drawings, and the claims. Illustrative embodiments are now discussed. Other embodiments may be used in addition or instead. Details that may be apparent or unnecessary may be omitted to save space or for a more affective presentation. Conversely, some embodiments may be practiced without all of the details that are disclosed. Also, in the context of the present application, when an element is referred to as being “on” another element, it can be directly on the another element or be indirectly on the another element with one or more intervening elements interposed therebetween. FIG. 1 illustrates a plotting system for printing bordered, pigmentless radioactive areas on paper. As illustrated in FIG. 1, a computer 101 may be connected to a plotter 103. The computer 101 may be of any type. The computer 101 may be configured to control the plotter 103 and, in particular, to cause the plotter to print various shapes and borders around those shapes. The computer 101 may be configured to print the borders around the shapes in a color that is different from the fill area within the shape. The computer 101 may be configured to control other typical printing functions, such as paper feeding, paper cutting, and the density of what is printed. The computer 101 may be configured to do the other things discussed herein. The plotter 103 may be of any type. For example, the plotter 103 may be a wide format plotter, such as a Hewlett-Packard model 450C. The plotter 103 may be configured to print on paper through one or multiple print heads. Each print head may be associated with a cartridge having its own printing solution. The plotter 103 may be configured to feed paper, cut paper, and/or control the location and density of printing on paper. The plotter 103 may be configured to do each or all of these things, as well as the other things discussed herein, in response to commands from a computer, such as the computer 101. The computer 101 may be connected to the plotter 103 through a wired or wireless connection or both. The connection may be direct or it may be through a local area network and/or wide area network. Although not illustrated in FIG. 1, multiple plotters may be driven by the computer 101. Similarly, the plotter 103 may be connected to multiple computers. FIG. 2 is a block diagram of a plotting system for printing bordered, pigmentless radioactive areas on paper. The block diagram may be illustrative of the plotting system illustrated in FIG. 1 and/or other types of plotting systems. Similarly, the plotting system illustrated in FIG. 1 may contain components different than those illustrated in FIG. 2. As illustrated in FIG. 2, the plotting system may include a computer 201. The computer 201 may be the same as the computer 101 or may be different. The computer 201 may include a user interface 203 and a software graphics application 205. The user interface 203 may include any type of user interface device, such as a display, touch screen, mouse, and/or keyboard. The software graphics application 205 may include any type of software graphic application. The application may be configured to enable a user to readily select one or more shapes to be printed, such as one or more squares, rectangles, circles, and/or ovals. The software graphics application 205 may be configured to allow the user to place a border around each shape. The software graphics application 205 may be configured to allow the user to select the color of each border, the thickness of each border, and the color of the fill within the border. The software graphics application 205 may be configured to allow the user to select the density of the border and/or the density of the fill within the border. This selection may be referred to in the software graphics application 205 as the “transparency” of the border and/or the fill. One such software graphics application which may be suitable for the software graphics application 205 is Microsoft Excel. The software graphics application 205 may enable a user to control the size of the shapes which are selected, the size of the paper on which the shapes are to be printed, and/or the layout of the shapes on the paper. The plotting system illustrated in FIG. 2 may include a plotter 207. The plotter 207 may be the same as the plotter 103 illustrated in FIG. 1 or it may be different. The plotter 207 may include a controller 209, a border cartridge 211, a radioactive isotope solution cartridge 213, and a paper supply 215. The paper supply 215 may be a single sheet of paper that is manually fed and/or a roll of paper that the plotter 207 is configured to cut under the control of a computer, such as the computer 201. The paper that may be used in the paper supply 215 may be of any size and/or type. For example, the paper may be coated bond paper, such as HP Product No. C6020B (a thirty-six inch wide roll of coated bond paper) or HP Product No. C6019B (a twenty-four inch wide roll of coated bond paper). The border cartridge 211 may be any type of cartridge which is configured to hold and deliver pigmented fluid, such as ink. The border cartridge 211 may include an integrated print head, or may be configured to deliver its contents to a separate print head. The pigmented fluid may be of any color, such as black, cyan, yellow, or magenta. The radioactive isotope solution cartridge 213 may be configured to hold radioactive isotopes in a pigmentless carrier solution and to controllably deliver that isotope solution to a print head. The print head may be integrated with the radioactive isotope solution cartridge 213 or may be separate from it. The controller 209 may be configured to cause the plotter 207 to perform one or more of the operations that are described herein for a plotter, such as to controllably feed paper from the paper supply 215 past the print heads, to controllably move the print heads to different locations on the paper, and/or to cause one or more of the print heads to print at controllable locations and/or at controllable densities on the paper. The controller 209 may be configured to perform these functions pursuant to commands from a computer, such as the computer 201. FIG. 3 illustrates a process for depositing a bordered, pigmentless radioactive carrier solution in a confined area on a piece of paper. The process illustrated in FIG. 3 may be implemented by the plotting system illustrated in FIG. 1, FIG. 2, and/or by any other type of plotting system. Similarly, the plotting system illustrated in FIG. 1 or FIG. 2 may be implemented in any other process. The process may include additional steps, may not include all of the steps illustrated in FIG. 3, and/or may perform the steps in a different sequence. A solution containing radioactive isotopes, such as Cobalt 57 (CO57), Iodine 125 (I-125), or Palladium 103 (Pd103) may be purchased or made. In one embodiment, the radioactive isotopes are Cobalt 57, Iodine 125, Palladium 103, Barium 133, Carbon 14, Gadolinium 153, Phosphorus 33, and/or Tellurium 99. As illustrated in the Dry Isotope Solution step 301, this isotope solution may be dried down to remove the solution from the isotopes. To facilitate the dry down process, heat may be applied. The isotope solution may be allowed to dry under this heat for several hours. After the isotope solution has dried, a pigmentless carrier solution may be mixed with the dried isotopes, as reflected by a Mix Isotopes with Carrier Solution step 303. During this step, an off-the-shelf, stock, pigmentless carrier solution may be mixed with the dried isotope(s). Alternatively, a custom-made, pigmentless carrier solution may be used, such as a mixture of 600 mg of cobalt chloride (CoCl), 10 ml ethylene glycol, 10 ml glycerin, and 80 ml of 0.1M hydrochloric acid (HCl), or it might be mixed in any other proportion. The pigmentless, radioactive carrier solution may have a viscosity which is suitable for being deposited on the substrate using a standard or modified inkjet cartridge, such as the radioactive isotope solution cartridge 213 illustrated in FIG. 2. If too thin, the mixed solution may run when printed. If too thick, the mixed solution may not expel smoothly from the radioactive isotope solution cartridge. The radioactive carrier solution may be pigmentless and thus unobservable to the naked eye after being printed. In other applications, a pigment may be added to the radioactive carrier solution, such as an ink. The pigmentless radioactive carrier solution may be loaded in a radioactive isotope solution cartridge, such as the radioactive isotope solution cartridge 213 illustrated in FIG. 2, as reflected by a Load Isotope Carrier Solution in Cartridge step 305. In some cases, the radioactive isotope solution cartridge may come preloaded with ink, such as in the case of a Hewlett-Packard No. 40 black ink cartridge. In these instances, the ink may be removed from the radioactive isotope solution cartridge and replaced with the pigmentless radioactive carrier solution. In other cases, the radioactive isotope solution cartridge 213 may be purchased empty, such as in the case of other compatible brands of empty cartridges. A border cartridge, such as the border cartridge 211, may be loaded in the plotter, as reflected by a Load Border Cartridge step 307. The border cartridge 211 may be purchased preloaded with ink or have ink added to it. An active area shape may be selected and configured, as reflected by a Select and Configure Active Area Shape step 309. During this step, the user may communicate through a user interface, such as the user interface 203, with a software graphics application, such as the software graphics application 205. The communication may cause the software graphics application to select a pre-defined shape, such as a square, rectangle, circle, or oval. The communication may also specify a fill for the shape, such as a uniform color, and the transparency of the fill. The communication may also specify a size for the shape. The communication may also specify the number of shapes and how they are to be placed and arranged on one or more sheets of paper. The communication may designate that a border is to be placed around the shape, as reflected by a Set Border step 311. The communication may specify a color for the border, its thickness, and its transparency. The communication may specify that the color of the border be different than the fill. More particularly, the communication may specify a color for the border which the software graphics application and the plotter may assign exclusively to the border cartridge within the plotter, such as to the border cartridge 211 in the plotter 207. Similarly, the user may select a color for the fill of a shape which the software graphics application and the plotter may assign exclusively to the radioactive isotope solution cartridge, such as to the radioactive isotope solution cartridge 213 in the plotter 207. In this way, the border will be printed only by border cartridge and the fill will be printed only by the radioactive isotope solution cartridge 213. FIGS. 4A-4F illustrate various sizes, shapes, and types of bordered, pigmentless radioactive areas. Each of these areas, as well as areas of different sizes, shapes and types, may be selected by the user through the use of the software graphics application 205. FIG. 4A illustrates a radioactive area that is square. The area includes a thin border 401 and a fill (e.g., a pigmentless radioactive fill or an active area) 403. FIG. 4B also illustrates a radioactive area that is square with a border 405 and a fill (e.g., a pigmentless radioactive fill or an active area) 407. The border 405 in FIG. 4B, however, may be thicker than the border 401 in FIG. 4A. FIG. 4C also illustrates a radioactive area which is square, with a border 409 and a fill (e.g., a pigmentless radioactive fill or an active area) 411. This square is similar to the squares illustrated in FIGS. 4A and 4B, except that the border 409 is even thicker. FIGS. 4A-4C thus illustrate variations in the thickness of the border that may be selected during the Set Border step 311. FIG. 4D illustrates a radioactive shape which is rectangular and which includes a border 413 and a fill 415. FIG. 4E also illustrates a radioactive shape which is rectangular with a border 417 and a fill (e.g., a pigmentless radioactive fill or an active area) 419. FIG. 4E is similar to FIG. 4D, except that the border 417 is spaced from the fill 419. FIG. 4F illustrates a radioactive shape that is circular which includes a border 421 and a fill (e.g., a pigmentless radioactive fill or an active area) 423. FIGS. 4D-4F thus illustrate that the shape of the radioactive area may be other than square and that the border may be spaced from the fill. Fills 403, 407, 411, 415, 419, and 423 are illustrated in FIGS. 4A-4F, respectively, with a cross-hatch pattern. It is to be understood that no such cross-hatch pattern may in fact appear when the shape is printed. To the contrary, the fill may not be in any way visible to the naked eye because it may be pigmentless. After the attributes of the shape have been selected and configured, and after the user has specified how the shape is to be printed on the paper, the user may direct the computer to print one or more instances of the selected and configured shape on paper by a plotter, as reflected by a Print step 313. As part of this step, the plotter may respond by printing in accordance with the selections and configurations that were made. This may include, for example, cutting the length of paper on a roll to the length set by the user. FIGS. 5A-5B illustrate alternate arrangements of bordered, pigmentless radioactive areas that may be printed on a continuous sheet of paper. These areas are illustrated as rectangular. FIG. 5A illustrates each rectangular shape 501 being printed with its longest dimension running across the width of the paper, while FIG. 5B illustrates each rectangular shape 503 being printed with its longest dimension running transverse to the width of a paper, but in a stacked configuration. Any other type of layout may be used in addition or instead. The layout may be set by the user when using the software graphics application 205, by the application itself so as to best utilize the surface area of the paper, and/or by the plotter. Although FIGS. 5A-5B illustrate only replicas of the same shape being printed during a single run, different shapes may in addition or instead be printed during such a single run. FIGS. 5A and 5B also illustrate shapes being printed on a roll of paper. Through appropriate commands from the computer and/or the plotter, the plotter may cause the roll of paper to be cut between each shape or between each set of stacked shapes, while the printing is ongoing. The plotter may in addition or instead print each shape and/or set of shapes on separate sheets of paper, fed automatically or manually. After the shapes are printed on the paper, each shape may be cut from the paper, as reflected by a Cut Active Sheet(s) Around Border step 315. During this step, non-active paper outside of the border of each shape may be removed. In some cases, a small frame of non-active paper around the border of each shape may be permitted to remain, such as a frame that is between one and two inches wide. In other applications, the shape may be cut at the outer edge of its border, within its border, at the inner edge of its border, or in any other way. The presence of a visible border around each pigmentless active area may serve a multitude of purposes. For example, the visible border may serve to signal that the radioactive isotope has been printed on the paper, thus providing a safety function. The visible border also provides a convenient means for identifying where cuts should be made to remove non-active paper on which no printing has taken place or at least portions thereof. Each active sheet may be laminated, as reflected by a Laminate Active Sheet(s) step 317. During this step, each side of an active sheet may be laminated, so as to prevent radioactive isotopes from separating from each sheet, potentially creating a hazard. FIG. 6 is a partial cross-section of a laminated sheet of paper containing a bordered, pigmentless radioactive area. As illustrated in FIG. 6, a sheet of paper 601 containing a bordered, pigmentless radioactive area is protected on one side by a protective sheet 603 and on the other side by a protective sheet 605. The protective sheets 603 and 605 may be made of any material, but are typically a transparent plastic film suitable for use with any commercially available, heat-applying laminating machine. The protective sheets may cover all of the active area on the paper 601. The protective sheets 603 and 605 may extend beyond the active area to the perimeter of the paper 601 or beyond. In some cases, the lamination process may result in the protective sheets 603 and 605 extending well beyond the perimeter of the paper 601. In this instance, excessive portions of the protective sheets 603 and 605 may be cut off. The protective sheets 603 and 605 may be affixed to the paper 601 by any means, such as by an adhesive The surfaces of the paper 601 may in addition or instead be sealed through application of a liquid sealant which may thereafter dry into a hard surface. The printed paper may be tested to verify the integrity of the radioactive area on the paper. The testing may seek to verify the shape of the active area, its homogeneity, and/or any other desired characteristic, as reflected by a Test Active Sheet(s) step 319. Each laminated, active sheet may be placed in a protective housing, as reflected by a Place Laminated Active Sheet in Protective Housing step 321. The finished product may then be distributed as flood source. FIG. 7 is a cross-section of a completed flood source. As illustrated in FIG. 7, a laminated, active sheet 701 may be placed within a central slot of a protective housing 703. A spacer 705 may be provided to ensure that the laminated, active sheet 701 fits snugly within the central slot of the protective housing and to ensure that its surface is parallel to the surface of the protective housing 703, thus maximizing the uniformity of its radiation. The protective housing 703 may be made of any material. For example, it may be made of acrylic or ABS. The spacer 705 may similarly be made of any type of material. For example, it may be made of foam. The components, steps, features, objects, benefits and advantages that have been discussed are merely illustrative. None of them, nor the discussions relating to them, are intended to limit the scope of protection in any way. Numerous other embodiments are also contemplated, including embodiments that have fewer, additional, and/or different components, steps, features, objects, benefits and advantages. The components and steps may also be arranged and ordered differently. For example, each of the printed shapes thus-far have been described as being uniformly filled with radioactive isotopes. In other applications, the filling may not be uniform, but may have a desired gradient or other pattern. For example, a pattern of stripes or rings may be printed. A hatch pattern may in addition or instead be printed. A plotter which is directed to make an active area completely uniform may fail to do so, particularly when it has just started to print. Instead of printing a uniform distribution of the isotope across the surface of a shape, for example, the distribution may have a discernible gradient. Printed sheets which fail to provide the desired degree of uniformity may be discarded. However, the radioactive isotopes may be expensive. Instead of discarding such non-uniform printed sheets, two such sheets may be placed back-to-back with their gradients in opposite directions. This may create a combined sheet which may then have the desired degree of uniformity. Thus far, each shape has been described as having a visible border completely around it. In other applications, only a partial border may be provided. For example, each of the rectangular shapes 503 in FIG. 5A may not have any visible border, but may instead be separated from one another by a visible, vertical demarcation line. The isotope carrier solution has also thus-far been described as being pigmentless. In some applications, a pigment such as ink may be included. Plotters have thus-far been described as being useful for transferring the active isotope to paper. In some applications, other devices may be used, such as “laser” type printers. Isotopes have thus-far been described as being printed on paper. In other applications, sheets of material other than paper may be used, such as films, such as Mylar®, or acetate. The radioactive isotopes and the borders around them have thus-far been described as being printed at the same time, albeit through different heads. In other applications, the border and the radioactive isotopes may be printed at different times e.g., during different traverses of the paper past the print heads. The border and the radioactive isotopes have thus-far been described as being printed through separate heads. In some applications, a single print head with appropriate multiplexing technology may instead be used to print both. Nothing that has been stated or illustrated is intended to cause any dedication to any component, step feature, object, benefit, advantage, or equivalent to the public, regardless of how it has been expressed. While the present invention has been described in connection with certain exemplary embodiments, it is to be understood that the invention is not limited to the disclosed embodiments, but, on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the appended claims, and equivalents thereof.
055816053	claims	1. An optical element comprising: a substrate having a plurality of concave surfaces or convex surfaces with a substantially same curvature; and multilayer films for reflecting X-rays, formed on the concave surfaces or convex surfaces of said substrate and composed of thin films; wherein when X-rays are incident into the multilayer films on said concave surfaces or convex surfaces, the X-rays are reflected with a predetermined diverging angle on the multilayer films and as a result a plurality of secondary X-ray sources having the diverging angle are formed on a same plane located a predetermined distance apart from said concave surfaces or convex surfaces. said first plane being a plane of incidence with respect to X-rays and passing through a vertex of said concave surfaces or convex surfaces, and said second plane being a plane passing through said vertex and being perpendicular to said first plane. an optical reflector having an X-ray reflecting surface forming a part of a parabola of revolution obtained by revolving an arbitrary parabola about a base axis passing through a vertex and a focus of the parabola and inclined at a predetermined angle relative to a normal line to said illuminated surface, said optical reflector reflecting X-rays by said X-ray reflecting surface to irradiate said illuminated surface; and an optical element for reflecting X-rays incident thereinto substantially in parallel with said base axis to irradiate said X-rays onto the X-ray reflecting surface of said optical reflector; wherein said optical reflector and said optical element are rotated in a united manner about a rotation axis passing through said optical element and being parallel to the normal line to said illuminated surface; wherein said optical element comprises: a substrate having a plurality of concave surfaces or convex surfaces with a substantially same curvature; and multilayer films for reflecting X-rays, formed on the concave surfaces or convex surfaces of said substrate and composed of thin films; wherein when X-rays are incident into the multilayer films on said concave surfaces or convex surfaces, the X-rays are reflected with a predetermined diverging angle on the multilayer films and as a result a plurality of secondary X-ray sources having the diverging angle are formed on a same plane located a predetermined distance apart from said concave surfaces or convex surfaces. said first plane being a plane of incidence with respect to X-rays and passing through a vertex of said concave surfaces or convex surfaces, and said second plane being a plane passing through said vertex and being perpendicular to said first plane. an optical reflector having an X-ray reflecting surface forming a part of a parabola of revolution obtained by revolving an arbitrary parabola about a base axis passing through a vertex and a focus of the parabola and inclined at a predetermined angle relative to a normal line to said illuminated surface, said optical reflector reflecting X-rays by said X-ray reflecting surface to irradiate said illuminated surface; an optical element for reflecting X-rays incident thereinto substantially in parallel with said base axis to irradiate said X-rays onto the X-ray reflecting surface of said optical reflector; an X-ray source for emitting X-rays toward said optical element; and rotation driving means for rotating said optical reflector and said optical element in a united manner about a rotation axis passing through said optical element and being parallel to the normal line to said illuminated surface; wherein said optical reflector and said optical element are rotated in a united manner by said rotation driving means to irradiate the X-rays emitted from said X-ray source onto said illuminated surface in an arc shape; wherein said optical element comprises: a substrate having a plurality of concave surfaces or convex surfaces with a substantially same curvature; and multilayer films for reflecting X-rays, formed on the concave surfaces or convex surfaces of said substrate and composed of thin films; wherein when X-rays are incident into the multilayer films on said concave surfaces or convex surfaces, the X-rays are reflected with a predetermined diverging angle on the multilayer films and as a result a plurality of secondary X-ray sources having the diverging angle are formed on a same plane located a predetermined distance apart from said concave surfaces or convex surfaces. said first plane being a plane of incidence with respect to X-rays and passing through a vertex of said concave surfaces or convex surfaces, and said second plane being a plane passing through said vertex and being perpendicular to said first plane. mask holding means for holding a photomask set on said illuminated surface; wafer holding means for holding a wafer onto which an image of pattern on said photomask is to be transferred; a projection optical system for receiving said image of pattern on said photomask and projecting the image of pattern onto said wafer; conveying means for successively conveying said mask holding means and wafer holding means; and controlling means for performing a control of conveyance of said conveying means and a control of rotation of said rotation driving means; wherein under control of said controlling means, while said optical reflector and said optical element are rotated in a united manner by said rotation driving means, said mask holding means and wafer holding means are successively conveyed by said conveying means to consecutively transfer the image of pattern on said photomask onto said wafer. said first plane being a plane of incidence with respect to X-rays and passing through a vertex of said concave surfaces or convex surfaces, and said second plane being a plane passing through said vertex and being perpendicular to said first plane. 2. An optical element according to claim 1, wherein said concave surfaces or convex surfaces are two-dimensionally arranged on said substrate. 3. An optical element according to claim 2, wherein said concave surfaces or convex surfaces each have a shape forming a part of spherical surface. 4. An optical element according to claim 2, wherein said concave surfaces or convex surfaces each have such a shape that a radius of curvature in a curve defined by crossing a first plane and said concave surfaces or convex surfaces is different from a radius of curvature in a curve defined by crossing a second plane and said concave surfaces or convex surfaces, 5. An optical element according to claim 4, wherein said concave surfaces or convex surfaces each have a shape of toroidal surface. 6. An optical element according to claim 5, wherein said multilayer films reflect X-rays of wavelength in the range of 5 nm to 20 nm. 7. An optical element according to claim 1, wherein said concave surfaces or convex surfaces each have a shape forming a part of a side surface of cylinder and one-dimensionally arranged on said substrate. 8. An optical system for illuminating an illuminated surface in an arc shape, comprising: 9. An optical system accoding to claim 8, wherein said concave surfaces or convex surfaces each have such a shape that a radius of curvature in a curve defined by crossing a first plane and said concave surfaces or convex surfaces is different from a radius of curvature in a curve defined by crossing a second plane and said concave surfaces or convex surfaces, 10. An optical system according to claim 9, wherein said concave surfaces or convex surfaces in said optical element each have a shape of toroidal surface. 11. An optical system according to claim 8, wherein said multilayer films in said optical system reflect X-rays of wavelength in the range of 5 nm to 20 nm. 12. An optical system according to claim 8, wherein the focus of said parabola is located on said illuminated surface. 13. An optical system according to claim 12, wherein a distance between the secondary X-ray sources formed by said optical element and the X-ray reflecting surface of said optical reflector is substantially equal to a distance between the X-ray reflecting surface of said optical reflector and said illuminated surface. 14. An optical apparatus for illuminating a predetermined area, comprising: 15. An optical apparatus accoding to claim 14, wherein said concave surfaces or convex surfaces in said optical element each have such a shape that a radius of curvature in a curve defined by crossing a first plane and said concave surfaces or convex surfaces is different from a radius of curvature in a curve defined by crossing a second plane and said concave surfaces or convex surfaces, 16. An optical apparatus according to claim 15, wherein said concave surfaces or convex surfaces in said optical element each have a shape of toroidal surface. 17. An optical apparatus according to claim 14, wherein said multilayer films in said optical system reflect X-rays of wavelength in the range of 5 nm to 20 nm. 18. An optical apparatus according to claim 14, wherein said illumination optical apparatus further comprises light deflecting means for deflecting the X-rays emitted from said X-ray source so as to make said X-rays incident into said optical element in a direction along said rotation axis. 19. An optical apparatus according to claim 18, wherein said light deflecting means is set on said rotation axis and wherein said X-ray source and said light deflecting means are stationary when said rotation axis is rotated by said rotation driving means. 20. An optical apparatus according to claim 14, wherein said focus of the parabola is located on said illuminated surface. 21. An optical apparatus according to claim 20, wherein a distance between the secondary X-ray sources formed by said optical element and the X-ray reflecting surface of said optical reflector is substantially equal to a distance between the X-ray reflecting surface of said optical reflector and said illuminated surface. 22. An optical apparatus according to claim 14, wherein said optical reflector and said optical element are pivoted in a predetermined range by said rotation driving means. 23. An optical apparatus according to claim 14, further comprising: 24. An optical apparatus accoding to claim 23, wherein said concave surfaces or convex surfaces in said optical element each have such a shape that a radius of curvature in a curve defined by crossing a first plane and said concave surfaces or convex surfaces is different from a radius of curvature in a curve defined by crossing a second plane and said concave surfaces or convex surfaces, 25. An optical apparatus according to claim 24, wherein said concave surfaces or convex surfaces in said optical element each have a shape of toroidal surface. 26. An optical apparatus according to claim 23, wherein said multilayer films in said optical system reflect X-rays of wavelength in the range of 5 nm to 20 nm. 27. An optical apparatus according to claim 23, wherein said illumination optical apparatus further comprises light deflecting means for deflecting the X-rays emitted from said X-ray source so as to make said X-rays incident into said optical element in a direction along said rotation axis. 28. An optical apparatus according to claim 27, wherein said light deflecting means is set on said rotation axis and wherein said X-ray source and said light deflecting means are stationary when said rotation axis is rotated by said rotation driving means. 29. An optical apparatus according to claim 23, wherein said focus of the parabola is located on said illuminated surface. 30. An optical apparatus according to claim 29, wherein a distance between the secondary X-ray sources formed by said optical element and the X-ray reflecting surface of said optical reflector is substantially equal to a distance between the X-ray reflecting surface of said optical reflector and said illuminated surface. 31. An optical apparatus according to claim 23, wherein said optical reflector and said optical element are pivoted in a predetermined range by said rotation driving means.
	summary
053032713	abstract	The device comprises a central body carrying a first inflatable flexible head and two jacks each carrying an inflatable flexible head at its end. The rods of the jacks are oriented in two directions located on either side of the central body to assure displacement of the central body as a result of the retraction and extension of the rods of the jacks in opposite directions. In the expanded state, the inflatable flexible head are maintained by wedging in the annular space between the bundle casing and the outer casing of the steam generator. In the retracted and deflated state, the flexible heads can be displaced in the annular space. The device also comprises an assembly for guidance by rolling on the lower end of the bundle casing of the steam generator.
	description	This disclosure relates to storing hazardous material in a subterranean formation and, more particularly, storing spent nuclear fuel in a subterranean formation. Hazardous waste is often placed in long-term, permanent, or semi-permanent storage so as to prevent health issues among a population living near the stored waste. Such hazardous waste storage is often challenging, for example, in terms of storage location identification and surety of containment. For instance, the safe storage of nuclear waste (e.g., spent nuclear fuel, whether from commercial power reactors, test reactors, or even military waste) is considered to be one of the outstanding challenges of energy technology. Safe storage of the long-lived radioactive waste is a major impediment to the adoption of nuclear power in the United States and around the world. Conventional waste storage methods have emphasized the use of tunnels, and is exemplified by the design of the Yucca Mountain storage facility. Other techniques include boreholes, including vertical boreholes, drilled into crystalline basement rock. Other conventional techniques include forming a tunnel with boreholes emanating from the walls of the tunnel in shallow formations to allow human access. In a general implementation, a hazardous material storage bank includes a wellbore extending into the Earth and including an entry at least proximate a terranean surface, the wellbore including a substantially vertical portion, a transition portion, and a substantially horizontal portion; a storage area coupled to the substantially horizontal portion of the well bore, the storage area within or below a shale formation, the storage area vertically isolated, by the shale formation, from a subterranean zone that includes mobile water; a storage container positioned in the storage area, the storage container sized to fit from the wellbore entry through the substantially vertical, the transition, and the substantially horizontal portions of the wellbore, and into the storage area, the storage container including an inner cavity sized enclose hazardous material; and a seal positioned in the wellbore, the seal isolating the storage portion of the wellbore from the entry of the wellbore. In an aspect combinable with the general implementation, the storage area is formed below the shale formation and is vertically isolated from the subterranean zone that includes mobile water by the shale formation. In another aspect combinable with any of the previous aspects, the storage area is formed within the shale formation, and is vertically isolated from the subterranean zone that includes mobile water by at least a portion of the shale formation. In another aspect combinable with any of the previous aspects, the shale formation includes a permeability of less than about 0.001 millidarcys. In another aspect combinable with any of the previous aspects, the shale formation includes a brittleness of less than about 10 MPa, where brittleness includes a ratio of compressive stress of the shale formation to tensile strength of the shale formation. In another aspect combinable with any of the previous aspects, the shale formation includes a thickness proximate the storage area of at least about 100 feet. In another aspect combinable with any of the previous aspects, the shale formation includes a thickness proximate the storage area that inhibits diffusion of the hazardous material that escapes the storage container through the shale formation for an amount of time that is based on a half-life of the hazardous material. In another aspect combinable with any of the previous aspects, the shale formation includes about 20 to 30% weight by volume of clay or organic matter. In another aspect combinable with any of the previous aspects, the hazardous material includes spent nuclear fuel. Another aspect combinable with any of the previous aspects further includes at least one casing assembly that extends from at or proximate the terranean surface, through the wellbore, and into the storage area. In another aspect combinable with any of the previous aspects, the storage container includes a connecting portion configured to couple to at least one of a downhole tool string or another storage container. In another general implementation, a method for storing hazardous material includes moving a storage container through an entry of a wellbore that extends into a terranean surface, the entry at least proximate the terranean surface, the storage container including an inner cavity sized enclose hazardous material; moving the storage container through the wellbore that includes a substantially vertical portion, a transition portion, and a substantially horizontal portion, the storage container sized to fit from the wellbore entry through the substantially vertical, the transition, and the substantially horizontal portions of the wellbore; moving the storage container into a storage area that is coupled to the substantially horizontal portion of the well bore, the storage area located within or below a shale formation and vertically isolated, by the shale formation, from a subterranean zone that includes mobile water; and forming a seal in the wellbore that isolates the storage portion of the wellbore from the entry of the wellbore. In an aspect combinable with the general implementation, the storage area is formed below the shale formation and is vertically isolated from the subterranean zone that includes mobile water by the shale formation. In another aspect combinable with any of the previous aspects, the storage area is formed within the shale formation. In another aspect combinable with any of the previous aspects, the shale formation is geologically formed below an impermeable formation that is formed between the shale formation and the subterranean zone that includes mobile water. In another aspect combinable with any of the previous aspects, the shale formation includes geological properties including two or more of: a permeability of less than about 0.001 millidarcys; a brittleness of less than about 10 MPa, where brittleness includes a ratio of compressive stress of the shale formation to tensile strength of the shale formation; a thickness proximate the storage area of at least about 100 feet; or about 20 to 30% weight by volume of organic material or clay. In another aspect combinable with any of the previous aspects, the hazardous material includes spent nuclear fuel. In another aspect combinable with any of the previous aspects, the wellbore further includes at least one casing that extends from at or proximate the terranean surface, through the wellbore, and into the storage area. Another aspect combinable with any of the previous aspects further includes prior to moving the storage container through the entry of the wellbore that extends into the terranean surface, forming the wellbore from the terranean surface to the shale formation. Another aspect combinable with any of the previous aspects further includes installing a casing in the wellbore that extends from at or proximate the terranean surface, through the wellbore, and into the storage area. Another aspect combinable with any of the previous aspects further includes cementing the casing to the wellbore. Another aspect combinable with any of the previous aspects further includes, subsequent to forming the wellbore, producing hydrocarbon fluid from the shale formation, through the wellbore, and to the terranean surface. Another aspect combinable with any of the previous aspects further includes removing the seal from the wellbore; and retrieving the storage container from the storage area to the terranean surface. Another aspect combinable with any of the previous aspects further includes monitoring at least one variable associated with the storage container from a sensor positioned proximate the storage area; and recording the monitored variable at the terranean surface. In another aspect combinable with any of the previous aspects, the monitored variable includes at least one of radiation level, temperature, pressure, presence of oxygen, presence of water vapor, presence of liquid water, acidity, or seismic activity. Another aspect combinable with any of the previous aspects further includes, based on the monitored variable exceeding a threshold value: removing the seal from the wellbore; and retrieving the storage container from the storage area to the terranean surface. In another general implementation, a spent nuclear fuel storage system includes a directional wellbore formed from a terranean surface, through a first subterranean layer, and into a second subterranean layer deeper than the first subterranean layer, the first subterranean layer including a rock formation that includes a source of mobile water, the second subterranean layer including a shale formation that fluidly isolates a portion of the directional wellbore formed within the shale formation from the first subterranean layer; a container configured to be moved through the directional wellbore into the portion of the directional wellbore formed within the shale formation, the container including a volume enclosed by a housing configured to store a plurality of spent nuclear fuel pellets; and a plug set in the directional wellbore between the portion of the directional wellbore formed within the shale formation and the terranean surface. In an aspect combinable with the general implementation, the directional wellbore is formed through a third subterranean layer between the first and second subterranean layers, the third subterranean layer including a substantially impermeable rock formation. In another aspect combinable with any of the previous aspects, the impermeable rock formation is more brittle than the shale formation. In another aspect combinable with any of the previous aspects, the impermeable rock formation is less permeable than the shale formation. Another aspect combinable with any of the previous aspects further includes a monitoring system, including a monitoring control system communicably coupled to one or more systems positioned proximate the container. Another aspect combinable with any of the previous aspects further includes a tubular liner constructed in the directional wellbore and sealed against a wall of the directional wellbore. The present disclosure also describes additional implementations of a hazardous material storage bank. For example, implementations of systems and method for storing a hazardous material include a wellbore formed from a terranean surface to a subterranean zone that includes shale, the wellbore including a substantially vertical portion, a radius portion, and a substantially non-vertical portion; a storage container positioned in the substantially non-vertical portion of the wellbore and including a volume sized to encapsulate a hazardous material that is isolated from a source of mobile water based upon proximity of the storage container in the shale; and a seal positioned in the wellbore between the storage container and an inlet of the wellbore at the terranean surface, the seal configured to fluidly isolate at least a portion of the substantially non-vertical portion from at least a portion of the substantially vertical portion. As another example, implementations of systems and method for storing a hazardous material include a wellbore formed from a terranean surface to a subterranean zone, the wellbore including a substantially vertical portion, a radius portion, and a substantially non-vertical portion, the subterranean zone including a geologic formation defined by two or more of the following characteristics: a permeability of less than about 0.001 millidarcys, a brittleness of less than about 10 MPa, where brittleness includes a ratio of compressive stress of the shale formation to tensile strength of the shale formation, a thickness of typically about 100 feet, and about 20 to 30% weight by volume of organic material or clay; a storage container positioned in the substantially non-vertical portion of the wellbore and including a volume sized to encapsulate a hazardous material; and a seal positioned in the wellbore between the storage container and an inlet of the wellbore at the terranean surface. As another example, implementations of systems and method for banking a hazardous material, such as a spent nuclear fuel material, include forming a wellbore from a terranean surface to a subterranean zone that includes shale, the wellbore including a substantially vertical portion, a radius portion, and a substantially non-vertical portion; and pumping a hardenable slurry into the substantially non-vertical portion of the wellbore, the hardenable slurry including a mixture of a hardenable material (e.g., cement, resin, polymer, concrete, grout) and a spent nuclear fuel material. Implementations of a hazardous material storage bank according to the present disclosure may include one or more of the following features. For example, a hazardous material storage bank according to the present disclosure may allow for multiple levels of containment of hazardous material within a storage bank located thousands of feet underground, decoupled from any nearby mobile water. A hazardous material storage bank according to the present disclosure may also use proven techniques (e.g., drilling) to create or form a storage area for the hazardous material, in a subterranean zone proven to have fluidly sealed hydrocarbons therein for millions of years. As another example, a hazardous material storage bank according to the present disclosure may provide long-term (e.g., thousands of years) storage for hazardous material (e.g., radioactive waste) in a shale formation that has geologic properties suitable for such storage, including low permeability, thickness, and ductility, among others. In addition, a greater volume of hazardous material may be stored at low cost—relative to conventional storage techniques—due in part to directional drilling techniques that facilitate long horizontal boreholes, often exceeding a mile in length. In addition, rock formations that have geologic properties suitable for such storage may be found in close proximity to sites at which hazardous material may be found or generated, thereby reducing dangers associated with transporting such hazardous material. Implementations of a hazardous material storage bank according to the present disclosure may also include one or more of the following features. Large storage volumes, in turn, allow for the storage of hazardous materials to be emplaced without a need for complex prior treatment, such as concentration or transfer to different forms or containers. As a further example, in the case of nuclear waste material from a reactor for instance, the waste can be kept in its original pellets, unmodified, or in its original fuel rods, or in its original fuel assemblies, which contain dozens of fuel rods. In another aspect, the hazardous material may be kept in an original holder but a cement or other material is injected into the holder to fill the gaps between the hazardous materials and the structure. For example, if the hazardous material is stored in fuel rods which are, in turn, stored in fuel assemblies, then the spaces between the rods (typically filled with water when inside a nuclear reactor) could be filled with cement or other material to provide yet an additional layer of isolation from the outside world. As yet a further example, secure and low cost storage of hazardous material is facilitated while still permitting retrieval of such material if circumstances deem it advantageous to recover the stored materials. The details of one or more implementations of the subject matter described in this disclosure are set forth in the accompanying drawings and the description below. Other features, aspects, and advantages of the subject matter will become apparent from the description, the drawings, and the claims. The present disclosure describes a hazardous material storage bank system, which includes one or more wellbores formed into a subterranean zone to provide long-term (e.g., tens, hundreds, or even thousands of years) storage of hazardous material (e.g., biological, chemical, nuclear, or otherwise) in one or more underground storage volumes storage containers. The subterranean zone includes multiple subterranean layers having different geological formations and properties. The storage containers may be deposited in a particular subterranean layer based on one or more geologic properties of that layer, such as low permeability, sufficient thickness, low brittleness, and other properties. In some aspects, the particular subterranean layer comprises a shale formation, which forms an isolative seal between the storage containers and another subterranean layer that comprises mobile water. FIGS. 1A-1C are schematic illustrations of example implementations of a hazardous material storage bank system, e.g., a subterranean location for the long-term (e.g., tens, hundreds, or thousands of years or more) but retrievable safe and secure storage of hazardous material, during a deposit or retrieval operation according to the present disclosure. For example, turning to FIG. 1A, this figure illustrates an example hazardous material storage bank system 100 during a deposit (or retrieval, as described below) process, e.g., during deployment of one or more containers of hazardous material in a subterranean formation. As illustrated, the hazardous material storage bank system 100 includes a wellbore 104 formed (e.g., drilled or otherwise) from a terranean surface 102 and through multiple subterranean layers 112, 114, 116, and 118. Although the terranean surface 102 is illustrated as a land surface, terranean surface 102 may be a sub-sea or other underwater surface, such as a lake or an ocean floor or other surface under a body of water. Thus, the present disclosure contemplates that the wellbore 104 may be formed under a body of water from a drilling location on or proximate the body of water. The illustrated wellbore 104 is a directional wellbore in this example of hazardous material storage bank system 100. For instance, the wellbore 104 includes a substantially vertical portion 106 coupled to a radiussed or curved portion 108, which in turn is coupled to a substantially horizontal portion 110. As used in the present disclosure, “substantially” in the context of a wellbore orientation, refers to wellbores that may not be exactly vertical (e.g., exactly perpendicular to the terranean surface 102) or exactly horizontal (e.g., exactly parallel to the terranean surface 102). In other words, those of ordinary skill in the drill arts would recognize that vertical wellbores often undulate offset from a true vertical direction, that they might be drilled at an angle that deviates from true vertical, and horizontal wellbores often undulate offset from a true horizontal direction. Further, the substantially horizontal portion 110, in some aspects, may be a slant wellbore or other directional wellbore that is oriented between exactly vertical and exactly horizontal. Further, the substantially horizontal portion 110, in some aspects, may be a slant wellbore or other directional well bore that is oriented to follow the slant of the formation. As illustrated in this example, the three portions of the wellbore 104—the vertical portion 106, the radiussed portion 108, and the horizontal portion 110—form a continuous wellbore 104 that extends into the Earth. The illustrated wellbore 104 has a surface casing 120 positioned and set around the wellbore 104 from the terranean surface 102 into a particular depth in the Earth. For example, the surface casing 120 may be a relatively large-diameter tubular member (or string of members) set (e.g., cemented) around the wellbore 104 in a shallow formation. As used herein, “tubular” may refer to a member that has a circular cross-section, elliptical cross-section, or other shaped cross-section. For example, in this implementation of the hazardous material storage bank system 100, the surface casing 120 extends from the terranean surface through a surface layer 112. The surface layer 112, in this example, is a geologic layer comprised of one or more layered rock formations. In some aspects, the surface layer 112 in this example may or may not include freshwater aquifers, salt water or brine sources, or other sources of mobile water (e.g., water that moves through a geologic formation). In some aspects, the surface casing 112 may isolate the wellbore 104 from such mobile water, and may also provide a hanging location for other casing strings to be installed in the wellbore 104: Further, although not shown, a conductor casing may be set above the surface casing 112 (e.g., between the surface casing 112 and the surface 102 and within the surface layer 112) to prevent drilling fluids from escaping into the surface layer 112. As illustrated, a production casing 122 is positioned and set within the wellbore 104 downhole of the surface casing 120. Although termed a “production” casing, in this example, the casing 122 may or may not have been subject to hydrocarbon production operations. Thus, the casing 122 refers to and includes any form of tubular member that is set (e.g., cemented) in the wellbore 104 downhole of the surface casing 120. In some examples of the hazardous material storage bank system 100, the production casing 122 may begin at an end of the radiussed portion 108 and extend throughout the substantially horizontal portion 110. The casing 122 could also extend into the radiussed portion 108 and into the vertical portion 106. As shown, cement 130 is positioned (e.g., pumped) around the casings 120 and 122 in an annulus between the casings 120 and 122 and the wellbore 104. The cement 130, for example, may secure the casings 120 and 122 (and any other casings or liners of the wellbore 104) through the subterranean layers under the terranean surface 102. In some aspects, the cement 130 may be installed along the entire length of the casings (e.g., casings 120 and 122 and any other casings), or the cement 130 could be used along certain portions of the casings if adequate for a particular wellbore 102. The cement 130 can also provide an additional layer of confinement for the hazardous material in containers 126. The wellbore 104 and associated casings 120 and 122 may be formed with various example dimensions and at various example depths (e.g., true vertical depth, or TVD). For instance, a conductor casing (not shown) may extend down to about 120 feet TVD, with a diameter of between about 28 in. and 60 in. The surface casing 120 may extend down to about 2500 feet TVD, with a diameter of between about 22 in. and 48 in. An intermediate casing (not shown) between the surface casing 120 and production casing 122 may extend down to about 8000 feet TVD, with a diameter of between about 16 in. and 36 in. The production casing 122 may extend substantially horizontally (e.g., to case the substantially horizontal portion 110) with a diameter of between about 11 in. and 22 in. The foregoing dimensions are merely provided as examples and other dimensions (e.g., diameters, TVDs, lengths) are contemplated by the present disclosure. For example, diameters and TVDs may depend on the particular geological composition of one or more of the multiple subterranean layers (112-118), particular drilling techniques, as well as a size, shape, or design of a hazardous material container 126 that contains hazardous material to be deposited in the hazardous material storage bank system 100. In some alternative examples, the production casing 122 (or other casing in the wellbore 104) could be circular in cross-section, elliptical in cross-section, or some other shape. As illustrated, the wellbore 104 extends through subterranean layers 112, 114, and 116, and lands in subterranean layer 118. As discussed above, the surface layer 112 may or may not include mobile water. Subterranean layer 114, which is below the surface layer 112, in this example, is a mobile water layer 114. For instance, mobile water layer 114 may include one or more sources of mobile water, such as freshwater aquifers, salt water or brine, or other source of mobile water. In this example of hazardous material storage bank system 100, mobile water may be water that moves through a subterranean layer based on a pressure differential across all or a part of the subterranean layer. For example, the mobile water layer 114 may be a permeable geologic formation in which water freely moves (e.g., due to pressure differences or otherwise) within the layer 114. In some aspects, the mobile water layer 114 may be a primary source of human-consumable water in a particular geographic area. Examples of rock formations of which the mobile water layer 114 may be composed include porous sandstones and limestones, among other formations. Below the mobile water layer 114, in this example implementation of hazardous material storage bank system 100, is an impermeable layer 116. The impermeable layer 116, in this example, may not allow mobile water to pass through. Thus, relative to the mobile water layer 114, the impermeable layer 116 may have low permeability, e.g., on the order of nanodarcy permeability. Additionally, in this example, the impermeable layer 116 may be a relatively non-ductile (i.e., brittle) geologic formation. One measure of non-ductility is brittleness, which is the ratio of compressive stress to tensile strength. In some examples, the brittleness of the impermeable layer 116 may be between about 20 MPa and 40 MPa. As shown in this example, the impermeable layer 116 is shallower (e.g., closer to the terranean surface 102) than the storage layer 119. In this example rock formations of which the impermeable layer 116 may be composed include, for example, certain kinds of sandstone, mudstone, clay, and slate that exhibit permeability and brittleness properties as described above. In alternative examples, the impermeable layer 116 may be deeper (e.g., further from the terranean surface 102) than the storage layer 119. In such alternative examples, the impermeable layer 116 may be composed of an igneous rock, such as granite. Below the impermeable layer 116 is a storage layer 118. The storage layer 118, in this example, may be chosen as the landing for the substantially horizontal portion 110, which stores the hazardous material, for several reasons. Relative to the impermeable layer 116 or other layers, the storage layer 118 may be thick, e.g., between about 100 and 200 feet of total vertical thickness. Thickness of the storage layer 118 may allow for easier landing and directional drilling, thereby allowing the substantially horizontal portion 110 to be readily emplaced within the storage layer 118 during constructions (e.g., drilling). If formed through an approximate horizontal center of the storage layer 118, the substantially horizontal portion 110 may be surrounded by about 50 to 100 feet of the geologic formation that comprises the storage layer 118. Further, the storage layer 118 may also have no mobile water, e.g., due to a very low permeability of the layer 118 (e.g., on the order of milli- or nanodarcys). In addition, the storage layer 118 may have sufficient ductility, such that a brittleness of the rock formation that comprises the layer 118 is between about 3 MPa and 10 MPa. Examples of rock formations of which the storage layer 118 may be composed include: shale and anhydrite. Further, in some aspects, hazardous material may be stored below the storage layer, even in a permeable formation such as sandstone or limestone, if the storage layer is of sufficient geologic properties to isolate the permeable layer from the mobile water layer 114. In some examples implementations of the hazardous material storage bank system 100, the storage layer 118 is composed of shale. Shale, in some examples, may have properties that fit within those described above for the storage layer 118. For example, shale formations may be suitable for a long-term confinement of hazardous material (e.g., in the hazardous material containers 126), and for their isolation from mobile water layer 114 (e.g., aquifers) and the terranean surface 102. Shale formations may be found relatively deep in the Earth, typically 3000 feet or greater, and placed in isolation below any fresh water aquifers. Shale formations, for instance, may include geologic properties that enhance the long-term (e.g., thousands of years) isolation of material. Such properties, for instance, have been illustrated through the long term storage (e.g., tens of millions of years) of hydrocarbon fluids (e.g., gas, liquid, mixed phase fluid) without escape of such fluids into surrounding layers (e.g., mobile water layer 114). Indeed, shale has been shown to hold natural gas for millions of years or more, giving it a proven capability for long-term storage of hazardous material. Example shale formations (e.g., Marcellus, Eagle Ford, Barnett, and otherwise) has stratification that contains many redundant sealing layers that have been effective in preventing movement of water, oil, and gas for millions of years, lacks mobile water, and can be expected (e.g., based on geological considerations) to seal hazardous material (e.g., fluids or solids) for thousands of years after deposit. Shale formations may also be at a suitable depth, e.g., between 3000 and 12,000 feet TVD. Such depths are typically below ground water aquifer (e.g., surface layer 112 and/or mobile water layer 114). Further, the presence of soluble elements in shale, including salt, and the absence of these same elements in aquifer layers, demonstrates a fluid isolation between shale and the aquifer layers. Another particular quality of shale that may advantageously lend itself to hazardous material storage is its clay content, which, in some aspects, provides a measure of ductility greater than that found in other, impermeable rock formations (e.g., impermeable layer 116). For example, shale may be stratified, made up of thinly alternating layers of clays (e.g., between about 20-30% clay by volume) and other minerals. Such a composition may make shale less brittle and, thus less susceptible to fracturing (e.g., naturally or otherwise) as compared to rock formations in the impermeable layer (e.g., granite or otherwise). For example, rock formations in the impermeable layer 116 may have suitable permeability for the long term storage of hazardous material, but are too brittle and commonly are fractured. Thus, such formations may not have sufficient sealing qualities (as evidenced through their geologic properties) for the long term storage of hazardous material. The present disclosure contemplates that there may be many other layers between or among the illustrated subterranean layers 112, 114, 116, and 118. For example, there may be repeating patterns (e.g., vertically), of one or more of the mobile water layer 114, impermeable layer 116, and storage layer 118. Further, in some instances, the storage layer 118 may be directly adjacent (e.g., vertically) the mobile water layer 114, i.e., without an intervening impermeable layer 116. FIG. 1A illustrates an example of a deposit operation of hazardous material in the substantially horizontal portion 110 of the wellbore 104. For example, as shown, a work string 124 (e.g., tubing, coiled tubing, wireline, or otherwise) may be extended into the cased wellbore 104 to place one or more (three shown but there may be more or less) hazardous material containers 126 into long term, but in some aspects, retrievable, storage in the portion 110. For example, in the implementation shown in FIG. 1A, the work string 124 may include a downhole tool 128 that couples to the container 126, and with each trip into the wellbore 104, the downhole tool 128 may deposit a particular hazardous material container 126 in the substantially horizontal portion 110. The downhole tool 128 may couple to the container 126 by, in some aspects, a threaded connection. In alternative aspects, the downhole tool 128 may couple to the container 126 with an interlocking latch, such that rotation of the downhole tool 128 may latch to (or unlatch from) the container 126. In alternative aspects, the downhole tool 124 may include one or more magnets (e.g., rare Earth magnets, electromagnets, a combination thereof, or otherwise) which attractingly couple to the container 126. In some examples, the container 126 may also include one or more magnets (e.g., rare Earth magnets, electromagnets, a combination thereof, or otherwise) of an opposite polarity as the magnets on the downhole tool 124. In some examples, the container 126 may be made from or include a ferrous or other material attractable to the magnets of the downhole tool 124. As another example, each container 126 may be positioned within the wellbore 104 by a wellbore tractor (e.g., on a wireline or otherwise), which may push or pull the container into the substantially horizontal portion 110 through motorized (e.g., electric) motion. As yet another example, each container 126 may include or be mounted to rollers (e.g., wheels), so that the downhole tool 124 may push the container 126 into the cased wellbore 104. In some example implementations, the container 126, one or more of the wellbore casings 120 and 122, or both, may be coated with a friction-reducing coating prior to the deposit operation. For example, by applying a coating (e.g., petroleum-based product, resin, ceramic, or otherwise) to the container 126 and/or wellbore casings, the container 126 may be more easily moved through the cased wellbore 104 into the substantially horizontal portion 100. In some aspects, only a portion of the wellbore casings may be coated. For example, in some aspects, the substantially vertical portion 106 may not be coated, but the radiussed portion 108 or the substantially horizontal portion 110, or both, may be coated to facilitate easier deposit and retrieval of the container 126. FIG. 1A also illustrates an example of a retrieval operation of hazardous material in the substantially horizontal portion 110 of the wellbore 104. A retrieval operation may be the opposite of a deposit operation, such that the downhole tool 124 (e.g., a fishing tool) may be run into the wellbore 104, coupled to the last-deposited container 126 (e.g., threadingly, latched, by magnet, or otherwise), and pull the container 126 to the terranean surface 102. Multiple retrieval trips may be made by the downhole tool 124 in order to retrieve multiple containers from the substantially horizontal portion 110 of the wellbore 104. Each container 126 may enclose hazardous material. Such hazardous material, in some examples, may be biological or chemical waste or other biological or chemical hazardous material. In some examples, the hazardous material may include nuclear material, such as spent nuclear fuel recovered from a nuclear reactor (e.g., commercial power or test reactor) or military nuclear material. For example, a gigawatt nuclear plant may produce 30 tons of spent nuclear fuel per year. The density of that fuel is typically close to 10 (10 gm/cm3=10 kg/liter), so that the volume for a year of nuclear waste is about 3 m3. Spent nuclear fuel, in the form of nuclear fuel pellets, may be taken from the reactor and not modified. Nuclear fuel pellets are solid, and emit very little gas other than short-lived tritium (13 year half-life). In some aspects, the storage layer 118 should be able to contain any radioactive output (e.g., gases) within the layer 118, even if such output escapes the containers 126. For example, the storage layer 118 may be selected based on diffusion times of radioactive output through the layer 118. For example, a minimum diffusion time of radioactive output escaping the storage layer 118 may be set at, for example, fifty times a half-life for any particular component of the nuclear fuel pellets. Fifty half-lives as a minimum diffusion time would reduce an amount of radioactive output by a factor of 1×10−15. As another example, setting a minimum diffusion time to thirty half-lives would reduce an amount of radioactive output by a factor of one billion. For example, plutonium-239 is often considered a dangerous waste product in spent nuclear fuel because of its long half-life of 24,100 years. For this isotope, 50 half-lives would be 1.2 million years. Plutonium-239 has low solubility in water, is not volatile, and as a solid is not capable of diffusion through a matrix of the rock formation that comprises the illustrated storage layer 118 (e.g., shale or other formation). The storage layer 118, for example comprised of shale, may offer the capability to have such isolation times (e.g., millions of years) as shown by the geological history of containing gaseous hydrocarbons (e.g., methane and otherwise) for several million years. In contrast, in conventional nuclear material storage methods, there was a danger that some plutonium might dissolve in a layer that comprised mobile ground water upon confinement escape. Turning to FIG. 1B, an alternative deposit operation is illustrated. In this example deposit operation, a fluid 132 (e.g., liquid or gas) may be circulated through the wellbore 104 to fluidly push the containers 126 into the substantially horizontal wellbore portion 110. In some example, each container 126 may be fluidly pushed separately. In alternative aspects, two or more containers 126 may be fluidly pushed, simultaneously, through the wellbore 104 for deposit into the substantially horizontal portion 110. The fluid 132 can be, in some cases, water. Other examples include a drilling mud or drilling foam. In some examples, a gas may be used to push the containers 126 into the wellbore, such as air, argon, or nitrogen. In some aspects, the choice of fluid 132 may depend at least in part on a viscosity of the fluid 132. For example, a fluid 132 may be chosen with enough viscosity to impede the drop of the container 126 into the substantially vertical portion 106. This resistance or impedance may provide a safety factor against a sudden drop of the container 126. The fluid 132 may also provide lubrication to reduce a sliding friction between the container 126 and the casings 120 and 122. The container 126 can be conveyed within a casing filled with a liquid of controlled viscosity, density, and lubricant qualities. The fluid-filled annulus between the inner diameter of the casings 120 and 122 and the outer diameter of the conveyed container 126 represents an opening designed to dampen any high rate of container motion, providing automatic passive protection in an unlikely decoupling of the conveyed container 126. In some aspects, other techniques may be employed to facilitate deposit of the container 126 into the substantially horizontal portion 110. For example, one or more of the installed casings (e.g., casings 120 and 122) may have rails to guide the storage container 126 into the wellbore 102 while reducing friction between the casings and the container 126. The storage container 126 and the casings (or the rails) may be made of materials that slide easily against one another. The casings may have a surface that is easily lubricated, or one that is self-lubricating when subjected to the weight of the storage container 126. The fluid 132 may also be used for retrieval of the container 126. For example, in an example retrieval operation, a volume within the casings 120 and 122 may be filled with a compressed gas (e.g., air, nitrogen, argon, or otherwise). As the pressure increases at an end of the substantially horizontal portion 110, the containers 126 may be pushed toward the radiussed portion 108, and subsequently through the substantially vertical portion 106 to the terranean surface. Turning to FIG. 1C, another alternative deposit operation is illustrated. In this example deposit operation, the fluid 132 (e.g., liquid or gas) may be circulated through a tubular fluid control casing 134 to fluidly push the containers 126 into the substantially horizontal wellbore portion 110. The fluid 132 may circulate through an end of the substantially horizontal portion 110 in the fluid control casing 134 and recirculate back to the terranean surface 102 in an annulus between the fluid control casing 134 and the casings 122 and 120. In some examples, each container 126 may be fluidly pushed separately. The annulus between the fluid control casing 134 and the casings 120 and 122 may be filled with a fluid or compressed gas to reverse the flow of fluid 132, e.g., in order to push the containers 126 back towards the terranean surface 102. In alternative aspects, two or more containers 126 may be fluidly pushed, simultaneously, through the wellbore 104 for deposit into the substantially horizontal portion 110. The fluid control casing 134 could be similar or identical to the production casing 122. For that case, a separate tubular member could be enclosed in the wellbore 102 or within the production casing 122 to provide a return path for the fluid 132. In some aspects, the wellbore 104 may be formed for the primary purpose of long-term storage of hazardous materials. In alternative aspects, the wellbore 104 may have been previously formed for the primary purpose of hydrocarbon production (e.g., oil, gas). For example, storage layer 118 may be a hydrocarbon bearing formation from which hydrocarbons were produced into the wellbore 104 and to the terranean surface 102. In some aspects, the storage layer 118 may have been hydraulically fractured prior to hydrocarbon production. Further in some aspects, the production casing 122 may have been perforated prior to hydraulic fracturing. In such aspects, the production casing 122 may be patched (e.g., cemented) to repair any holes made from the perforating process prior to a deposit operation of hazardous material. In addition, any cracks or openings in the cement between the casing and the drill hole can also be filled at that time. For example, in the case of spent nuclear fuel as a hazardous material, the wellbore may be formed at a particular location, e.g., near a nuclear power plant, as a new wellbore provided that the location also includes an appropriate storage layer 118, such as a shale formation. Alternatively, an existing well that has already produced shale gas, or one that was abandoned as “dry,” (e.g., with sufficiently low organics that the gas in place is too low for commercial development), may be selected as the wellbore 104. In some aspects, prior hydraulic fracturing of the storage layer 118 through the wellbore 104 may make little difference in the hazardous material storage capability of the wellbore 104. But such a prior activity may also confirm the ability of the storage layer 118 to store gases and other fluids for millions of years. If, therefore, the hazardous material or output of the hazardous material (e.g., radioactive gasses or otherwise) were to escape from the container 126 and enter the fractured formation of the storage layer 118, such fractures may allow that material to spread relatively rapidly over a distance comparable in size to that of the fractures. In some aspects, the wellbore 102 may have been drilled for a production of hydrocarbons, but production of such hydrocarbons had failed, e.g., because the storage layer 118 comprised a rock formation (e.g., shale or otherwise) that was too ductile and difficult to fracture for production, but was advantageously ductile for the long-term storage of hazardous material. FIGS. 2A-2E are schematic illustrations of example implementations of a hazardous material storage bank system during storage and monitoring operations according to the present disclosure. For example, FIG. 2A illustrates the hazardous material storage bank system 100 in a long term storage operation. One or more hazardous material containers 126 are positioned in the substantially horizontal portion 110 of the wellbore 104. A seal 134 is placed in the wellbore 104 between the location of the containers 126 in the substantially horizontal portion 110 and an opening of the substantially vertical portion 106 at the terranean surface 102 (e.g., a well head). In this example, the seal 134 is placed at an uphole end of the substantially vertical portion 108. Alternatively, the seal 134 may be positioned at another location within the substantially vertical portion 106, in the radiussed portion 108, or even within the substantially horizontal portion 110 uphole of the containers 126. In some aspects, the seal 134 may be placed at least deeper than any source of mobile water, such as the mobile water layer 114, within the wellbore 104. In some aspects, the seal 134 may be formed substantially along an entire length of the substantially vertical portion 106. As illustrated, the seal 134 fluidly isolates the volume of the substantially horizontal portion 110 that stores the containers 126 from the opening of the substantially vertical portion 106 at the terranean surface 102. Thus, any hazardous material (e.g., radioactive material) that does escape the containers 126 may be sealed (e.g., such that liquid, gas, or solid hazardous material) does not escape the wellbore 104. The seal 134, in some aspects, may be a cement plug or other plug, that is positioned or formed in the wellbore 104. As another example, the seal 134 may be formed from one or more inflatable or otherwise expandable packers positioned in the wellbore 104. Prior to a retrieval operation (e.g., as discussed with reference to FIGS. 1A-1B), the seal 134 may be removed. For example, in the case of a cement or other permanently set seal 134, the seal 134 may be drilled through or otherwise milled away. In the case of semi-permanent or removable seals, such as packers, the seal 134 may be removed from the wellbore 104 through a conventional process as is known. FIG. 2B illustrates an example monitoring operation during long term storage of the containers 126. For example, in some aspects, it may be advantageous or required to monitor one or more variables during long term storage of the hazardous material in the containers 126. In this example of FIG. 2B, the monitoring system includes one or more sensors 138 placed in the wellbore 104 (e.g., within the substantially horizontal portion 110) and communicably coupled to a monitoring control system 146 through a cable 136 (e.g., electrical, optical, hydraulic, or otherwise). Although illustrated as within wellbore 102 (e.g., inside of the casings), the sensors 138 may be placed outside of the casings, or even built into the casings before the casings are installed in the wellbore 102. Sensors 138 could also be placed outside the casing (e.g., casings 120 and/or 122), or outside the fluid control casing 134. As shown, the sensors 138 may monitor one or more variables, such as, for example, radiation levels, temperature, pressure, presence of oxygen, a presence of water vapor, a presence of liquid water, acidity, seismic activity, or a combination thereof. Data values related to such variables may be transmitted along the cable 136 to the monitoring control system 146. The monitoring control system 146, in turn, may record the data, determine trends in the data (e.g., rise of temperature, rise of radioactive levels), send data to other monitoring locations, such as national security or environmental center locations, and may further automatically recommend actions (e.g., retrieval of the containers 126) based on such data or trends. For example, a rise in temperature or radioactive level in the wellbore 104 above a particular threshold level may trigger a retrieval recommendation, e.g., to ensure that the containers 126 are not leaking radioactive material. In some aspects, there may be a one-to-one ratio of sensors 138 to containers 126. In alternative aspects, there may be multiple sensors 138 per container 126, or there may be fewer. FIG. 2C shows another example monitoring operation during long term storage of the containers 126. In this example, sensors 138 are positioned within a secondary horizontal wellbore 140 that is formed separately from the substantially vertical portion 106. The secondary horizontal wellbore 140 may be an uncased wellbore, through which the cable 136 may extend between the monitoring control system 146 and the sensors 138. In this example, the secondary horizontal wellbore 140 is formed above the substantially horizontal portion 110 but within the storage layer 118. Thus, the sensors 138 may record data (e.g., radiation levels, temperature, acidity, seismic activity) of the storage layer 118. In alternative aspects, the secondary horizontal wellbore 140 may be formed below the storage layer 118, above the storage layer in the impermeable layer 116, or in other layers. Further, although FIG. 2C shows the secondary horizontal wellbore 140 formed from the same substantially vertical portion 106 as the substantially horizontal portion 110, the secondary horizontal wellbore 140 may be formed from a separate vertical wellbore and radiussed wellbore. FIG. 2D shows another example monitoring operation during long term storage of the containers 126. In this example, sensors 138 are positioned within a secondary vertical wellbore 142 that is formed separately from the wellbore 104. The secondary vertical wellbore 142 may be a cased or an uncased wellbore, through which the cable 136 may extend between the monitoring control system 146 and the sensors 138. In this example, the secondary vertical wellbore 142 bottoms out above the substantially horizontal portion 110 but within the storage layer 118. Thus, the sensors 138 may record data (e.g., radiation levels, temperature, acidity, seismic activity) of the storage layer 118. In alternative aspects, the secondary vertical wellbore 140 may bottom out below the storage layer 118, above the storage layer in the impermeable layer 116, or in other layers. Further, although shown placed in the secondary vertical wellbore 142 at a level adjacent the storage layer 118, sensors 138 may be placed anywhere within the secondary vertical wellbore 142. Alternatively, the secondary vertical wellbore 142 may, in some aspects, be constructed prior to wellbore 102, thereby permitting monitoring by installed sensors 138 during construction of the wellbore 102. Also, the monitoring borehole 142 could be sealed to prevent the possibility that material that leaks into borehole 142 would have a path to the terranean surface 102. FIG. 2E shows another example monitoring operation during long term storage of the containers 126. In this example, sensors 138 are positioned within a secondary directional wellbore 144 that is formed separately from the wellbore 104. The secondary directional wellbore 144 may be an uncased wellbore, through which the cable 136 may extend between the monitoring control system 146 and the sensors 138. In this example, the secondary directional wellbore 144 lands adjacent the substantially horizontal portion 110 and within the storage layer 118. Thus, the sensors 138 may record data (e.g., radiation levels, temperature, acidity, seismic activity) of the storage layer 118. In alternative aspects, the secondary directional wellbore 144 may land below the storage layer 118, above the storage layer in the impermeable layer 116, or in other layers. Further, although shown placed in the secondary directional wellbore 144 at a level adjacent the storage layer 118, sensors 138 may be placed anywhere within the secondary directional wellbore 144. In some aspects, the secondary directional wellbore 144 may be used for retrieval of the containers 126, for example, in case the wellbore 104 is inaccessible. FIG. 3A is a schematic illustration of another example implementation of a hazardous material storage bank system according to the present disclosure. FIG. 3A illustrates an overhead schematic diagram of an hazardous material storage bank system 300 that illustrates an example configuration of wellbores that can be formed or used to store hazardous material, such as spent nuclear fuel, biological material, or chemical material. Hazardous material storage bank system 300 includes a vertical wellbore 302 (viewed from above here) with multiple horizontal wellbores 304 extending therefrom. In this example, four horizontal wellbores 304 may be formed from the single vertical wellbore 302. The example hazardous material storage bank system 300 shows a storage bank that can provide long-term (e.g., millions of years) storage for a volume of hazardous material greater than, for example, the hazardous material storage bank system 100. For instance, each horizontal wellbore 304 may be substantially similar to the substantially horizontal portion 110 shown in FIG. 2A, which can store one or more containers 126 of hazardous material. Each horizontal wellbore 304 may be formed in the storage layer 118 or below the storage layer 118 to provide a sufficient seal against the diffusion of hazardous output in the event of a leak from the one or more containers. Thus, in the example of hazardous material storage bank system 300, hazardous material may be stored more efficiently, as only a single vertical wellbore 302 need be formed to account for multiple horizontal wells 304. FIG. 3B is another schematic illustration of another example implementation of a hazardous material storage bank system according to the present disclosure. FIG. 3B illustrates an overhead schematic diagram of an hazardous material storage bank system 350 that illustrates an example configuration of wellbores that can be formed or used to store hazardous material, such as spent nuclear fuel, biological material, or chemical material. In this example, the system 350 includes a vertical wellbore 352 with multiple lateral wellbores 354 formed from the vertical wellbore 352. The lateral wellbores 354, in this example, are substantially parallel to each other in a “pitchfork” pattern (or other pattern, such as an “F” pattern, crow's foot pattern, or otherwise). Each lateral wellbore 354 may be formed in the storage layer 118 or below the storage layer 118 to provide a sufficient seal against the diffusion of hazardous output in the event of a leak from the one or more containers. In addition, each lateral wellbore 354 may be or include a storage area for containers 126. FIGS. 4A-4C are schematic illustrations of an example implementation of a hazardous material container according to the present disclosure. FIGS. 4A-4C illustrate isometric, vertical cross-section, and horizontal cross-section views, respectively, of a hazardous material container 400. In some aspects, the hazardous material container 400 may be similar to the illustrated container 126 and usable in the hazardous material storage bank system 100, the hazardous material storage bank system 400, or other hazardous material storage bank system according to the present disclosure. The hazardous material container 400 may be used to store chemical hazardous material, biological hazardous material, nuclear hazardous material, or otherwise. For example, in the illustrated implementation, the hazardous material container 400 stores spent nuclear fuel in the form of spent nuclear fuel rods 406. As illustrated, the hazardous material container 400 includes a housing 402 (e.g., a crush-proof or crush resistant housing) that encloses a volume 404 to store the hazardous material. In this example, the spent nuclear fuel rods 406 are positioned in the housing 402 prior to sealing of the hazardous material container 400. Each spent nuclear fuel rod 406 comprises multiple spent nuclear fuel pellets 408. For example, the spent nuclear fuel pellets 408 contain most of the radioisotopes (including the tritium) of the spent nuclear fuel removed from a nuclear reactor. To form the spent nuclear fuel rods 406, the fuel pellets 408 are surrounded by zirconium tubes, just as in the reactor. These tubes offer an additional level of containment. The tubes can be mounted in the original fuel assemblies, or removed from those assemblies for tighter packing for the spent nuclear fuel rods 406. The tubes are placed in sealed capsules to form the rods 406, typically 15 feet long, with a diameter large enough to store a substantial number of fuel pellets 408, yet small enough to permit placement in the housing 402. In some aspects, the housing 402 (and other components of the hazardous material container 400) may be formed from metals or ceramics that, for example, have very high resistance to corrosion or radioactivity (e.g., zirconium or its alloy zircaloy, stainless steel, titanium, or other low corrosion materials). In addition, in some aspects, a storage area into which the container 400 is placed may be filled or partially filled with nitrogen, argon, or some other gas that reduces danger of corrosion to the housing 402 and other components of the container 400. Further, the dimensions of the housing 402 (and hazardous material container 400, generally) may be designed to fit in a wellbore, such as the wellbore 104. Example dimensions of the housing 402 may include a length, L, of between 12 and 15 feet, and, in the case of a substantially square housing 402, side width, W, of between 5 and 9 inches. The housing 402, in alternative aspects, may have a substantially circular horizontal cross-section diameter of between about 7 and 13 in. In some examples, the hazardous material container 400 (and container 126) may be sized (e.g., length and width/diameter) for efficient deposit and retrieval into and from the wellbore 104. For example, the length, L, may be determined based on, e.g., the radius dimension of the radiussed portion 108, to ensure that the hazardous material container 400 may be moved through the radiussed portion 108 and into the substantially horizontal portion 110. As another example, the width, W, may be determined based on a diameter of one or more of the casings in the wellbore 104, such as the surface casing 120 and the production casing 122. The illustrated hazardous material container 400 also includes a connector portion 410, which is shown on one end of the housing 402 but may be formed on both ends as well. In some aspects, the connector portion 410 may facilitate coupling of the hazardous material container 400 to a downhole tool (e.g., downhole tool 128) to permit deposit and retrieval of the hazardous material container 400 from storage in a wellbore. Further, the connector portion 410 may facilitate coupling of one hazardous material container 400 to another hazardous material container 400. The connector portion 410, in some aspects, may be a threaded connection. For example, a connector portion 410 on one end of the housing 402 may be a male threaded connection while a connector portion 410 on the opposite end of the housing 402 may be a female threaded connection. In alternative aspects, the connector portion 410 may be an interlocking latch, such that rotation (e.g., 360 degrees or less) may latch (or unlatch) the housing 402 to a downhole tool or other hazardous material container 400. In alternative aspects, the connector portion 410 may include one or more magnets (e.g., rare Earth magnets, electromagnets, a combination thereof, or otherwise) which attractingly couple to, e.g., a downhole tool or another hazardous material container 400. Referring generally to FIGS. 1A-1B, 2A-2E, 4A-4C, the example hazardous material storage bank system (e.g., 100, 300, and otherwise) may provide for multiple layers of containment to ensure that a hazardous material (e.g., biological, chemical, nuclear) is sealingly stored in an appropriate subterranean layer. In some example implementations, there may be at least twelve layers of containment. In alternative implementations, a fewer or a greater number of containment layers may be employed. First, using spent nuclear fuel as an example hazardous material, the fuel pellets are taken from the reactor and not modified. They may be made from sintered uranium dioxide (UO2), a ceramic, and may remain solid and emit very little gas other than short-lived tritium. Unless the pellets are exposed to extremely corrosive conditions or other effects that damage the multiple layers of containment, most of the radioisotopes (including the tritium) will be contained in the pellets. Second, the fuel pellets are surrounded by the zircaloy tubes of the fuel rods, just as in the reactor. As described, the tubes could be mounted in the original fuel assemblies, or removed from those assemblies for tighter packing. Third, the tubes are placed in the sealed housings of the hazardous material container. The housing may be a unified structure or multi-panel structure, with the multiple panels (e.g., sides, top, bottom) mechanically fastened (e.g., screws, rivets, welds, and otherwise). Fourth, a material (e.g., solid or fluid) may fill the hazardous material container to provide a further buffer between the material and the exterior of the container. Fifth, the hazardous material container(s) are positioned (as described above), in a wellbore that is lined with a steel or other sealing casing that extends, in some examples, throughout the entire wellbore (e.g., a substantially vertical portion, a radiussed portion, and a substantially horizontal portion). The casing is cemented in place, providing a relatively smooth surface (e.g., as compared to the wellbore wall) for the hazardous material container to be moved through, thereby reducing the possibility of a leak or break during deposit or retrieval. Sixth, the cement that holds or helps hold the casing in place, may also provide a sealing layer to contain the hazardous material should it escape the container. Seventh, the hazardous material container is stored in a portion of the wellbore (e.g., the substantially horizontal portion) that is positioned within a thick (e.g., 100-200 feet) seam of a rock formation that comprises a storage layer. The storage layer may be chosen due at least in part to the geologic properties of the rock formation (e.g., no mobile water, low permeability, thick, appropriate ductility or non-brittleness). For example, in the case of shale as the rock formation of the storage layer, this type of rock may offers a level of containment since it is known that shale has been a seal for hydrocarbon gas for millions of years. The shale may contain brine, but that brine is demonstrably immobile, and not in communication with surface fresh water. Eighth, in some aspects, the rock formation of the storage layer may have other unique geological properties that offer another level of containment. For example, shale rock often contains reactive components, such as iron sulfide, that reduce the likelihood that hazardous materials (e.g., spent nuclear fuel and its radioactive output) can migrate through the storage layer without reacting in ways that reduce the diffusion rate of such output even further. Further, the storage layer may include components, such as clay and organic matter, that typically have extremely low diffusivity. For example, shale may be stratified and composed of thinly alternating layers of clays and other minerals. Such a stratification of a rock formation in the storage layer, such as shale, may offer this additional layer of containment. Ninth, the storage layer may be located deeper than, and under, an impermeable layer, which separates the storage layer (e.g., vertically) from a mobile water layer. Tenth, the storage layer may be selected based on a depth (e.g., 3000 to 12,000 ft.) of such a layer within the subterranean layers. Such depths are typically far below any layers that contain mobile water, and thus, the sheer depth of the storage layer provides an additional layer of containment. Eleventh, example implementations of the hazardous material storage bank system of the present disclosure facilitate monitoring of the stored hazardous material. For example, if monitored data indicates a leak or otherwise of the hazardous material (e.g., change in temperature, radioactivity, or otherwise), or even tampering or intrusion of the container, the hazardous material container may be retrieved for repair or inspection. Twelfth, the one or more hazardous material containers may be retrievable for periodic inspection, conditioning, or repair, as necessary (e.g., with or without monitoring). Thus, any problem with the containers may be addressed without allowing hazardous material to leak or escape from the containers unabated. FIG. 5 is a schematic illustration of another example implementation of a hazardous material storage bank system according to the present disclosure. FIG. 5 illustrates an example implementation of a hazardous material storage bank system 500, which includes hazardous material storage bank system 500 includes a wellbore 504 formed (e.g., drilled or otherwise) from a terranean surface 502 and through multiple subterranean layers 512, 514, 516, and 518. The illustrated wellbore 504 is a directional wellbore in this example of hazardous material storage bank system 500. For instance, the wellbore 504 includes a substantially vertical portion 506 coupled to a radiussed or curved portion 508, which in turn is coupled to a substantially horizontal portion 510. Generally, such components of the hazardous material storage bank system 500 are substantially the same as similarly-named components of hazardous material storage bank system 100. For example, the illustrated wellbore 504 has a surface casing 520 positioned and set around the wellbore 504 from the terranean surface 502 into a particular depth in the Earth. For example, the surface casing 520 may be a relatively large-diameter tubular member (or string of members) set (e.g., cemented) around the wellbore 504 in a shallow formation. For example, in this implementation of the hazardous material storage bank system 500, the surface casing 520 extends from the terranean surface through a surface layer 512. The surface layer 512, in this example, is a geologic layer comprised of one or more layered rock formations. In some aspects, the surface layer 512 in this example may or may not include freshwater aquifers, salt water or brine sources, or other sources of mobile water (e.g., water that moves through a geologic formation). In some aspects, the surface casing 520 may isolate the wellbore 504 from such mobile water, and may also provide a hanging location for other casing strings to be installed in the wellbore 504. Further, although not shown, a conductor casing may be set above the surface casing 520 (e.g., between the surface casing 520 and the surface 502 and within the surface layer 512) to prevent drilling fluids from escaping into the surface layer 512. As illustrated, a production casing 522 is positioned and set around the wellbore 504 downhole of the surface casing 520. Although termed a “production” casing, in this example, the casing 522 may or may not have been subject to hydrocarbon production operations. Thus, the casing 522 refers to and includes any form of tubular member that is set (e.g., cemented) in the wellbore 504 downhole of the surface casing 520. In some examples of the hazardous material storage bank system 500, the production casing 522 may begin at an end of the radiussed portion 508 and extend throughout the substantially horizontal portion 510. As shown, cement 530 is positioned (e.g., pumped) around the casings 520 and 522 in an annulus between the casings 520 and 522 and the wellbore 504. The cement 530, for example, may secure the casings 520 and 522 (and any other casings or liners of the wellbore 504) through the subterranean layers under the terranean surface 502. As illustrated, the wellbore 504 extends tluough subterranean layers 512, 514, and 516, and lands in storage layer 518. As discussed above, the surface layer 512 may or may not include mobile water. Subterranean layer 514, which is below the surface layer 512, in this example, is a mobile water layer 514. Below the mobile water layer 514, in this example implementation of hazardous material storage bank system 500, is an impermeable layer 516. The impermeable layer 516, in this example, may not allow mobile water therethrough. Thus, relative to the mobile water layer 514, the impermeable layer 516 may have low permeability, e.g., on the order of nanodarcy permeability. Additionally, in this example, the impermeable layer 516 may be a relatively non-ductile (i.e., brittle) geologic formation. Below the impermeable layer 516 is a storage layer 518. The storage layer 518, in this example, may be chosen as the landing for the substantially horizontal portion 510, which stores the hazardous material, for several reasons. Relative to the impermeable layer 516 or other layers, the storage layer 518 may be thick, e.g., between about 100 and 200 feet of TVD. Thickness of the storage layer 518 may allow for easier landing and directional drilling, thereby allowing the substantially horizontal portion 510 to stay within the storage layer 518 during formation (e.g., drilling). If formed through an approximate horizontal center of the storage layer 518, the substantially horizontal portion 510 may be surrounded by about 50 to 100 feet of the geologic formation that comprises the storage layer 518. Further, the storage layer 518 may also have no mobile water, e.g., due to a very low permeability of the layer 518 (e.g., on the order of milli- or nanodarcys). In addition, the storage layer 518 may have sufficient ductility, such that a brittleness of the rock formation that comprises the layer 518 is between about 3 MPa and 10 MPa. Examples of rock formations of which the storage layer 518 may be composed include: shale and anhydrite. In some examples implementations of the hazardous material storage bank system 500, the storage layer 518 is composed of shale. Shale, in some examples, may have properties that fit within those described above for the storage layer 518. For example, shale formations may be suitable for a long-term confinement of hazardous material and for their isolation from mobile water layer 514 (e.g., aquifers) and the terranean surface 502. Shale formations may be found relatively deep in the Earth, typically 3000 feet or greater, and placed in isolation below any fresh water aquifers. Hazardous material storage bank system 500 also includes a work string 524 (e.g., tubing, coiled tubing, wireline, or otherwise) that is extendable through the wellbore 504 to deposit (e.g., pump) a hazardous slurry 526 into a portion of the wellbore 504 (e.g., the substantially horizontal portion 510). The hazardous material slurry 526 comprises a mixture of a hardenable material 528 and hazardous material 532. For example, the hardenable material 528 may be cement, a cementitious material, resin, concrete, adhesive, grout, or other hardenable (e.g., over a known time duration). The hazardous material 532 may be, for example, biological material, chemical material, or nuclear material such as spent nuclear fuel pellets. In operation, the work string 524 may deposit (e.g., through pumping) the hazardous material slurry 426 in the substantially horizontal portion 510 of the wellbore 504. Over time, the hardenable material 528 in the slurry 526 may harden, thereby substantially trapping and sealing the hazardous material 532 within the hardened slurry and in the wellbore 504. The hazardous material 532 may thus be sealed in the hardened material 528, within the wellbore 504, and within the storage layer 518, providing multiple layers of containment of any output from the hazardous material 532. The hardening time can be set to be short, or it could be set to a longer period (years or decades) to facilitate early retrieval, if it is determined that easier retrieval during the first few years would be advantageous. Although not shown, once the deposit operation is completed, a seal (e.g., seal 134) may be placed in the wellbore 504 uphole of the hardened slurry. Further, once sealed, a monitoring system (e.g., as shown and described with reference to one or more of FIGS. 2B-2E) may be installed in system 500 to monitor one or more variables associated with the hazardous material 532 (e.g., temperature, radioactivity, water vapor, oxygen, seismic activity, tampering or otherwise). FIGS. 6A-6C are flowcharts that illustrate example methods 600, 640, and 670, respectively, associated with storing hazardous material. Turning to method 600, this example method for storing hazardous material may be performed with or by, e.g., hazardous material storage bank system 100 as described with reference to FIGS. 1A-1B and 2A-2E. Alternatively, method 600 may be performed by another hazardous material storage bank system in accordance with the present disclosure. Method 600 may begin at step 602, which includes moving a storage container through an entry of a wellbore that extends into a terranean surface. The storage container encloses a hazardous material, such as chemical, biological, or nuclear waste, or another hazardous material. In some aspects, the storage container may be positioned in the entry directly from a mode of transportation (e.g., truck, train, rail, or otherwise) which brought the hazardous material to the site of the wellbore. In some aspects, a packaging of the hazardous material during transport is not removed for movement of the storage container into the entry. In some aspects, such transport packaging is only removed as the storage container fully enters the wellbore. Method 600 may continue at step 604, which includes moving the storage container through the wellbore that includes a substantially vertical portion, a transition portion, and a substantially horizontal portion. In some aspects, the wellbore is a directional, or slant wellbore. The storage container may be moved through the wellbore in a variety of manners. For example, a tool string (e.g., tubular work string) or wireline may include a downhole tool that couples to the storage container and moves (e.g., pushes) the storage container from the entry to the horizontal portion of the wellbore. As another example, the storage container may ride on rails installed in the wellbore, e.g., a cased wellbore. As yet another example, the storage container may be moved through the wellbore with a wellbore tractor (e.g., motored or powered tractor). In another example, the tractor could be built as part of the storage container. As yet a further example, the storage container may be moved through the wellbore with a fluid (e.g., gas or liquid) circulated through the wellbore. Method 600 may continue at step 606, which includes moving the storage container into a storage area located within or below a shale formation. For example, the horizontal portion of the wellbore may include or be coupled to the storage area and may be formed through a shale seam within a subterranean zone. In some aspects, the shale may include one or more geologic qualities that provide for a fluidic seal (e.g., gas and liquid) against the escape of any hazardous material beyond the shale formation (e.g., vertically or horizontally). In alternative aspects, the storage area may be formed in the horizontal portion of the wellbore in a rock formation that is not shale, but shares particular geologic characteristics with shale (e.g., anhydrite, and other formations). For example, the rock formation of the storage area may be relatively impermeable, with permeability values less than 0.001 millidarcys (and even down to nanodarcys). As another example, the rock formation may be ductile, having a brittleness of less than about 10 MPa so as to prevent or help prevent fracturing that can allow hazardous material leaks therethrough. Brittleness, as used herein in example implementations, is the ratio of compressive stress of the rock formation to tensile strength of the rock formation. As another example, the rock formation may be relatively thick, with thickness proximate the storage area of between about 100 and 200 feet (although less thick and more thick formations are also contemplated by the present disclosure). As another example, the rock formation may be composed of clay or other organic material, e.g., of about 20-30% weight by volume, to help ductility. Method 600 may continue at step 608, which includes forming a seal in the wellbore that isolates the storage portion of the wellbore from the entry of the wellbore. For example, once the storage container is moved into the storage area (or after all storage containers are moved into the storage area), a seal may be formed in the wellbore. The seal may be a cement plug, an inflatable seal (e.g., packer), or other seal or combination of such seals. In some aspects, the seal is removable so as to facilitate a subsequent retrieval operation of the storage container. Method 600 may continue at step 610, which includes monitoring at least one variable associated with the storage container from a sensor positioned proximate the storage area. The variable may include one or more of temperature, radioactivity, seismic activity, oxygen, water vapor, acidity, or other variable that indicates a presence of the hazardous material (e.g., within the wellbore, outside of the storage container, in the rock formation, or otherwise). In some aspects, one or more sensors may be positioned in the wellbore, on or attached to the storage container, within a casing installed in the wellbore, or in the rock formation proximate the wellbore. The sensors, in some aspects, may also be installed in a separate wellbore (e.g., another horizontal or vertical wellbore) apart from the storage area. Method 600 may continue at step 612, which includes recording the monitored variable at the terranean surface. For example, variable data received at the one or more sensors may be transmitted (e.g., on a conductor or wirelessly) to a monitoring system (e.g., control system 146) at the terranean surface. The monitoring system may perform a variety of operations. For example, the monitoring system may record a history of one or more of the monitored variables. The monitoring system may provide trend analysis in the recorded variable data. As another example, the monitoring system may include one or more threshold limits for each of the monitored variables, and provide an indication when such threshold limits are exceeded. Method 600 may continue at step 614, which includes determining whether the monitored variable exceeds a threshold value. For example, the one or more sensors may monitor radioactivity in the wellbore, e.g., an amount of radiation released by the hazardous material, whether in alpha or beta particles, gamma rays, x-rays, or neutrons. The sensors, for instance, may determine an amount of radioactivity, in units of measure of curie (Ci) and/or becquerel (Bq), rads, grays (Gy), or other units of radiation. If the amount of radioactivity does not exceed a threshold value that, for example, would indicate a large leak of hazardous nuclear material from the storage container, then the method 600 may return to step 610. If the determination is “yes,” method 600 may continue at step 616, which includes removing the seal from the wellbore. For example, in some aspects, once a threshold value (or values) is exceeded, a retrieval operation may be initiated by removing the seal. In alternative aspects, exceeding of a threshold value may not automatically trigger a retrieval operation or removal of the wellbore seal. In some aspects, there may be multiple monitored variables, and a “yes” determination is only made if all monitored variables exceed their respective threshold values. Alternatively, a “yes” determination may be made if at least one monitored variable exceeds its respective threshold value. Method 600 may continue at step 618, which includes retrieving the storage container from the storage area to the terranean surface. For example, once the seal is removed (e.g., drilled through or removed to the terranean surface), the work string may be tripped into the wellbore to remove the storage container (or containers) for inspection, repair, or otherwise. In some aspects, rather than removing the seal from the wellbore to retrieve the storage container, other remedial measures may be taken. For example, if the determination is “yes” in step 614, rather than recovering the hazardous material, a decision might be made to improve the seal. This could be done, for example, by injecting a cement or other sealant into the borehole to fill the space previously filled with gas. Turning to method 640, this example method for storing hazardous material may be performed prior to, for example, method 600. For example, in some aspects, the wellbore into which the storage container is moved in method 400 is formed primarily for the storage of hazardous material. Alternatively, the wellbore may have been formed prior to execution of method 600 and, in some aspects, years or decades prior to execution of method 600. For instance, the wellbore may have been initially formed with a primary purpose of hydrocarbon production. Method 640 may begin at step 642, which includes forming drilling) the wellbore from the terranean surface to the rock formation. In some aspects, the rock formation is shale or other rock formation that includes geologic characteristics suitable for hazardous material storage. Method 640 may continue at step 644, which includes installing a casing in the wellbore that extends from at or proximate the terranean surface, through at least a portion of the wellbore. In some aspects, the casing may be installed an entire length of the wellbore (e.g., through a vertical portion, a transition portion, and a horizontal or slant portion of the wellbore. Method 640 may continue at step 646, which includes cementing the casing to the wellbore. In some aspects, the cement may be installed throughout an entire length of the wellbore. Alternatively, only a portion of the casing may be cemented in the wellbore. Method 640 may continue at step 648, which includes producing hydrocarbon fluid from the rock formation, through the wellbore, and to the terranean surface. In some aspects, the wellbore and casing may first be completed, e.g., perforated and hydraulically fractured, prior to production of hydrocarbon fluids. In some aspects, prior to or subsequent to completing the wellbore, it may be determined that there is insufficient hydrocarbons in the rock formation for economical production. Method 640 may continue at step 650, which includes shutting in the wellbore. In some aspects, shutting in the wellbore may include cementing the wellbore though at least a portion of its entire length. Thus, in such aspects, prior to step 602 of method 600, the wellbore may be re-formed (e.g., drilled out) to remove the cementing or other seal. In some aspects, step 650 may not be performed, as step 602 from method 600 may be initiated directly after production of hydrocarbons in step 648 is completed. Turning to method 670, this example method for storing hazardous material may be performed with or by, e.g., hazardous material storage bank system 500 as described with reference to FIG. 5. Alternatively, method 670 may be performed by another hazardous material storage bank system in accordance with the present disclosure. Method 670 may begin at step 672, which includes forming a vertical portion of a wellbore from a terranean surface into a subterranean zone. Method 670 may continue at step 674, which includes forming a transitional portion of the wellbore, from the vertical portion, through the subterranean zone. Method 670 may continue at step 676, which includes forming a horizontal portion of the wellbore, from the transitional portion, into or beneath a rock formation. The rock formation may be comprised of shale or other rock formation with appropriate geologic characteristics (e.g., permeability, ductility, thickness and/or claim or organic material composition) that evidence a fluid seal between the rock formation and a subterranean layer that includes mobile water. In some alternative aspects, however, the formed wellbore may be a substantially vertical wellbore, with no transition or horizontal portion. Method 670 may continue at step 678, which includes pumping a hardenable slurry that includes a mixture of a hardenable material and a spent nuclear fuel material into the horizontal portion of the wellbore (or vertical portion if no horizontal portion). The hardenable material may include, for example, a cementitious material, a hardenable resin or epoxy, concrete, grout, or other flowable material that hardens into a solid over a defined period of time. The spent nuclear fuel, e.g., nuclear fuel pellets, may be mixed into the hardenable material such that when the hardenable material hardens, the spent nuclear fuel pellets are rigidly contained in the hardened slurry. FIG. 7 is a schematic illustration of an example controller 700 (or control system) for processes associated with a hazardous material storage bank. For example, the controller 700 can be used for the operations described previously, for example as or as part of the monitoring control system 146. For example, the controller 700 may be communicably coupled with, or as a part of, a hazardous material storage bank system as described herein. The controller 700 is intended to include various forms of digital computers, such as printed circuit boards (PCB), processors, digital circuitry, or otherwise that is part of a vehicle. Additionally the system can include portable storage media, such as, Universal Serial Bus (USB) flash drives. For example, the USB flash drives may store operating systems and other applications. The USB flash drives can include input/output components, such as a wireless transmitter or USB connector that may be inserted into a USB port of another computing device. The controller 700 includes a processor 710, a memory 720, a storage device 730, and an input/output device 740. Each of the components 710, 720, 730, and 740 are interconnected using a system bus 750. The processor 710 is capable of processing instructions for execution within the controller 700. The processor may be designed using any of a number of architectures. For example, the processor 710 may be a CISC (Complex Instruction Set Computers) processor, a RISC (Reduced Instruction Set Computer) processor, or a MISC (Minimal Instruction Set Computer) processor. In one implementation, the processor 710 is a single-threaded processor. In another implementation, the processor 710 is a multi-threaded processor. The processor 710 is capable of processing instructions stored in the memory 720 or on the storage device 730 to display graphical information for a user interface on the input/output device 740. The memory 720 stores information within the controller 700. In one implementation, the memory 720 is a computer-readable medium. In one implementation, the memory 720 is a volatile memory unit. In another implementation, the memory 720 is a non-volatile memory unit. The storage device 730 is capable of providing mass storage for the controller 700. In one implementation, the storage device 730 is a computer-readable medium. In various different implementations, the storage device 730 may be a floppy disk device, a hard disk device, an optical disk device, a tape device, flash memory, a solid state device (SSD), or a combination thereof. The input/output device 740 provides input/output operations for the controller 700. In one implementation, the input/output device 740 includes a keyboard and/or pointing device. In another implementation, the input/output device 740 includes a display unit for displaying graphical user interfaces. The features described can be implemented in digital electronic circuitry, or in computer hardware, firmware, software, or in combinations of them. The apparatus can be implemented in a computer program product tangibly embodied in an information carrier, for example, in a machine-readable storage device for execution by a programmable processor; and method steps can be performed by a programmable processor executing a program of instructions to perform functions of the described implementations by operating on input data and generating output. The described features can be implemented advantageously in one or more computer programs that are executable on a programmable system including at least one programmable processor coupled to receive data and instructions from, and to transmit data and instructions to, a data storage system, at least one input device, and at least one output device. A computer program is a set of instructions that can be used, directly or indirectly, in a computer to perform a certain activity or bring about a certain result. A computer program can be written in any form of programming language, including compiled or interpreted languages, and it can be deployed in any form, including as a stand-alone program or as a module, component, subroutine, or other unit suitable for use in a computing environment. Suitable processors for the execution of a program of instructions include, by way of example, both general and special purpose microprocessors, and the sole processor or one of multiple processors of any kind of computer. Generally, a processor will receive instructions and data from a read-only memory or a random access memory or both. The essential elements of a computer are a processor for executing instructions and one or more memories for storing instructions and data. Generally, a computer will also include, or be operatively coupled to communicate with, one or more mass storage devices for storing data files; such devices include magnetic disks, such as internal hard disks and removable disks; magneto-optical disks; and optical disks. Storage devices suitable for tangibly embodying computer program instructions and data include all forms of non-volatile memory, including by way of example semiconductor memory devices, such as EPROM, EEPROM, solid state drives (SSDs), and flash memory devices; magnetic disks such as internal hard disks and removable disks; magneto-optical disks; and CD-ROM and DVD-ROM disks. The processor and the memory can be supplemented by, or incorporated in, ASICs (application-specific integrated circuits). To provide for interaction with a user, the features can be implemented on a computer having a display device such as a CRT (cathode ray tube) or LCD (liquid crystal display) or LED (light-emitting diode) monitor for displaying information to the user and a keyboard and a pointing device such as a mouse or a trackball by which the user can provide input to the computer. Additionally, such activities can be implemented via touchscreen flat-panel displays and other appropriate mechanisms. The features can be implemented in a control system that includes a back-end component, such as a data server, or that includes a middleware component, such as an application server or an Internet server, or that includes a front-end component, such as a client computer having a graphical user interface or an Internet browser, or any combination of them. The components of the system can be connected by any form or medium of digital data communication such as a communication network. Examples of communication networks include a local area network (“LAN”), a wide area network (“WAN”), peer-to-peer networks (having ad-hoc or static members), grid computing infrastructures, and the Internet. While this specification contains many specific implementation details, these should not be construed as limitations on the scope of any inventions or of what may be claimed, but rather as descriptions of features specific to particular implementations of particular inventions. Certain features that are described in this specification in the context of separate implementations can also be implemented in combination in a single implementation. Conversely, various features that are described in the context of a single implementation can also be implemented in multiple implementations separately or in any suitable subcombination. Moreover, although features may be described above as acting in certain combinations and even initially claimed as such, one or more features from a claimed combination can in some cases be excised from the combination, and the claimed combination may be directed to a subcombination or variation of a subcombination. Similarly, while operations are depicted in the drawings in a particular order, this should not be understood as requiring that such operations be performed in the particular order shown or in sequential order, or that all illustrated operations be performed, to achieve desirable results. In certain circumstances, multitasking and parallel processing may be advantageous. Moreover, the separation of various system components in the implementations described above should not be understood as requiring such separation in all implementations, and it should be understood that the described program components and systems can generally be integrated together in a single software product or packaged into multiple software products. A number of implementations have been described. Nevertheless, it will be understood that various modifications may be made without departing from the spirit and scope of the disclosure. For example, example operations, methods, or processes described herein may include more steps or fewer steps than those described. Further, the steps in such example operations, methods, or processes may be performed in different successions than that described or illustrated in the figures. Accordingly, other implementations are within the scope of the following claims.
	description	This application is a continuation of application Ser. No. 12/369,834, filed on Feb. 12, 2009 now U.S. Pat. No. 8,696,174 that issued on Apr. 15, 2014 which claims the benefit of Provisional Application Ser. No. 61/086,078 filed Aug. 4, 2008 the entire contents of which is hereby expressly incorporated by reference herein. Not Applicable Not Applicable Not Applicable 1. Field of the Invention This invention relates to a light source, and more particularly to a search light that uses multiple light sources to create a single concentrated beam of light as a menorah configuration of light sources. 2. Description of Related Art including information disclosed under 37 CFR 1.97 and 1.98 Collimators are well known in the optical arts, and typically include a plurality of lens or reflectors that act upon light to emit nearly parallel rays. Such collimators include searchlights, headlamps and light projectors. A typical example of a light projector designed to emit a collimated beam can be found in U.S. Pat. No. 5,918,968, issued to Choi, which provides a parabolic reflector for converting light emitted from a lamp to parallel rays, a biconvex lens for collimating both direct and reflected light from the light source, a combination lens having a first lens and a second lens for focusing the collimated light from the biconvex lens to a focal point, and an image lens located beyond the focal point for converting the light focused at the focal point into a parallel beam. U.S. Pat. No. 6,827,475, issued to Vetorino et al., combines a plurality of lens and reflectors to collimate light that includes a conical reflector disposed about the base of a light emitting diode (LED) and a lens specially designed to focus the collected light into a nearly collimated beam. The lens have opposite, substantially elliptical surfaces that collect and collimate the rapidly diverging light from the LED and the reflector. Vetorino et al., however, do not provide for the compression of the collimated beam. It is also known in the art that the illuminance Lx of a light stream from a light source located perpendicular to an area illuminates that area according to the following relationship: Lx=Lm/m.sup.2. For example, one Lx of illuminance is equal to one Lm of luminous flux for an illuminated surface measuring one square meter in area, and with the light source arranged perpendicular to the surface. In another example, if the luminous flux is equal to 1,000 Lm and the uniformly illuminated surface is one square meter, then the illuminance of that area equals 1,000 Lx. Thus, in order to measure the luminous flux in a uniformly illuminated area of 1.0 square meters, a Lux Meter may be placed anywhere in the illuminated area. Some prior art producers of light sources, e.g., prior art flashlights utilizing light emitting diodes (LED) claim values of luminous flux (Lm) which in some instances appear higher than the maximum value that can be emitted by the light emitting diode in all directions. Such claims do not account for the uniformity of illuminance (Lx) of an illuminated area where the measurement was taken. Experimentally, the illuminance of two prior art LED's, have been measured and compared to their maximum luminous flux. Two prior art flashlights were chosen for the measurement: (1) ND HB F5, 6V, 2CR 123, 107 Lm Cree LED (hereinafter “HB F5”), and (2) NH HB VIGOUR, 6V, 2CR 123, 107 Lm Cree LED (hereinafter “HB VIGOUR”). Each flashlight having substantially identical electrical specifications, but different optical schematics. The HB F5 appears to utilize an optical schematic that allows for concentrated light emission with uniform luminous flux through the light stream and +/−2.5° angle of dispersion relative to the optical axis. The HB VIGOUR utilizes a focusing output lens system. Other light sources include flashlights which typically comprise a light source, a reflector located behind the light source, a lens or glass in front of the reflector, and a power supply. The reflector and the lens are intended to collect light from the source and collimate or focus the light into a desired beam. Such light sources are often portable, and generally produce a diverging beam of light whereby the brightness varies across the beam. Typically, the light beam is brightness at its center, and drops off dramatically at its peripheral edge. Examples of such prior art lights may be found in U.S. Pat. Nos. 1,823,762, 2,228,078, 4,286,311, and 4,527,223. An important advantage of the present invention is the provision of a light device where the light beam is minimally divergent or compressed along the optical axis, thereby allowing for increased intensity over an illumination range of interest. A number of patents and or publications have been made to address these issues. Exemplary examples of patents and or publication that try to address this/these problem(s) are identified and discussed below. The present invention provides a flashlight comprising a power supply, a light source for emitting light, a collecting lens for gathering and compressing the light from the light source, a negative lens for diverging the light, a collimating lens for projecting the light along a ray parallel with an optical axis, and a housing for mounting each component therein. In one embodiment, a flashlight is provided that includes a power supply, a light source, an adjustable collecting lens for gathering and compressing the light from the light source, a negative lens for diverging the light, a collimating lens for projecting the light along a ray at an adjustable angle with an optical axis, and a housing for mounting each component therein. It is an object of the merging light from multiple light sources into a single beam the beams of multiple sources of concentrated light. This provides or light beam that is nearly constant illumination intensity across the beam of light. This reduces or eliminates bight and dim areas that are created from previous light systems that use desecrate lighting elements. It is another object of the menorah configuration to be used for polychromatic light that consisting of or related to radiation of more than one wavelength and for coherent light that is usually monochromatic. The menorah configuration can be used with visible Light, IR and UV wavelengths of light. It is still another object of the menorah configuration design can be used for several layers of single light sources. Various objects, features, aspects, and advantages of the present invention will become more apparent from the following detailed description of preferred embodiments of the invention, along with the accompanying drawings in which like numerals represent like components. This description of preferred embodiments is intended to be read in connection with the accompanying drawings, which are to be considered part of the entire written description of this invention. The drawing figures are not necessarily to scale and certain features of the invention may be shown exaggerated in scale or in somewhat schematic form in the interest of clarity and conciseness. In the description, relative terms such as “horizontal,” “vertical,” “up,” “down,” “top” and “bottom” as well as derivatives thereof (e.g., “horizontally,” “downwardly,” “upwardly,” etc.) should be construed to refer to the orientation as then described or as shown in the drawing figure under discussion. These relative terms are for convenience of description and normally are not intended to require a particular orientation. Terms including “inwardly” versus “outwardly,” “longitudinal” versus “lateral” and the like are to be interpreted relative to one another or relative to an axis of elongation, or an axis or center of rotation, as appropriate. Terms concerning attachments, coupling and the like, such as “connected” and “interconnected,” refer to a relationship wherein structures are secured or attached to one another either directly or indirectly through intervening structures, as well as both movable or rigid attachments or relationships, unless expressly described otherwise. The term “operatively connected” is such an attachment, coupling or connection that allows the pertinent structures to operate as intended by virtue of that relationship. In the claims, means-plus-function clauses, if used, are intended to cover the structures described, suggested, or rendered obvious by the written description or drawings for performing the recited function, including not only structural equivalents but also equivalent structures. FIGS. 1 and 2 correspond to the illuminated fields of the HB VIGOUR and HB F5, respectively. Although, the illuminated area of fields is FIGS. 1 and 2 were each 1.0 m.sup.2, the distance of the flashlights to the illuminated surface varied. HB VIGOUR was located a distance of five meters from the illuminated area, corresponding to illuminated field “1a”; whereas, HB F5 was located a distance of 10.5 meters from the illuminated area, corresponding to illuminated field of FIG. 2. The distribution of illuminance throughout the illuminated fields in FIGS. 1 and 2 is given by Lx=Lm/m.sup.2 as illustrated by FIG. 3. Curve 81 of FIG. 3 represents the distribution of illuminance of the HB F5 having an illuminated area of 1.0 square meter at a distance of 10.5 meter from the illuminated surface. It can be seen that the maximum luminous flux for curve A is about 135 Lm. Curve 82 of FIG. 3 represents the distribution of illuminance of the HB VIGOUR having an illuminated area of 1 square meters at a distance of 5.0 meters from the illuminated surface. It can be seen that the maximum luminous flux for curve B is about 80 Lm. Dotted line 83 of FIG. 3 represents the theoretical maximum luminous flux, 107 Lm, of the LED used in both the HB F5 and HB VIGOUR. The area under curve 81, S1, is calculated as follows: Y=½n exp(−x2/2). Solving for S1 from −56 to +56: .intg.[½n exp(−x2/2)] dx=7,795 units. The area under curve 82, S.sub.2, is 112.times.80=8,960 units. It can be seen that S.sub.1 is smaller than S.sub.2, and S.sub.1/S.sub.2=0.87. Thus, the luminous flux of curve 81 is equal to 87% of 80 Lm which is 70 Lm, but not 135 Lm as some flashlight manufacturer's claim. Thus the uniformity distributed luminous flux cannot exceed the value of 107 L.sub.m because this value is the maximum output of the LED used in both flashlights. Referring to FIGS. 4-6, the present invention provides a flashlight 2 including a lens projection system 4, a light source 6, a power supply 8, and a housing 10. Although described as a portable flashlight for convenience, the present invention may be used for a wide variety of illumination purposes including spotlights and searchlights. Lens projecting system 4 comprises a collecting lens 22, a negative lens 24, and a collimating lens 26. Each lens 22, 24, and 26 is aligned along a common central optical axis 5 and mounted within housing 10. Collecting lens 22 defines a first or light gathering surface 31 and a second or light emitting surface 33 that defines a peripheral edge 35. Collecting lens 22 is mounted between light source 6 and negative lens 24. First surface 31 is nearly planar and arranged so as to be substantially perpendicular to optical axis 5. Second surface 33 is generally convex and intersects first surface 31 along peripheral edge 35. In one exemplary embodiment of the invention, collecting lens 22 is plano-convex with an optical focal length of about 17.5 millimeters and an outside diameter of about 18.0 mm. Negative lens 24 is positioned between the collecting lens 22 and the collimating lens 26, and defines a first surface 41, a second surface 43, and a peripheral edge 45. First surface 41 is generally convex having a first radius of curvature R1 (FIG. 4). Second surface 43 is generally concave having a second radius of curvature R2, wherein R1 is greater than R2. Peripheral edge 45 is generally cylindrical in shape and defines the outer circumferences of the first surface 41 and the second surface 43. In one embodiment of the invention, negative lens 24 is a negative meniscus lens having an optical focal length of −150 mm and an outside diameter of 25.0 mm. Referring to FIG. 5, collimating lens 26 defines a first surface 51, a second surface 53, and a peripheral edge 55, and is mounted between negative lens 24 and an aperture of housing 10. First surface 51 is generally convex having a radius of curvature R3. Second surface 53 is generally convex having a radius of curvature R4. Preferably, R3 is greater than R4. Peripheral edge 55 is generally cylindrical in shape and defines the outer circumferences of first surface 51 and second surface 53. In one embodiment of the invention, the collimating lens 26 is a biconvex lens having an optical focal length of −132 mm and an outside diameter of 43.9 mm. Lenses 22, 24, 26 may be formed from any suitable optical material having a refractive index in the range of 1.47214 to 1.74605. Such materials may include glass, polymers, etc. In one embodiment of the invention, lenses 22, 24, 26 are formed from BK7 optical glass having a refractive index of 1.47214. Light source 6 may be mounted within housing 10 generally along optical axis 5 of lens projection system 4. Light source 6 is often located a first distance D1 away from collecting lens 22 along optical axis 5 in such a manner that substantially all luminous radiation emitted by light source 6 falls upon first surface 31 of collecting lens 22. Distance D1 will depend upon the type of light source provided, since each light source emits light at various beam angles. Light source 6 may be any suitable light generating structure, e.g., incandescent, fluorescent, light emitting diode, etc. In one preferred embodiment of the invention, light source 6 comprises a light emitting diode of the type known in the art. Referring to FIGS. 4-7, housing 10 is shaped and sized so as to enclose and secure lens projecting system 4, light source 6, and power supply 8, while allowing light rays 100,101,102 to travel from light source 6, through light projecting system 4, so as to exit housing 10 via an aperture 107. Housing 10 may be formed from any suitable engineering material, e.g., metal, polymer, rubber, etc., or any combination thereof. Housing 10 generally comprises a plurality of sections 60, 62, 64, 66, 68 centrally disposed about optical axis 5. First section 60 is generally cylindrical in shape having a first end 90 and a second end 91, with light source 6 being mounted adjacent first end 90. Collecting lens 22 is often mounted adjacent to second end 91. In this way, a light ray 100 may travel through first section 60 from light source 6 and through collecting lens 22 adjacent second end 91. Second section 62 is generally cylindrical in shape having a first end 92 and a second end 93, with collecting lens 22 being mounted adjacent first end 92. Negative lens 24 is often mounted adjacent to second end 93. In this way, a light ray 101 (FIG. 4) may travel through second section 62 by passing through collecting lens 22 adjacent first end 92 and negative lens 24 adjacent second end 93. In one embodiment of the invention, second section 62 comprises three sub-sections 70, 72, 74. Sub-sections 70 and 74 are cylindrical in shape, but often with different diameters. Sub-section 72 is frusto-conical in shape and intersects sections 70 and 74. Third section 64 is generally frusto-conical in shape having a first end 94 and a second end 95, with negative lens 24 being mounted adjacent to first end 94. Collimating lens 26 is mounted adjacent to second end 95. In this way, a light ray 102 (FIG. 4) may divergently travel through third section 64 by entering negative lens 24 adjacent to first end 94, and exiting collimating lens 26 at second end 95. Fourth section 66 forms a rim to prevent damage to collecting lens 26. Housing 10 defines an aperture 80 in fourth section 66. In one embodiment of the invention, aperture 80 may have a diameter of about 50 mm. Fifth section 68 is generally cylindrical in shape and contains power supply 8. Section 68 is adjacent to first section 60 and is sized to accommodate the power supply 8. Power supply 8 is often portable and electrically connected to light source 6. Power supply 8 is not limited to any specific type of battery, i.e., alkaline, NiCad, etc.) and may be selected by one skilled in the art to meet requirements of the invention. Referring to FIG. 4, lens projection system 4 creates a preferred light path as defined by rays 100,101,102 whereby light from light source 6 is influenced by light projecting system 4 so as to be projected as a highly collimated beam exiting aperture 80 of housing 10. Light source 6 emits light ray 100 which is gathered at first side 31 of collection lens 22. Collecting lens 22 causes ray 100 to bend so that it follows a path that is nearly parallel to optical axis 5, resulting in ray 101. Ray 101 is then projected through negative lens 26, whereby it diverges from optical axis 5, resulting in ray 102. Ray 102 is then collimated by collimating lens 26 and exits aperture 80 at an angle 110 with optical axis 5. In one embodiment of the invention, the collimated beam exiting aperture 80 may have an angle 110 of +/−2.5° angle with optical axis 5. Advantageously, since all light emitted by light source 6 is gathered by collecting lens 22, the projected beam has uniform brightness at all points throughout its cross section. One embodiment of the invention may have a constant beam angle 110 with first distance D1, between light source 6 and first surface 31 of collection lens 22, being about 19 mm. In such an embodiment, second distance D2, between collection lens 22 and negative lens 24, is about 115 mm, and third distance D3, between the negative lens and the collimating lens, is about 94.4 mm. Referring to FIGS. 5 and 7, an alternative embodiment of the invention provides a flashlight 2 including a lens projection system 4, a light source 6, a power supply 8, and a housing 10. Light source 6 may be adjusted by a distance D1 from the lens projecting system 4, thereby resulting in a variable beam angle 101. First distance D1 may be adjusted between about 2.0 mm to about 11.4 mm, resulting in a beam angle 110 of about 0.25 degrees to 2.5 degrees respectively from optical axis 5. In the alternative embodiment, lens projecting system 4 comprises a collecting lens 22, a negative lens 24, and a collimating lens 26, wherein each lens is aligned along a central optical axis 5 and mounted within housing 10 along optical axis 5. Collecting lens 22 defines a first surface 31, a second surface 33, and a peripheral edge 35 that is mounted between light source 6 and the negative lens 24. Light source 6 is mounted within housing 10 generally along optical axis 5 of lens projecting system 4, and is again positioned a first distance D1 away from collecting lens 22 along optical axis 5 in such a manner that all luminous radiation emitted by light source 6 is projected upon first surface 31 of collecting lens 22. In the alternative embodiment of the invention, first distance D1 may be between about 2.0 mm to about 11.4 mm. Also in this alternative embodiment, housing 10 is shaped and sized to enclose and secure lens projecting system 4, light source 6, and power supply 8 while allowing light rays 100,101,102 to travel from light source 6, through light projecting system 4, and finally through an aperture 80 at a variable angle 110. Housing 10 generally comprises a plurality of sections 200, 210, 220, 230, 240 centrally disposed about optical axis 5. Section 200 is generally cylindrical in shape and hollow, having a first end 202 and a second end 204. A thread 206 is formed on the inside surface of section 200 adjacent to first end 202. Light source 6 is located within section 200 adjacent to first end 202. Referring to FIG. 7, section 210 is generally cylindrical in shape and hollow, having a first end 212 and a second end 214. A thread 216 is formed on the outside surface of section 210 adjacent to first end 212 that matingly complements thread 206. An annular flange 218 projects radially outwardly from the outer surface of section 210 adjacent to second end 214. A collecting lens 22 is mounted adjacent to first end 212 such that light traveling through first end 212 must pass through collecting lens 22. Section 220 is general cylindrical in shape and hollow, having a first end 222 and a frusto-conical second end 224. Section 220 has an internal diameter that is sized to accept annular flange 218 of section 210. A thread 228 is defined on the inner surface of section 220 adjacent to first end 222. Section 230 is generally cylindrical in shape and hollow, having a first end 232 and a second end 234. A thread 236 is defined on the internal surface of section 230 adjacent to a first end 232, and complementary in pitch to a corresponding thread located on the outer surface of second end 214 of section 210. Second end 234 of section 230 includes an annular shoulder 238. Section 240 is a substantially frusto conical, hollow cylinder having a first end 242 and a second end 244. The inner surface of section 240 comprises a series of recess steps suitable for seating negative lens 24 and collimating lens 26. Second end 234 of section 230 is sized so as to be received within an opening located at first end 242 of section 240 such that section 240 abuts shoulder 238. As a result of this construction, negative lens 24 and collimating lens 26, carried by section 240, may be adjusted along common optical access 5 by movement of sections 210 and 230 relative to section 220. FIG. 8 shows an optical schematic. Every source of concentrated light is constructed based on this optical schematic. The lenses 301 and 302 in this figure are a type of light emitting diode 300 and the distances 310 and 311 are determined such that the light emitted by the light emitting diode passes through lenses 301 and 302 and exits lens 302 as a cone of light with homogeneous distribution of light energy is throughout any plane of the light cone perpendicular to the optical axis passing though the centers of lens 301, lens 302 and the light emitting diode 300. All of the light emitted by the light emitting diode and passed through lens 301 and lens 302 is found only within the light cone and no light from the light emitting diode is found outside of the light cone. FIG. 9 shows several light sources combined. The optical axes of all light sources are parallel to each other and the whole system comprising the 7 light sources is symmetrical with respect to the center of the whole assembly. In this figure the multiple light sources 320 are secured in a base 321 that maintains the parallel alignment of the multiple light sources 320. The base 321 is secured to an adjustable base 322 for use as a fixed base, adjustable base or a motorized base 322. The same would be true for a system comprised of any other number of light sources. FIG. 10 shows a schematic drawing showing the light sources on a plane 331-332. The distances between the centers of neighboring light sources are equal to 330. Let us chose any three light sources located on the same axis, for example-axis 331-332 and let us see what they look like on a plane turned 90° to the plane on FIG. 11. It is seen in FIG. 11 that at distance 343 from the light sources the divergence relative to the central light sources is equal to 342, and maintains its value independent of any value of 343. For example, if the beam of each light source has a beam angle of 10°, and 343=6 meters, then the diameter of every beam will be 1 meter and the circular zone of divergence will be only 50 mm wide (while dimension 342=25 mm). This means that the zone of complete convergence of the beams is no less than 90% of the whole beam created by the merged individual beams. The light sources can be several layers of single light sources with a first layer of 7 light sources, next layer 12 light sources, next layers 17 light sources, e.t.c. to increase the intensity of the merged beam. FIG. 12 shows a picture of the light beams as they collectively leave projector, and FIG. 13 shows a picture of the convergence of the beams at a distance. The light can be polychromatic light that consisting of or related to radiation of more than one wavelength and for coherent light that is usually monochromatic. The menorah configuration can be used with visible Light, IR and UV wavelengths of light. Thus, specific embodiments of a compact searchlight utilizing the merging of multiple single beams to a concentrated light have been disclosed. It should be apparent, however, to those skilled in the art that many more modifications besides those described are possible without departing from the inventive concepts herein. The inventive subject matter, therefore, is not to be restricted except in the spirit of the appended claims.
	summary
	abstract	A telescoping guide for extraction and reinsertion support handling of in-core instrument thimble assemblies in the area above the upper support plate in the upper internals of a pressurized water reactor. The telescoping guides extend between the upper ends of the upper internals support columns and an axially movable instrumentation grid assembly which is operable to simultaneously raise the telescoping guides and extract the in-core instrument thimble assemblies from the reactor fuel assemblies.
056174560	claims	1. A method of fabricating a water rod including an ascending tube path having therein a coolant ascending path for guiding upward a coolant supplied, and a descending tube path disposed outside said ascending tube path and having therein a coolant descending tube path for guiding downward said coolant guided by said coolant ascending tube path and discharging said coolant to a region above fuel supporting portions, characterized in that either one of said ascending tube path and said descending tube path is inserted into a coupling member, the upper end of said one tube path is welded to said coupling member, the other of said tube paths is welded to the lower part of said coupling member, and a cover member forming a communication path, for communication of said coolant ascending tube path with said coolant descending tube path, between said cover member and said coupling member is attached to said coupling member.
	abstract	A grid (1) for selective transmission of electromagnetic radiation and a method for manufacturing such grid is proposed. Therein, the grid (1) comprises a structural element with walls (3) comprising a plurality of particles (19) of a radiation-absorbing material wherein the particles (19) are sintered together such that pores (21) are present between neighboring particles (19). The pores (21) are at least partially filled with a second solid material. The filling of the pores (21) can be done by inserting the second material in a liquid, preferably molten form into the pores. The second material can be itself radiation-absorbing as well and may help to both, increase the mechanical stability of the grid and to enhance the radiation-absorbing properties.
	abstract	Systems and methods for detecting an image of an object by use of X-ray beams generated by multiple small area sources are disclosed. A plurality of monochromator crystals may be positioned to intercept the plurality of first X-ray beams such that a plurality of second X-ray beams each having predetermined energy levels is produced. Further, an object to be imaged may be positioned in paths of the second x-ray beams for transmission of the second X-ray beams through the object and emitting from the object a plurality of transmission X-ray beams. The X-ray beams may be directed at angles of incidence upon a plurality of analyzer crystals for detecting an image of the object.
	abstract	A mixed extractant solvent including calix[4]arene-bis-(tert-octylbenzo)-crown-6 (“BOBCalixC6”), 4′,4′,(5′)-di-(t-butyldicyclo-hexano)-18-crown-6 (“DtBu18C6”), and at least one modifier dissolved in a diluent. The mixed extractant solvent may be used to remove cesium and strontium from an acidic solution. The DtBu18C6 may be present from approximately 0.01 M to approximately 0.4M, such as from approximately 0.086 M to approximately 0.108 M. The modifier may be 1-(2,2,3,3-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol (“Cs-7SB”) and may be present from approximately 0.01M to approximately 0.8M. In one embodiment, the mixed extractant solvent includes approximately 0.15M DtBu18C6, approximately 0.007M BOBCalixC6, and approximately 0.75M Cs-7SB modifier dissolved in an isoparaffinic hydrocarbon diluent. The mixed extractant solvent may form an organic phase in an extraction system that also includes an aqueous phase. Methods of extracting cesium and strontium as well as strontium alone are also disclosed.
046817069	summary	BACKGROUND OF THE INVENTION 1. Field of the Invention This invention generally relates to a facility for receiving nuclear waste of various radiation levels in shipping containers and solidly over-packing this waste into a module having a sufficiently low surface radiation count so that the wastes may be safely handled by human workers and permanently buried at a waste disposal site. 2. Description of the Prior Art Systems for packaging nuclear waste are known in the prior art. In the earliest of these systems, such wastes were merely packed on site into 55-gallon steel drums. The drums were then transported to a remote burial site. The surface radiation of these drums was often too high to allow them to be handled by human workers; consequently, the drums were handled by long boom cranes, which dropped the drums into simple trenches, where they were buried. Such systems were known as "kick and roll" systems. Unfortunately, such "kick and roll" systems proved to be unsatisfactory for the land disposal of nuclear wastes. The loose soil which these trenches were filled in with was much more permeable to water than the densely-packed soil which formed the trench sides, or the dense rock strata which typically formed the trench bottom. The permeability of the loose soil surrounding the drums caused these trenches to collect large amounts of standing water in what is known as the "bathtub effect". This standing water ultimately caused the steel walls of the drums buried within these trenches to corrode and collapse. The collapsing drums and compaction of the soil over time resulted in a downward movement or subsidence of the soil which caused a depression to form over the top of the trench. This depression in turn collected rain and other forms of surface water and hence worsened the tendency of the trench to collect and maintain a pool of standing water over the drums. The increase in standing water resulted in still more soil subsidence, and accelerated the corrosion and collapse of the drums buried therein. The corrosion and collapse of the drum containers in such sites has resulted in some radioactive contamination of the ground water flowing through them. To solve the problems associated with such "kick and roll" packaging and disposal systems, packaging systems utilizing radiation-shielding concrete packages were developed. In contrast to the thin walls of the 55-gallon drums, the thick walls of these concrete packages reduced the surface radiation of the resulting package to a point where they did not have to be handled by long-boom cranes. Instead, they could be safely handled by human operators. Additionally, the thick layer of concrete was much more resistant to degradation from ground water. In use, these thick-walled concrete packages were carried to the sites where the waste was generated, which was typically a nuclear power plant. The waste was thrown directly into the interior of these packages, and the packages were sealed on-site at the nuclear plant. The sealed packages were then carried to a remote disposal site and buried. The low surface radiation associated with these concrete packages allowed them to be stacked in an orderly fashion within the burial trench along with wastes in other containers by shielded forklifts. Unfortunately, despite the superiority of such concrete packaging over the drum-type packaging used in "kick and roll" systems, there are still a number of shortcomings associated with this particular packaging system. First, the packaging of the waste at the nuclear power plant for burial at a remotely-located disposal site required a great expenditure in time and effort in transporting the heavy concrete packages to and from the site. Second, the unisolated processing of the waste at the nuclear power plant exposed the plant to the possibility of nuclear contamination if any mishaps occur during the on-site packaging process. Third, there was no provision in such a system for determining whether or not any of the waste dumped into the concrete package was in liquid form. Federal regulations now strictly prohibit the burying of any waste in liquid form; therefore, the inability to quickly and conveniently confirm that none of the wastes loaded into the package are in liquid form is important. Fourth, this system could not conveniently handle high-level wastes, such as spent control rods; the concrete walls of the packages were simply not thick neough to reduce the surface radiation of the package to an acceptable level. Finally, the surface radiation of the concrete packages varied depending on the activity of the particular wastes packed therein; this system had no provision for conveniently confirming that the surface radiation of the resulting package did not exceed the maximum safe level at which the package could be directly handled by human workers. Clearly, a need exists for a packaging system which is capable of packaging radioactive waste of contactable and non-contactable levels of radioactivity into modules whose surface radiation does not exceed that which can be safely handled by human operators. Ideally, such a packaging system would cut to a minimum the amount of transportation of heavy packages, and should have some sort of means for preventing the radioactive contamination of the surrounding area should any mishaps occur during the packaging process. Finally, such a system should be capable of determining whether or not any liquids are present in the waste. SUMMARY OF THE INVENTION In its broadest sense, the invention is a nuclear waste packaging facility for receiving both contact-handled and remote-handled nuclear waste in shipping containers, and encapsulating the waste into modules. The facility includes a first shielded section for processing remote handled waste by remotely-controlled means, and a second, separately shielded section for processing contact handled waste. The facility further includes a module transporation and loading section disposed between the first and second sections for placing empty module containers in a loading position adjacent to each section. Separation of the facility into two separately shielded sections for processing contact and remote handled waste allows the facility to safely package waste of widely varying radioactivity with a minimum of expensive, remote-controlled handling equipment. Additionally, the use of a common module transportation and loading section for both the contact and remote handled sections economizes on the amount of machinery needed to encapsulate the various waste into permanent forms for burial. Both the first and second sections of the facility may each include its own characterization station. Each of these stations may include various radiation and ultrasonic detectors for determining the radioactive level of the waste, and whether or not any of the waste is in liquid form, respectively. Additionally, the outputs of these radiation and ultrasonic etectors may be connected to a computer, which is capable of generating a signal indicative of the number of waste containers which can be loaded into a partiuclar module container before the surface radiation of the completed module will exceed a certain, preselected level. The computer may also be programmed to actuate an alarm signal when the ultrasonic detector indicates that at least some of the waste sought to be encapsulated is in liquid form. Finally, both the contact and remote handled waste sections of the facility may include lag wells for temporarily storing waste arriving in broken containers, in illegal liquid forms, as well as separately shielded remedial action areas where such broken containers may be repaired, and where waste in liquid form may be converted into a buriable, solid form. The module loading and transportation section of the facility may include first and second parallel rail assemblies adjacent the remote and contact handled waste sections of the facility, respectively. The module loading and transportation section may include rail carts for transporting the module containers into loading positions adjacent the contact and remote handled waste sections, and the rail assemblies may include inclined beds so that the rail carts may roll into these loading positions by the force of gravity. In order to insulate the contact handled waste section of the facility from exposure to dangerous radiation during the process of loading remote handled waste into the modules, a shield wall may be placed along the transportation and loading section of the facility. Finally, the facility may include a single grouting station with an extendable trough for grouting waste loaded into the module containers from either the contact or remote handled sections of the facility. The use of a common grouting station having an extendable trough complements the overall arrangement of the facility in maximizing the efficiency of the packaging machinery used in the facility. The facility is preferably near a land disposal site in order to minimize the expense of transporting and burying the modules.
	summary
H00006270	summary	BACKGROUND OF THE INVENTION Although the tokamak is the leading magnetic fusion approach worldwide, its design embodiment and associated physics have not been attractive to the potential commercial users of magnetic fusion. Serious design concept development for a device to carry out ignition and burn physics and/or fusion engineering development in magnetic fusion has been in progress for several years. Prominent concepts and associated reference material include the following: Engineering Test Facility (ETF), ETF Design Center Team, Engineering Test Facility Mission Statement Document, ORNL/TM-6733, Oak Ridge National Laboratory (1980); International Tokamak Reactor (INTOR), INTOR Group, Nuclear Fusion 23, 1513 (1983); Fusion Engineering Device (FED), Fusion Engineering Device Design Description, ORNL/TM-7948, Oak Ridge National Laboratory (1981); and the Toroidal Fusion Core Experiment (TFCX), "The Toroidal Fusion Core Experiment (TFCX) Studies", paper IAEA-CN-44/H-I-3, presented at the Tenth International Conference on Plasma Physics and Controlled Nuclear Fusion Research, London, England, Sept. 12-19 (1984). The estimated, direct total cost of each of these systems is about $1 billion or more with perceived high risk in achieving the stated performance goals. Thus, continued progress of fusion can be enhanced if a design can be found which provides a more favorable cost risk-to-benefit ratio (i.e., an embodiment with small unit size and limited risk in reaching adequate plasma and fusion engineering performance). Major factors that contribute to the larger size and higher cost of the aforementioned design studies can be traced to a combination of physics assumptions, engineering criteria, nnd conventional tokamak wisdom. The conventional wisdom of tokamak operation and prudent engineering suggests the inclusion of a solenoid for inductive current drive, nuclear shields inboard of the plasma torus for protection of inboard coils and insulators, and a separate first wall and vacuum boundary. These items tend to increase the major radius of the torus and aspect ratio (major radius divided by the minor radius of the torus), which, in turn, leads to modest values of average beta (the plasma pressure divided by the magnetic field pressure containing the plasma, typically up to about 5% for aspect ratios of about 3). In the physics area, the assumed plasma energy confinement efficiency at reactor conditions leads to large plasma major and minor radii (about 3 meters or more and 1 meter or so, respectively) and plasma current of 6 to 12 megamperes (MA) when intermediate values of magnetic field between 4 and 6 tesla (T) are employed. For ignition devices with significant burn, a typical design has about 100 cubic meters in plasma volume, 100 megajoules (MJ) in plasma thermal energy content, and produces about 200 megawatts (MW) of deuterium-tritium (D-T) fusion power. The latest cost estimate of such a device using copper toroidal field (TF) coils is about $1 billion. Therefore, it is readily apparent that there is a need for a fusion device with small unit size, and limited risk in reaching adequate plasma and engineering performance. SUMMARY OF THE INVENTION In view of the above need it is an object of this invention to provide a compact toroidal-type fusion reactor with an improved cost risk-to-benefit ratio. Another object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Yet another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained. The result is a plasma confinement region having an aspect ratio (A) of less than 2, a beta of greater than 20%, high plasma current and low magnetic field less than 3T) which produces a highly stable toroidal-type plasma with natural elongation resembling a sphere with a modest hole through the center, suggesting the name of spherical torus. A typical example of ignition and burn spherical torus made in accordance with this invention may have a magnetic field strength of 2T at the plasma center has a major radius of 1.5 m, a minor radius of 1.0 m, a plasma current of 14 MA, a fusion power of 50 MW, an average beta of 24%, and a plasma thermal energy content of 30 MJ.
050911449	claims	1. In the operation of a nuclear reactor system, said system including a containment defining a drywall space wherein a nuclear reactor is disposed, there being a suppression pool in the containment with the suppression pool having a wetwell space above a level of said pool to which any non-condensable gases entering the suppression pool can vent, the method of continuously ventilating the containment comprising continuously exhausting the wetwell space to remove gas mixture therefrom while admitting inflow of air from an atmospheric source thereof to said wetwell during normal operation but blocking off said inflow during a loss-of-coolant-accident whenever a pressure in the wetwell space is above a predetermined value, and subjecting the gas subsequent to its removal from the wetwell to a treatment operation to separate any particulate material entrained therein from the gas mixture. a nuclear reactor which includes a reactor pressure vessel, and a reactor core situated in said pressure vessel, means enclosing space defining a containment in which the nuclear reactor is disposed, the containment including a drywell space, structure in said containment for holding a suppression pool of water and defining a wetwell space above a level of said water, with the wetwell space separated from the drywell space, means for maintaining a continuous exhaust flow of gas mixture from said wetwell space to remove gas mixture therefrom, means for continuously admitting air from an atmospheric source thereof to said wetwell space during normal operation but such means being operable to block air admission to the wetwell space during a loss-of-coolant-accident whenever a pressure in the wetwell is above a predetermined value, conduit means communicating at an entry end thereof with said wetwell space and extending to an opposite outlet end thereof located exteriorly remote from said containment and elevated above the containment, and gas treatment means disposed in said conduit means for treating the gas to separate any particulate matter entrained therein from said gas. a nuclear reactor having a reactor pressure vessel, and a reactor core in the vessel, a turbine unit, a condenser receiving an exhaust of steam from the turbine unit and converting it to a condensate, means for feeding a flow of condensate to the reactor vessel, all said operating components being disposed in a common containment drywell space defined by an enclosure structure, the enclosure structure including a structure part comprising a suppression pool housing separated from the drywell space, said housing containing a pool of water, there being a wetwell space in said housing above a level of the water pool, means defining a flow connection between said drywell space and a submerged location in said water pool, means for maintaining a continuous exhaust flow of gas mixture from the wetwell space to remove gas mixture therefrom, means for continuously admitting atmospheric air from a source thereof to said wetwell space during normal operation but such means being operable to block air admission to the wetwell space during a loss-of-coolant-accident whenever pressure in the wetwell space is above a predetermined value, conduit means communicating at an entry end thereof with the wetwell space and extending to an outlet end located exteriorly of the containment, and gas treatment means disposed in said conduit means for treating the gas to separate any particulate matter entrained therein from the gas. 2. The method of claim 1 in which the gas treatment operation comprises passing the gas mixture through a gravel bed. 3. The method of claim 2 in which the gravel is pebble size. 4. The method of claim 1 in which the gas treatment operation comprises passing the gas mixture through a particulate form of one of zeolite and synthetic zeolite. 5. The method of claim 1 in which the gas treatment operation comprises passing the gas through a foraminous member wetted with a fission particle absorbing solution. 6. The method of claim 5 in which the solution is sodium thiosulfate. 7. The method of claim 1 in which the gas treatment operation includes an additional treatment step of passing the gas through a charcoal mass to adsorb therewith any noble gases as may be present in the gas mixture. 8. The method of claim 7 in which the charcoal mass is maintained at a low temperature. 9. The method of claim 1 in which the gas removed from the wetwell is directed upwardly of the containment in a confined gas velocity enhancing flow course having an outlet to atmosphere substantially elevated above the containment. 10. The method of claim 9 in which exhausting of gas from the wetwell is a forced draft-induced flow. 11. The method of claim 9 in which exhausting of gas from the wetwell is a natural draft-induced flow. 12. The method of claim 11 in which thermal energy is supplied to the gas flow at least one location along said flow course to provide draft assist to said flow. 13. The method of claim 1 in which gas is exhausted from to the wetwell at rates which are effective to control pressure in the drywell upon happening of a loss-of-coolant event in the nuclear reactor to not exceed about one atmosphere gauge pressure. 14. In a nuclear system comprising 15. The nuclear system of claim 14 in which the gas treatment means comprises a filter unit containing a gravel bed through which the gas passes. 16. The nuclear system of claim 15 in which the gravel in bed thereof is of pebble size. 17. The nuclear system of claim 14 in which the gas treatment means comprises a filter unit containing a particulate form of one of zeolite or synthetic zeolite. 18. The nuclear system of claim 14 in which the gas treatment means comprises a mesh number through which the gas passes, and means for continuously wetting the mesh with a fission particle absorbing solution. 19. The nuclear system of claim 14 further comprising additional gas treatment means disposed in said conduit means downstream of said first gas treatment means for adsorbing any noble gas as may be present in the gas mixture. 20. The nuclear system of claim 19 in which said additional gas mixture treatment means comprises a charcoal mass. 21. The nuclear system of claim 20 further comprising means for maintaining said charcoal mass at or near cryogenic temperature. 22. The nuclear system of claim 21 in which said cryogenic temperature maintaining means comprises a source of liquified cryogenic gas, and means operable upon occurrence of a predetermined event for passing said liquified cryogenic gas through said charcoal mass in heat exchange relationship therewith. 23. The nuclear system of claim 14 in which the drywell space includes a lower space region, the suppression pool structure including a pool wall encircling said lower space region, a vent duct member disposed in said lower space region and with the pool wall defining an annular venting channel for establishing the flow path by which flow of any heated fluids present in the drywell incident a loss-of-coolant-accident can pass from the drywell into the pool of water, there being openings in the pool wall below the pool water level communicating the pool with the venting channel. 24. The nuclear system of claim 23 in which at least a portion of the reactor pressure vessel is disposed in said lower space region, said vent duct member encircling said pressure vessel portion. 25. The nuclear system of claim 23 further comprising and disposed within said containment, a steam turbine unit, a steam condenser for receiving steam exhaust from the turbine unit, and feedwater means for conveying a condensate of said steam exhaust to said pressure vessel. 26. The nuclear system of claim 14 in which a terminal section of said conduit means comprises a venting stack. 27. The nuclear system of claim 26 in which the wetwell exhaust flow maintenance means comprises a forced draft fan unit disposed in said conduit means, the atmospheric air admitting means comprising inlets in said suppression pool structure. 28. The nuclear system of 26 further comprising a torch unit disposed in said stack and operable to burn a fuel thereby to release thermal energy in the stack for providing draft assist to gas flowing from the wetwell. 29. The nuclear system of claim 27 in which said conduit means is sized such that flow therethrough is at a rate sufficient to control pressure in the drywell upon happening of a loss-of-coolant accident to not exceed about one atmosphere gauge pressure. 30. A nuclear system comprising an array of operating components including, 31. The nuclear system of claim 30 in which said housing is of elongated but narrowed lateral expanse, the means for admitting atmospheric air to the wetwell comprising an inlet vent means disposed at an end of the housing, the conduit means entry end having communication with the wetwell space at an opposite end of the housing, whereby whenever said inlet valve means is admitting air to the wetwell space, the ventilating flow in the wetwell space sweeps that space from end-to-end thereof. 32. The nuclear system of claim 31 further comprising forced draft flow imposing means disposed in said conduit means. 33. The nuclear system of claim 27 further comprising an conduit bypass leg extending in flow course bypass of the forced draft fan to therewith bypass gas flow through the fan during a loss-of-coolant-accident whenever the pressure in the wetwell space exceeds a predetermined value. 34. The nuclear space of claim 33 further comprising a normally closed pre-loaded check valve disposed in said bypass leg, said valve operable to open responsive to pressure in said wetwell space in excess of said predetermined value.
	summary
	claims	1. A radiation delivery device comprising:a rotatable source component including a plurality of radiation sources;a rotatable collimator component comprising a primary collimator body for directing radiation from the radiation sources to a common focal area; anda shielding body, wherein the rotatable source component is positioned within an inner diameter of the primary collimator body, the rotatable source component rotatable independent of the primary collimator body. 2. The radiation delivery device of claim 1, wherein the primary collimator body comprises one or more sets of primary collimator passages for directing the radiation from the radiation sources. 3. The radiation delivery device of claim 2, wherein the rotatable collimator component further comprises at least one additional rotatable collimator body including one or more sets of additional collimator passages for directing the radiation from the radiation sources. 4. The radiation delivery device of claim 3, wherein the additional collimator passages are different than the primary collimator passages in shape and/or size. 5. The radiation delivery device of claim 3, wherein the primary collimator body is arranged within an interior cavity of the additional rotatable collimator body. 6. The radiation delivery device of claim 5, wherein sets of additional collimator passages are arranged at differing radial positions on the additional rotatable collimator body. 7. The radiation delivery device of claim 6, wherein the additional collimator passages arranged at differing radial positions have different shape and/or size. 8. The radiation delivery device of claim 5, wherein the rotatable source component exhibits a non-concentric arrangement with the primary collimator body and/or additional rotatable collimator body. 9. The radiation delivery device of claim 1, wherein the common focal area has a diameter or width of 2 mm to 60 mm. 10. The radiation delivery device of claim 1, wherein the radiation sources are arranged along a curved surface extending along the rotatable source component longitudinal axis. 11. The radiation delivery device of claim 1, wherein the radiation sources comprise radioactive material. 12. The radiation delivery device of claim 11, wherein the radioactive material is selected from the group consisting of cobalt-60, cesium-137 and iridium-192. 13. The radiation delivery device of claim 2, wherein the primary collimator body does not exhibit curvature in a region of the primary collimator passages. 14. The radiation delivery device of claim 3, wherein the one or more sets of additional collimator passages are unequal in number to the primary collimator passages. 15. A method of directing radiation from a plurality of radiation sources to a common focal area comprising:positioning a rotatable source component comprising the radiation sources within an inner diameter of a primary collimator body of a rotatable collimator component, the rotatable source component rotatable independent of the primary collimator body;rotating the rotatable source component from a position of the radiation sources facing a shielding body to a position of the radiation sources facing passages of the primary collimator body; anddirecting the radiation to the common focal area with the primary collimator body. 16. The method of claim 15, wherein the primary collimator body comprises one or more sets of primary collimator passages for directing the radiation. 17. The method of claim 16, wherein the rotatable collimator component further comprises at least one additional rotatable collimator body including one or more sets of additional collimator passages for directing the radiation to the common focal point. 18. The method of claim 17, wherein the additional collimator passages are different than the primary collimator passages in size and/or shape. 19. The method of claim 17, wherein the additional collimator passages differ in number from the primary collimator passages. 20. The method of claim 17, wherein the primary collimator body is arranged within an inner diameter of the additional rotatable collimator body. 21. The method of claim 20, wherein the rotatable source component, primary collimator body and/or additional rotatable collimator body are rotated to align the primary collimator passages and additional collimator passages with the radiation sources. 22. The method of claim 15, wherein the common focal area is located within a patient's body. 23. The method of claim 16, wherein the primary collimator body does not exhibit curvature in a region of the primary collimator passages. 24. The method of claim 17, wherein the one or more sets of additional collimator passages are unequal in number to the primary collimator passages. 25. The method of claim 24, wherein radiation dosage to the common focal area is varied by the unequal number of collimator passages in the one or more additional sets.
	claims	1. Process for the preparation of a product comprising a phosphate of at least one element M(IV) chosen from thorium(IV) and actinide(IV)s, wherein it comprises the following stages:a) mixing a solution comprising thorium(IV) and/or at least one actinide(IV) with a phosphoric acid solution in amounts such that the molar ratio PO 4 M ⁢ ⁢ ( IV ) where M(IV) represents the total concentration of thorium(IV) and/or actinide(IV)s, is from 1.4 to 2,b) heating the mixture of the solutions in a closed container at a temperature of 50 to 250° C. to precipitate a product comprising a phosphate of at least one element M chosen from thorium(IV) and actinide(IV)s having a P/M molar ratio of 1.5, andc) separating the precipitated product from the solution. 2. Process according to claim 1, which additionally comprises the following stages:d) washing with water the precipitated product thus separated, ande) drying the washed product. 3. Process according to claim 1, in which the thorium solution is a solution of ThCl4 in hydrochloric acid. 4. Process according to claim 1, in which the actinide is uranium(IV) and the uranium(IV) solution is a solution of UCl4 in hydrochloric acid. 5. Process according to claim 1, in which the actinide is neptunium(IV) and the neptunium(IV) solution is a solution of neptunium in nitric acid. 6. Process according to claim 1, in which the actinide is plutonium(IV) and the plutonium(IV) solution is a solution of plutonium in nitric acid. 7. Process according to claim 1, in which, in stage a), at least one element chosen from trivalent actinides and trivalent lanthanides is additionally added to the mixture in order to include trivalent actinide(s) and/or trivalent lanthanide(s) in the product precipitated in stage b). 8. Process for the preparation of thorium phosphate/diphosphate of formula Th4(PO4)4P2O7, wherein a product based on thorium(IV) phosphate is prepared by carrying out the process according to claim 1 using, in stage a), a solution comprising thorium and phosphoric acid and wherein the product based on thorium(IV) phosphate is subjected to a heat treatment carried out at least partially at a temperature of 700° C. to 1300° C. 9. Process according to claim 8, in which the heat treatment is carried out in two stages which are respectively a first stage carried out at a temperature of 300 to 500° C. for 1 h to 5 hours and a second stage carried out at a temperature of 1100 to 1300° C. for 3 to 15 h. 10. Process for the preparation of uranium phosphate, wherein a product based on uranium(IV) phosphate is prepared by carrying out the process according to claim 1 using, in stage a), a solution comprising uranium and phosphoric acid and wherein the product based on uranium(IV) phosphate is subjected to a heat treatment carried out at least partially at a temperature of 700° C. to 1300° C. 11. Process according to claim 10, in which the heat treatment is carried out in two stages which are respectively a first stage carried out at a temperature of 300 to 500° C. for 1 h to 5 hours and a second stage carried out at a temperature of 1100 to 1300° C. for 3 to 15 h. 12. Process for the preparation of a solid solution of phosphates of thorium and of at least one tetravalent actinide, wherein a product comprising phosphates of Th and of at least one tetravalent actinide is prepared by carrying out the process according to claim 1 using, in stage a), a solution comprising thorium and at least one actinide and phosphoric acid and wherein the product based on phosphates of thorium(IV) and of actinide(IV) is subjected to a heat treatment carried out at least partially at a temperature of 700° C. to 1300° C. 13. Process according to claim 12, in which the solid solution of phosphates corresponds to the formula:Th4-xMx(PO4)4P2O7in which M is an element chosen from Pa(IV), U(IV), Np(IV) and Pu(IV), and x satisfies the following conditions:x≦3.75 for Pa(IV)x≦3 for U(IV)x≦2.14 for Np(IV)x≦1.67 for Pu(IV). 14. Process according to claim 12, in which the heat treatment is carried out in two stages which are respectively a first stage carried out at a temperature of 300 to 500° C. for 1 h to 5 hours and a second stage carried out at a temperature of 1100 to 1300° C. for 3 to 15 h. 15. Process for the preparation of a composite material including at least one actinide(III) and/or at least one lanthanide(III), wherein the precipitate comprising a phosphate of Th(IV) and/or of actinide(IV)(s) is prepared by carrying out the process according to claim 1 and wherein a powder comprising at least one actinide(III) and/or at least one lanthanide(III) in the phosphate form is dispersed in the precipitate and wherein the combination is subsequently subjected to a heat treatment, optionally preceded by a compacting, carried out at least partially at a temperature of 700 to 1300° C. 16. Process for the separation of uranium(VI), in the form of the uranyl ion UO22+, present in a solution with other cations, including thorium, wherein phosphoric acid is added to the solution in an amount such that the molar ratio phosphoric ⁢ ⁢ acid other ⁢ ⁢ cations is from 1.4 to 2, wherein the solution thus obtained is heated at a temperature of 50 to 250° C. in a closed container, in order to precipitate a product comprising the cations other than uranium, and wherein the solution comprising uranium(VI) is recovered. 17. Process for the decontamination of radioactive aqueous effluent comprising contaminating radioactive cations, the process comprising:adding thorium and then phosphoric acid to the effluent in amounts such that the P/Th molar ratio is from 1.4 to 2;heating the effluent in a closed container at a temperature of 50 to 250° C.; andprecipitating a product from the effluent comprising thorium phosphate and entrained contaminating radioactive cations.
	abstract	The present disclosure provides a collimating body and a multi-source focusing radiation therapy head. The collimating body includes a first collimating portion and a second collimating portion. The first collimating portion and the second collimating portion are arranged side by side and closely fixed. The first collimating portion includes a first collimating hole set, and the second collimating portion includes a second collimating hole set. The first collimating portion and the second collimating portion are able to move oppositely in a direction perpendicular to a side-by-side direction, so as to align or stagger the first collimating hole set and the second collimating hole set.
046876170	claims	1. A steady-state method of maintaining an inductively formed spheromak plasma comprising the steps of: (a) inductively producing a spheromak plasma by: evacuating a vacuum vessel and filling said vessel with a neutral species; producing a first poloidal magnetic field within said vacuum vessel; producing a second poloidal magnetic field within said vacuum vessel by pulsing a current I.sub.pf in a first direction through a poloidal field generating coil, the poloidal field generating coil being located in a toroidally shaped flux core within the vacuum vessel, such that the first and second poloidal magnetic fields are superimposed to form a composite poloidal magnetic field .psi. within said vacuum vessel having regions of stronger and weaker strength; producing a toroidal magnetic field .PHI. in said vacuum vessel by passing a current I.sub.TF through a toroidal field generating coil which is located in the flux core, thereby initiating a plasma discharge and causing toroidal flux to appear outside of the flux core; expanding the plasma in the direction of said region of weaker poloidal magnetic field strength; (b) forming a linked toroidal spheromak plasma from said expanded plasma in which some flux surfaces of said spheromak plasma link both the plasma and the core; and (c) oscillating the poloidal and toroidal magnetic fields .psi. and .PHI., while said plasma flux surfaces are linked to both the plasma and the core, such that .psi. and .PHI. have different phases. (d) completely pinching off a portion of said expanded plasma from said flux core, said completely pinched off plasma forming a detached toroidal spheromak plasma and; (e) reconnecting the flux surfaces said spheromak plasma to said flux core such that some magnetic flux links both the plasma and the core such that a linked spheromak plasma is formed. (a) inductively producing a spheromak plasma by: evacuating a vacuum vessel and filling said vessel with a neutral species; producing a first poloidal magnetic field within said vacuum vessel; producing a second poloidal magnetic field within said vacuum vessel by pulsing a current I.sub.PF in a first direction through a poloidal field generating coil being located in a toroidally shaped flux core within the vacuum vessel, such that the first and second poloidal magnetic fields are superimposed to form a composite poloidal magnetic field within said vacuum vessel having regions of stronger and weaker strength; producing a toroidal magnetic field .PHI. in said vacuum vessel by passing a current I.sub.TF through a toroidal field generating coil which is located in the flux core, thereby initiating a plasma discharge and causing toroidal flux to appear outside of the flux core; expanding the plasma in the direction of said region of weaker poloidal magnetic field strength; completely pinching off a portion of said expanded plasma from said flux core, said completely pinched off plasma portion forming a detatched toroidal spheromak plasma, by setting I.sub.PF .ltoreq.0; (b) setting I.sub.TF =0; (c) reconnecting the flux surfaces said spheromak plasma to said flux core, such that some magnetic flux links both the plasma and the core, by increasing I.sub.PF while I.sub.TF =0; (d) injecting toroidal flux into said reconnected plasma by setting I.sub.TF >0; and (e) oscillating .psi. and .PHI. such that .psi. and .PHI. have different phases. 2. The method of claim 1 wherein .psi. and .phi. are oscillated according to the relationship: EQU .psi.=.psi..sub.0 +.psi..sub.1 cos .omega.t 3. The method of claim 2 where .delta.=-.pi./2. 4. The method of claim 1 wherein said linked spheromak plasma is formed by: 5. The method of claim 4 wherein step (d) is accomplished by letting I.sub.PF .ltoreq.0. 6. The method of claim 5 wherein step (e) is accomplished by letting I.sub.PF >0, with I.sub.TF =0. 7. A quasi-steady-state method of maintaining an inductively formed plasma comprising the steps of: 8. The method of claim 1 wherein said plasma is pinched off by energizing a set of pinching coils located near the flux core. 9. The method of claim 1 wherein said plasma is pinched off by simultaneously reversing the directions of I.sub.PF and I.sub.TF. 10. The method of claim 1 wherein said linked spheromak plasma is formed by pinching off a portion of said expanded plasma such that some flux surfaces of said spheromak plasma remain connected to the core.
	claims	1. A method of implanting particles into a workpiece, the method comprising:forming a beam of charged particles;adjusting a longitudinal spacing between the charged particles along the beam; anddirecting the beam towards the workpiece in a pattern in an exposure chamber. 2. The method of claim 1, wherein a dosage of the beam is less than about 5×1017 charged particles/cm2. 3. The method of claim 1, wherein a dosage of the beam is less than about 5×1010 charged particles/cm2. 4. The method of claim 1, wherein the workpiece is resistless while directing the beam. 5. The method of claim 1, further comprising, during directing the beam, exposing a surface of the workpiece to a reactant. 6. The method of claim 1, further comprising annealing the implanted particles. 7. The method of claim 1, wherein forming the beam comprises:forming a stream of the particles;collimating the stream along an axis of propagation; anddigitizing the stream. 8. The method of claim 1, wherein forming the beam comprises creating temporally and spatially resolved digital flashes comprising at least one particle per digital flash. 9. The method of claim 1, wherein directing the beam comprises:deflecting the beam using a series of deflection stages disposed longitudinally along an axis of propagation of the beam; anddemagnifying the beam. 10. A workpiece manufactured by the method of claim 1. 11. A method of implanting at least one dopant into a workpiece, the method comprising:forming a beam comprising a series of particles of at least one ion species;directing the beam towards the workpiece; andduring directing, altering at least one parameter of the spacing of the particles in the beam. 12. The method of claim 11, wherein the parameter comprises ion species. 13. The method of claim 11, wherein the parameter comprises beam energy. 14. The method of claim 13, wherein altering the beam energy comprises varying the beam energy between about 5 and 500 keV. 15. The method of claim 11, wherein the parameter comprises a density of particles in the beam. 16. The method of claim 11, wherein altering the parameter is during directing the beam across a transistor on the workpiece. 17. The method of claim 11, wherein altering the parameter is during directing the beam across a die on the workpiece. 18. The method of claim 11, wherein forming the beam comprises forming a digital beam. 19. A workpiece manufactured by the method of claim 11. 20. A method of processing to implant material into a workpiece, the method comprising:directing a beam comprising charged particles which are spaced along a longitudinal direction of the beam onto the workpiece in a pattern in an exposure chamber, such that charged particles of the beam are sequentially directed to different positions on the workpiece.
	abstract	Illustrative embodiments provide for the operation and simulation of the operation of fission reactors, including the movement of materials within reactors. Illustrative embodiments and aspects include, without limitation, nuclear fission reactors and reactor modules, including modular nuclear fission reactors and reactor modules, nuclear fission deflagration wave reactors and reactor modules, modular nuclear fission deflagration wave reactors and modules, methods of operating nuclear reactors and modules including the aforementioned, methods of simulating operating nuclear reactors and modules including the aforementioned, and the like.
	description	The present disclosure relates generally to radiology and, more particularly to, a radiation protection barrier. Medical practitioners, involved in radiology such as fluoroscopy, interventional cardiology, interventional radiology, and neurointerventional radiology, may use x-ray imaging for various procedures. In such procedures, typically the medical practitioners wear lead or lead equivalent aprons for protecting themselves from prolonged exposure to X-rays. Typically, such aprons weigh fifteen pounds or more. Therefore, regular and prolonged use of such aprons can create fatigue, pain, and can even lead to chronic physical ailments such as back, spine, and shoulder pain. One solution is to make the aprons lighter by using thinner layers of radiation protecting material (such as lead or lead equivalent material), but such change in density and/or atomic structure can affect the protection level offered by such aprons. Additionally, there are ceiling hanging lead or lead-equivalent aprons, but such hanging aprons can cater to only a single person and other medical practitioners involved in the radiology procedure would still need to wear conventional lead aprons. Maintaining sterility is an issue for any apparatus requiring physicians to reach through lead slits to perform a procedure on a patient. In light of the foregoing discussion, there exists a need to overcome the aforementioned drawbacks associated with the use of lead aprons and devices used in radiology procedures. Various embodiments of the present disclosure provide a radiation protection barrier that can be used in conjunction with radiology procedures. In an embodiment, a radiation protection barrier is disclosed. The radiation protection barrier includes at least one plain panel, each including an elongate frame, and a protective sheet attached to the elongate frame. The radiation protection barrier also includes at least one interventional panel coupled to at least one plain panel, each of at least one interventional panel includes an elongate frame, a protective sheet movably arranged on the elongate frame, a pair of sterile gloves arranged at an intermediate portion of the protective sheet, and a window configured on the protective sheet under the pair of sterile gloves. The radiation protection barrier further includes a plurality of wheel arrangements coupled to the elongate frames of at least one plain and interventional panels. In another embodiment, a radiation protection barrier is disclosed, which includes a plain panel, having an elongate frame and a protective sheet attached to the elongate frame. The radiation protection barrier also includes an interventional panel coupled to the plain panel, the interventional panel includes an elongate frame, a protective sheet movably arranged on the elongate frame, a pair of sterile gloves arranged at an intermediate portion of the protective sheet, and a window configured on the protective sheet under the pair of sterile gloves. The radiation protection barrier further includes a plurality of wheel arrangements coupled to the elongate frames of the plain and interventional panels. In another embodiment, a radiation protection barrier is disclosed, which includes an interventional panel having an elongate frame, a protective sheet movably arranged on the elongate frame, a pair of sterile gloves arranged at an intermediate portion of the protective sheet, and a window configured on the protective sheet under the pair of sterile gloves. The radiation protection barrier also includes a plurality of wheel arrangements coupled to the elongate frame of the interventional panel. Other aspects and example embodiments are provided in the drawings and the detailed description that follows. The drawings referred to in this description are not to be understood as being drawn to scale except if specifically noted, and such drawings are only exemplary in nature. In the following description, for purposes of explanation, numerous specific details are set forth in order to provide a thorough understanding of the present disclosure. It will be apparent, however, to one skilled in the art that the present disclosure can be practiced without these specific details. Reference in this specification to “one embodiment” or “an embodiment” means that a particular feature, structure, or characteristic described in connection with the embodiment is included in at least one embodiment of the present disclosure. The appearance of the phrase “in an embodiment” in various places in the specification is not necessarily all referring to the same embodiment, nor are separate or alternative embodiments mutually exclusive of other embodiments. Moreover, various features are described which may be exhibited by some embodiments and not by others. Similarly, various requirements are described which may be requirements for some embodiments, but not for other embodiments. Moreover, although the following description contains many specifics for the purposes of illustration, anyone skilled in the art will appreciate that many variations and/or alterations to said details are within the scope of the present disclosure. Similarly, although many of the features of the present disclosure are described in terms of each other, or in conjunction with each other, one skilled in the art will appreciate that many of these features can be provided independently of other features. Accordingly, this description of the present disclosure is set forth without any loss of generality to, and without imposing limitations upon, the present disclosure. Referring now to the drawings, FIG. 1 is a perspective view of a radiation protection barrier 100, in accordance with an embodiment of the present disclosure. As shown, the radiation protection barrier 100 includes at least one plain panel, such as a plain panel 102. In the present embodiment, the radiation protection barrier 100 is shown to include a single plain panel 102, however, it will be evident to those skilled in the art that the radiation protection barrier 100 may include more than one plain panel, such as two or three plain panels. The plain panel 102 includes an elongate frame 104. In an embodiment, the elongate frame 104 is a rectangular frame made of four frame members coupled to each other. The frame members may be made of material, such as metal, plastic or any combination thereof. In an embodiment, the frame members may be made of protective material, such as lead or lead-equivalent material, explained in greater detail herein later. Further, the frame members may be hollow or solid rods coupled to each other to form the elongate frame 104. It will be evident that, a height of the elongate frame 104 would correspond to a height that is necessary to shield a medical practitioner from radiation when standing behind the radiation protection barrier 100. In an example, the elongate frame 104 may include such a length that the plain panel 102 from a ground surface offers a height of a couple of feet, such as 4 feet to 7 feet. In an example, the plain panel 102 may be configured to have a height of 6 feet. In an embodiment, the elongate frame 104 may be configured to have a fixed length to offer a non-adjustable height to the plain panel 102. Alternatively, the elongate frame 104 may be configured to have a variable length to offer adjustable height to the plain panel 102. For example, the elongate frame 104 may be configured to have a telescopic arrangement or configuration, which allows adjustable height for the plain panel 102. The plain panel 102 includes a protective sheet 106 attached to the elongate frame 104. The term “protective sheet” used herein refers to a protective layer adapted to provide protection against radiation. The protective sheet 106 can be an integral part of the elongate frame 104, attached to the elongate frame 104, or slide into the elongate frame 104. For sterility, a sterile drape is attached across the panels with sticky strips or some other temporary manner. If the elongate frame is separate rather than an integral part of the protective sheet, the elongate frame must be long enough to support the weight of the protective sheet. In an embodiment, the protective sheet 106 is impregnated with a protective material or contains a layer of protective material. For example, the protective sheet 106 includes (or is made solely of) a layer of protective material or made of a clear material that is impregnated with the protective material. According to an embodiment, the layer of protective material is composed of a material selected from a group consisting of Lead, Erbium, Holmium, Dysprosium, Terbium, Gadolinium, Europium, Samarium, Tantalum, Hafnium, Lutetium, Ytterbium, Thulium, Thorium, Uranium or any combination thereof. In an example, the layer of protective material includes lead or lead-equivalent material, i.e. the protective sheet 106 is solely made of lead or lead-equivalent material. Alternatively, the protective sheet 106 may be made of a clear material impregnated with the protective material, i.e. the protective sheet 106 may be made of a clear acrylic material impregnated with lead or lead-equivalent material. According to an embodiment, the clear nature of the protective sheet 106 enables the medical practitioner to look therethrough while performing any task associated with a radiology procedure. In an alternative embodiment, with the implementation of virtual reality operating systems, which is becoming more widely available nowadays, it may not be necessary for the protective sheet 106 to be clear for allowing the medical practitioner to look therethrough. Thus, the clear nature of the protective sheet 106 is optional, and the protective sheet 106 may be configured to be unclear, i.e. when made solely of a layer of protective material. Further, in an embodiment, the layer of protective material may include sufficient thickness that enables the protective sheet 106 to block the X-rays to pass therethrough, thereby providing radiation protection. In an example, the layer of protective material may include a thickness in a range of 2 to 5 millimeters. According to an embodiment, temporary sterile fabric attaches to the lower half of the protective sheet 106 to provide sterility during the procedure. The sterile fabric may include cotton or synthetic fabric. In an embodiment, the sterile fabric can be stick-on fabric adapted to be peelably coupled to the protective sheet 106. The radiation protection barrier 100 also includes at least one interventional panel, such as interventional panels 110. As shown in FIG. 1, in the present embodiment, the radiation protection barrier 100 includes two interventional panels 110. However, it may be evident to those skilled in the art that the radiation protection barrier 100 may include a single interventional panel (instead of the two interventional panels 110) or more than two interventional panels, such as three interventional panels. The interventional panels 110 are coupled to at least one plain panel, i.e. the plain panel 102. As shown, the two interventional panels 110 are laterally coupled to each other, and one of the two interventional panels 110 is further laterally coupled to the plain panel 102, which is explained in greater detail herein later. Each of the two interventional panels 110 includes an elongate frame, such as elongate frame 112. The elongate frame 112 of the interventional panels 110 is structurally and functionally similar to the elongate frame 104 of the plain panel 102, explained herein above. For example, the elongate frame 112 is also a rectangular frame, which may be made of metal or plastic rods or protective material, and the rods may be solid or hollow. Further, a height of the elongate frame 112 would correspond to a height of the elongate frame 104. Moreover, the elongate frame 112 may be configured to have either a non-adjustable height or adjustable heights (i.e. telescopic configuration). Each of the interventional panels 110 includes a protective sheet 114. The protective sheet 114 is impregnated with a protective material or contains a layer of a protective material. The protective sheet 114 is substantially similar to the protective sheet 106 of the plain panel 102. For example, the protective sheet 114 also includes a rectangular shape and dimensions, for example, a length and a width conforming to a length and a width of the elongate frame 112. In an embodiment, the protective sheet 114 is solely made of a layer of protective material, as explained herein above in conjunction with the plain panel 102. Alternatively, the protective sheet 114 may be made of a clear material impregnated with the protective material, i.e. made of a clear acrylic material impregnated with lead or lead-equivalent material. Additionally, according to an embodiment, a sterile drape would then be placed across the mid to bottom portion of the protective sheet 114 in order to maintain or provide sterility. The interventional panels 110 are embedded or attached with the protective sheet 114, which is movably arranged on the elongate frame 112. The sterile drape is movably arranged across the interventional panels 110 anteriorly and posteriorly (i.e. from front and behind). According to an embodiment, each of the interventional panels 110 further includes an adjustment mechanism (not shown) for allowing the protective sheet 114 of the interventional panels 110 to move along the elongate frame 112. In an example, the adjustment mechanism may include a shaft and rollers arrangement (or a rack and pinion arrangement, not shown) mounted on the elongate frame 112, and the protective sheet 114 is arranged on the shaft and rollers arrangement in a manner such that the protective sheet 114 can move along the elongate frame 112. Further, the adjustment mechanism may be manually operated or electronically and remotely operated to allow the protective sheet 114 to move along the elongate frame 112. Additionally, it may be evident to those skilled in the art that when the elongate frame 112 is configured to have the adjustable heights (for example, by implementing telescopic arrangement) the interventional panels 110 may not include the adjustment mechanism, as explained herein above. Each of the interventional panels 110 also includes a pair of sterile gloves 116 with customized attachment to the panel, either by a perimeter of adhesive material or by another mechanism, arranged at an intermediate portion 118 (or at a top portion) of the protective sheet 114. The pair of sterile gloves 116 may be detachably coupled to the protective sheet 114 of the interventional panels 110. For example, the protective sheet 114 may include a pair of holes (shown) and proximal ends of the pair of sterile gloves 116 are configured to be detachably attached around the pair of holes, using hook and loop fastener, adhesive and so forth. As shown, the pair of sterile gloves 116 is configured to have a shape and a size that allow a medical practitioner to insert his/her hands into the pair of sterile gloves 116 to perform any task associated with an interventional radiology procedure by standing behind the interventional panels 110. The arm length of the gloves can be customized for optimal comfort when performing the procedure behind the protective sheet. For example, the tasks may include handling interventional devices or equipment and so forth. The sterile nature of the pair of sterile gloves 116 allows the medical practitioner to effectively (i.e. in clean or germ-free manner) perform the interventional radiology procedure while still being shielded from radiation exposure. According to an embodiment, each of the pair of sterile gloves 116 is solely made of or impregnated with radiation protective material, as explained herein above. In an embodiment, each of the pair of sterile lead or lead-equivalent gloves 116 may be made of a pair of spaced apart sterile fabric, such that a layer of radiation protective material is positioned between the pair of spaced apart sterile lead or lead-equivalent fabric, and a removable sterile drape surrounds the holes for the gloves in order to maintain sterility during the procedure, as discussed herein above. In use, height of the pair of sterile gloves 116 from a ground surface can be adjusted using the adjustment mechanism arranged on the elongate frame 112 or with the help of telescopic configuration of the elongate frame 112, as explained herein above. Each of the interventional panels 110 also includes a window 120 configured on the protective sheet 114 under the pair of sterile gloves 116. The window 120 includes a flap 122 for openably closing an opening (not shown) of the window 120. In an example, the window is created by cutting a rectangular hole in the protective sheet 114 and overlaying an oversized lead or lead-equivalent flap anterior or posterior to the window 120. The size of the flap 122 insures a radiation protective seal. A plastic sterile fabric may hug the flap 122 to maintain sterility. The window 120 is configured or arranged below the pair of sterile gloves 116. Therefore, the flap 122 may be solely made of a layer of protective material. A medical practitioner may use the window 120 to perform certain task, associated with the interventional radiology procedure, which may not be done suitably using the pair of sterile gloves 116. In an example, such tasks may include putting interventional devices on the table for the clinicians' use, such as a catheter, wire, stent, etc. According to an embodiment, each of the plain or interventional panels 102, 110 also includes a lead or lead-equivalent roof (not shown) at an oblique angle to shield practitioners behind the radiation protection barrier 100 from scatter radiation. As explained herein above, the two interventional panels 110 are laterally coupled to each other, and one of the two interventional panels 110 is further laterally coupled to the plain panel 102. According to an embodiment, the elongate frames 104, 112 of at least one plain panel, i.e. the plain panel 102, and the interventional panels, i.e. the interventional panels 110, are foldably coupled. The term “foldably coupled” used herein relates to coupling of the elongate frames 104, 112 of the plain panel 102 and the interventional panels 110 such that the plain panel 102 and the interventional panels 110 can be folded to be placed (or positioned) close to each other or in an overlapping state. This may help in storing the radiation protection barrier 100, when not in use, in addition to ensuring radiation protection in smaller workspaces. In an embodiment, the radiation protection barrier 100 includes intermediate protective lead or lead-equivalent strips arranged between the elongate frames to allow foldable coupling therebetween. As shown, the radiation protection barrier 100 includes intermediate protective strips 130 and 132 positioned between the two interventional panels 110, and between the plain panel 102 and one interventional panel 110, respectively. In other words, the intermediate protective strips 130, 132 are arranged (coupled or mounted) between the elongate frames 112, 112 and the elongate frames 104, 112, respectively. The intermediate protective strips 130, 132 include required flexibility to allow foldable coupling between the plain and interventional panels 102, 110. Further, it will be appreciated that the intermediate protective strips 130, 132 are also made of lead or lead-equivalent material. As mentioned herein above, the sterile drapes cross the plain or interventional panels 102, 110; therefore, the sterile drapes also cross the lower half of the intermediate protective strips 130 and 132 to maintain sterility during the procedure. The purpose of the intermediate protective strips 130, 132 is to provide a radiation protective seal for any small air gaps between the plain or interventional panels 102, 110. According to another embodiment, the radiation protection barrier 100 may include hinges (not shown) arranged between the elongate frames to allow foldable coupling therebetween. It will be apparent to those skilled in the art that the elongate frames 104, 112 of the plain and interventional panels 102, 110 may be laterally and directly coupled in a foldable manner using long lead or lead-equivalent hinges. In such instances, the intermediate protective strips 130, 132 may not be arranged between the elongate frames 104, 112. The radiation protection barrier 100 includes a plurality of wheel arrangements 140 coupled to the elongate frame(s) 104, 112 of the plain and interventional panels 102, 110. According to an embodiment, each of the plurality of wheel arrangements 140 includes a wheel support 142 coupled to the elongate frame, such as the elongate frames 104, 112, of the plain and interventional panels 102, 110. As shown, the wheel support 142 may be one of a solid or a hollow rod that is either made of metal or plastic. Further, the wheel support 142 may be fixedly or detachably coupled to the elongate frames 104, 112. Each of the plurality of wheel arrangements 140 also includes a pair of wheels 144 arranged on the wheel support 142. Further, each of the plurality of wheel arrangements 140 includes a stop member 146 arranged on each of the pair of wheels 144. The plurality of wheel arrangements 140 enables the movement of the radiation protection barrier 100 from one place to another, and further allows the plain and interventional panels 102, 110 to move with respect to each other to attain a folded, unfolded, or any specific position. Moreover, the stop member 146 of the plurality of wheel arrangements 140 may be used to break the pair of wheels 144 thereby allowing the radiation protection barrier 100 to have a stationary position with respect to a ground surface. In an embodiment, the radiation protection barrier 100 further includes protective lead or lead-equivalent lower drapes 150 arranged on the elongate frames 104, 112 of the plain and interventional panels 102, 110. As shown, the protective lower drapes 150 are arranged on lower frame members (not shown) of the elongate frames 104, 112. These protective lower drapes 150 are placed at the ankle level, alleviating the need for sterility per standard operating room procedures, since they are below the level of the patient's table. The protective lower drapes 150 protect the feet of the medical practitioners from the exposure of X-rays, while allowing the medical practitioner to comfortably perform the procedure. In an embodiment, the protective lower drapes 150 may be solely made of a layer of protective material. Referring now to FIG. 2, illustrated is a perspective view of a radiation protection barrier 200, in accordance with another embodiment of the present disclosure. As shown, the radiation protection barrier 200 is substantially similar to the radiation protection barrier 100, explained in conjunction with FIG. 1. For example, the radiation protection barrier 200 includes a plain panel 202 and an interventional panel 204 coupled to the plain panel 202. The plain and interventional panels 202, 204 are structurally and functionally similar to the plain and interventional panels 102, 110, respectively, of the radiation protection barrier 100. The radiation protection barrier 200 also includes a plurality of wheel arrangements 206, similar to the plurality of wheel arrangements 140, coupled to elongate frames of the plain and interventional panels 202, 204. It will be apparent to a person skilled in the art that the text explaining the plain and interventional panels 202, 204 and the plurality of wheel arrangements 140 is avoided for the purpose of brevity. Referring now to FIG. 3, illustrated is a perspective view of a radiation protection barrier 300, in accordance with yet another embodiment of the present disclosure. As shown, the radiation protection barrier 300 is substantially similar to the radiation protection barrier 100, explained in conjunction with FIG. 1. For example, the radiation protection barrier 300 also includes an interventional panel 302 (such as the interventional panel 110) and a plurality of wheel arrangements 304 (such as the plurality of wheel arrangements 140) coupled to an elongate frame 306 of the interventional panel 302. The width of the panel may be extended to the dimension necessary to insure radiation safety of the operator and assisting staff at the interventional table. It will be apparent to a person skilled in the art that the text explaining the interventional panel 302 and the plurality of wheel arrangements 304 is avoided for the purpose of brevity. Embodiments of the present disclosure substantially eliminate or at least partially address the aforementioned problems in the background and provide a radiation protection barrier. The radiation protection barrier enables medical practitioners to avoid wearing heavy lead or lead equivalent aprons, thereby avoiding chronic physical ailments such as back, spine, and shoulder pain, which can arise from prolonged use of such heavy aprons. The radiation protection barrier provides the required protection from X-ray radiation, as there is no need to compromise at the structural (i.e. thickness) level of the radiation protecting material that will be used to make the radiation protection barrier. Further, the radiation protection barrier of the present disclosure can be simultaneously used by multiple medical practitioners involved in any radiology procedure. Moreover, the radiation protection barrier is specifically designed for use in sterile settings, which is necessary for performing interventional radiology procedures, such as those related to interventional cardiology, interventional radiology, neurointerventional radiology, and so forth. Further in use, when the medical practitioner removes his/her hands from the sterile lead or lead-equivalent gloves, the medical practitioner will have sterile non-lead gloves underneath, which can be used to collect devices off a sterile table and pass the devices to be applied on a patient's body through the window, while the fluoroscopy machine is in off mode. The radiation protection barrier of the present disclosure creates a radiation free zone for a supporting technician or attendant who can stand at the table preparing devices later applied to the patient. A nurse can comfortably monitor vitals of the patient from behind the radiation protection barrier. Medications can be administered from a long IV line placed behind the radiation protection barrier and outside of the sterile field so that the nurse can maintain his/her position. The embodiments illustrated and described herein as well as embodiments not specifically described herein but within the scope of the aspects of the invention constitute an exemplary radiation protection barrier. The benefits and advantages described above may relate to one embodiment or may relate to several embodiments. The embodiments are not limited to those that solve any or all of the stated problems or those that have any or all of the stated benefits and advantages. Aspects of any of the examples described above may be combined with aspects of any of the other examples described to form further examples without losing the effect sought. The above description is given by way of example only and various modifications may be made by those skilled in the art. The above specification, examples and data provide a complete description of the structure and use of exemplary embodiments. Although various embodiments have been described above with a certain degree of particularity, or with reference to one or more individual embodiments, those skilled in the art could make numerous alterations to the disclosed embodiments without departing from the spirit or scope of this specification.
043022871	abstract	A method for controlling the operation of a nuclear reactor to increase the reactor power in a range in which pellet-clad-mechanical-interaction occurs. The method includes the steps of increasing the reactor power from a power level in which pellet-clad-mechanical-interaction begins to take place up to a predetermined power level for the nuclear reactor and controlling the rate of increase of the linear heat generating rate. The rate of increase is controlled with at least one of a rate no less than 0.15 KW/ft/hr., and a rate no greater than a predetermined critical rate so as to shorten the time necessary to raise the reactor power to the predetermined power level without causing pellet-clad-mechanical-interaction damage to the fuel elements.
040452840	description	A first embodiment of the nuclear reactor fuel containment safety structure of this invention is variously disclosed in FIGS. 1-3 and is generally illustrated by the number 10. This first embodiment 10 includes, generally, a fuel reactor shield 11 (FIG. 1) an exhaust passage means 12, and a deactivating containment base 13. Fuel reactor shield 11 is illustrated as a concrete structure with a fuel containment chamber 15 adapted to contain an atomic reactor 16 with the reactor fuel therefor. Floor 17 of reactor shield 11 can be an integral part of shield 11, as it is illustrated, or in the alternative, floor 17 could be provided, preferably in the central section of shield 11, with a rupture panel 18 which, when subjected to any molten radioactive mass, would be dissolved with the mass or otherwise give way thereto to allow the temperature elevated mass to flow from chamber 15 of shield 11, by passing downwardly through such an exhaust passage means, and into containment base 13. In any event, this invention 10 includes a floor exhaust passage structure means 12 for fuel reactor shield 11 which, when the reactor shield is subjected to a temperature elevated fuel mass, floor passage means 12 will provide for the flow of the fuel mass before, and in lieu of, any rupture of the sides of fuel reactor shield 11 whereby such a mass will be caused to flow downwardly only from fuel reactor shield 11. Deactivating containment base 13 is provided with, among other things, a manifold chamber 20 (FIGS. 1 and 2), dome 21, distribution passages 22, refractory vessels 23, flux infusion plugs 24 and flux infusion rods 25. Manifold chamber 20 is centrally positioned below exhaust passage means 12 and, dome 21 is centrally positioned within chamber manifold 20. Deactivating containment base 13 is shown to be constructed of concrete or similar material as an intregal part of fuel reactor shield 11 and also forming manifold chamber dome 20. Distribution passages are radially positioned around the base of dome 21 and 22 open into manifold chamber 20. Passages 22 are also inclined downwardly and away from dome 21 whereby fuel flowing over dome 21 will tend to flow through dispersion passages 22 under the force of gravity. Passages 22, dome 21 and the associated chamber 20 are coated with, for example, tungsten or other similar appropriate material, to prevent molten fuel therein from adversely reacting with the material of base 13. Soluble fluxing plugs 24 are provided in each of the passages. The fluxing material of this invention should be a substance with which both molten fuel mass and a chosen control substance are mutually soluble under anticipated conditions. Solubility of the fluxing with the control materials aids in distribution of control material throughout the fuel mass to inhibit nuclear reaction in the fuel. An example of fluxing material are those materials used for uranium glass, and an example of a control element is boron or boron compounds. Control substances further inhibit production of heat and isotopes. Plugs 24 may be composed of fused basalts which will readily dissolve with molten fuel. The plugs 24 will also prevent initial flow of fluid through dispersion passages 22 until plugs 24 are fully dissolved or otherwise melted by the fuel, thus, causing the molten fuel to be backed up in the upper portion of diversion passages 22 into manifold chamber 20 to provide a more equal distribution of the molten fuel with respect to dispersal passages 22. Passages 22 are provided with liners or sleeves 26 of fiberglas, or similar materials (FIG. 3) on collapsible supports 28 (FIG. 5) within jackets 29 to prevent shattering of secondary containment base 13 by expansion of dispersion passage pipe 22. Evacuation of the system is desirable. As illustrated, dispersion passages or pipes 22 are turned vertically downward 30 near the lower ends thereof (FIGS. 1 and 6) and open into refractory containers or vessels 23, composed of firebrick 21, or similar material, with fluxing and control material contained therein. Passage 32 is provided in refractory material 33 in container 23, to facilitate the positioning and containment of additional fluxing material 34, whereby, fuel flowing from vertical portion 30 of dispersion passages 22 into respective containers 23 will be further subjected to cooling as a result of infusion of fluxing material 34 and control material 33 with the molten fuel. A second embodiment of the invention is illustrated in FIG. 4 and is generally, a modification of the lower, or end portion, of deactivating containment base 13 of the first embodiment, with an alternate lower extremity of dispersion passages 22 and associated refractory vessels 23. In particular, in this embodiment of the invention, the molten fuel is passed angularly downwardly from dispersion passage 22 into an angular passage 37 and horizontal passage 38 within and around fluxing and control materials such as boron or cadmium compounds. In this regard, the infusion fluxing rods 34 are positioned horizontally and actually centrally in horizontal passage 38 either by fusible struts 40 (FIG. 4) or by an end anchorage into material 33 (FIG. 6) whereby fluxing material will be spaced within passage 38 to allow molten fuel to pass therearound and thereby be readily dissolved therewith. A third embodiment of this invention is illustrated in FIG. 7 and includes, generally, a fuel reactor shield 41 elevated on a deactivating containment base 43. An open passage means 42 between fuel containment chamber 44 and a manifold chamber 45 directly interconnected by a vertical passage 46, which, in turn, opens upon a dome 47 similar to dome 20 described with respect to the first embodiment, and extends into radially outwardly and downwardly extending dispersion passages 48. Dispersion passages 48 of this embodiment of the invention can be utilized with the flux infusion structures illustrated with respect to the first and second embodiment of this invention (FIGS. 1-6). A fourth embodiment of this invention is illustrated in FIG. 8 and includes generally, a fuel reactor shield 51 on a deactivating containment base 53. An open passage means 52 is provided between a fuel containment chamber 54 and a manifold chamber 55, directly interconnected by a vertical passage 56 which, in turn opens into vertically positioned dispersion passages 57 which extend radially outwardly and downwardly from vertical passage 56, and into respective refractory vessels. The dispersion passages and refractory vessels are otherwise utilized like those above described with respect to the other embodiments of this invention. Soluble plugs 58 are variously selectively provided to control the timing of the flow of fluid mass in passages 57 so that the most uniform distribution of the fluid mass can be had. In operation, when the cooling mechanism, such as water pipes distributed throughout the structure in which the atomic reactor is contained and otherwise associated with, fails for any reason whatsoever, the reactor will elevate rapidly in temperature and will eventually cause the fuel to become a temperature elevated radioactive flowing mass. This mass will first melt the bottom of the primary containment 15 of the reactor and then flow by gravity downwardly upon the floor of reactor shield 11 whereupon the floor 17 thereof, which is either open or provided with a rupture panel which will rupture more readily, and thereby prior to, the rupturing of the walls of reactor shield 11, and thereby will flow through passage means 12 from reactor shield 11 into manifold chamber 20. Molten fuel flowing into manifold chamber 20 will flow downwardly onto dome 21 and be distributed around the base thereof. Continued flow of the mass will carry the mass into the upper portions of diffusion passages 22 and against soluble plugs 24. Plugs 24 will temporarily retain the flow of the molten fuel causing the fuel to be backed up into manifold chamber 20 more evenly distribute the fuel around the base of the dome, in the event of any irregularity in the flow of the fluid around the dome upon its initial contact therewith. Infusion plugs which are preferably made of fused fluxing material or fused basalts and will be dissolved in the molten fuel tending to cool the fuel and when sufficiently dissolved or infused by the fuel will open up dispersal passages to allow the fuel to flow downwardly and outwardly in multiple passages, thereby further dividing and dispersing the fuel to lower the temperature and isotope production thereof. Further flow of the fuel downwardly in passages will result in the flow of fluid into the refractory vessels and additional fluxing material in passage of the fluxing over and around material contained in the vessel to again apply fluxing material to the dispersed fuel and thereby further cool the fuel to a less dangerous temperature. In operation of the second embodiment of this invention (FIG. 4) the fuel mass will flow as it did with respect to the first embodiment and will thus be cooled and dispersed into dispersion passages. However, the molten fuel flowing from passages 37 into refractory containers 31 will proceed therein at an angle and then horizontally over and around fluxing material 34 in passage to finally provide sufficient dissolution of the mass to lower the temperature thereof below the dangerous point. In the operation of the third embodiment of this invention (FIG. 7) the molten radioactive mass that may be formed in the reactor shield 41 will flow through open passage means 42 into a manifold chamber 45 which will direct the super critically elevated fuel mass through a vertical passage 46 and directly over a dispersion dome 47 whereby the fuel will be distributed through multiple dispersion passages 48. Thereafter the molten fuel will be received and fluxed in accordance with either of the structures of the first or second embodiments of this invention, as above described, to finally lower the temperature of the fuel mass to below the dangerous level. In operation of the fourth embodiment of this invention (FIG. 8) the molten radioactive mass that may be found in the reactor chamber of shield 51 will flow through open passage means 52 into manifold chamber 55 which will direct the molten fuel mass through extended vertical passage 56 and directly into passages 57. Plugs 58 will act much like plugs 24 of the first embodiment of this invention, with plug 58 in extended vertical passage being in direct line of the flow of fuel as was dome 21. Thus, it can be seen that the nuclear reactor fuel containment safety structure of this invention provides a means whereby any radioactive molten fuel mass formed within the fuel reactor shield will be automatically dispersed into multiple parts whereby the regenerative critical heating characteristics thereof will, by dispersal be greatly reduced. Moreover, the nuclear reactor fuel containment safety structure of this invention provides a dispersion means which is efficient, due to the provision of means for uniformly distributing the molten fuel means into the dispersion structure. Further, fluxing dispersion means is provided within the dispersion structure whereby additional cooling, as a result of the fluxing effects, are provided within the dispersion structures of this invention to further lower the temperature of the radioactive and temperature elevated flowing fuel mass to lower the temperature below the dangerous range to a safe temperature. All of these functions are provided without reliance on auxillary water cooling, or other cooling systems, which have been relied on in the past and which are subject to rupture and other malfunction and, all automatically without being subject to the deficiency associated with reliance human reaction or intricate mechanical interlocked or interconnected systems which are so readily subject to failure. Changes may be made in the form, construction and arrangement of parts from that disclosed herein without in any way departing from the spirit of the invention or sacrificing any of the attendant advantages thereof, provided, however, that such changes fall within the scope of the claims appended hereto.
	description	This application is a continuation of U.S. patent application Ser. No. 10/100,223 filed Mar. 15, 2002 now abandoned, which claims priority under 35 U.S.C. § 119(e) to U.S. Provisional Application No. 60/358,132, filed Feb. 20, 2002, the disclosure of which is incorporated by reference herein. 1. Field of the Invention The invention relates in general to the field of construction, and specifically to improved apparatus and methods for seismic retrofitting concrete structures. 2. Description of the Related Art Retrofitting of existing concrete structures is often necessary to meet improved building safety codes. For example, in regions of the world susceptible to earthquakes, building codes are continually examined and modified by the appropriate regulatory agencies to require improved structural resilience to seismic activity by retrofitting the existing structure to provide additional stability and resilience to seismic vibrations. Seismic retrofitting of an existing concrete structure is often a large undertaking with significant inconveniences to the occupants of the concrete structure. Some retrofitting procedures comprise strengthening the concrete structure by coupling additional concrete and/or steel (to provide ductility). Other retrofitting procedures comprise isolating the concrete structure from the ground by installing shock absorbing systems. Typically, such construction projects entail high levels of noise, dust, pollution, vibration, and general disruption to the normal operations of the concrete structure. These inconveniences are especially troublesome for structures such as hospitals, where the occupants are especially sensitive to any disruptions, and relocation for the duration of the construction project is generally not feasible. Mechanical drilling of concrete is an especially disruptive component of the retrofitting of concrete structures. Typically, such mechanical drilling is accomplished by using diamond-tipped rotary drills or impact drills, which drill by brute physical contact with the concrete surface. These types of mechanical drills produce high levels of noise, the concrete surface. These types of mechanical drills produce high levels of noise, significant vibrations which propagate to other parts of the structure, and substantial amounts of dust and debris which require special protective measures. Lasers have been used in exotic construction projects, because of their ability to cut a wide variety of materials and their applicability to hazardous or extreme conditions. For example, in U.S. Pat. No. 4,227,582 (“the '582 patent”) issued to Price and incorporated in its entirety by reference herein, Price discloses an apparatus and method for perforating a well casing and its surrounding formations from within the confined area of an oil or gas well. In the '582 patent, the laser drilling tool is used in conjunction with a high pressure injection of exothermic gases (e.g., oxygen) and fluxing agents (e.g., powdered iron or alkali halides) which react with the drilled material to speed up the drilling process. In addition, U.S. Pat. No. 4,568,814 (“the '814 patent”) issued to Hamasaki et al., and incorporated in its entirety by reference herein, discloses an apparatus and method for cutting concrete in highly hazardous contexts, such as for the dismantling of a biological shield wall in a nuclear reactor. The '814 patent also discloses the use of an automated laser cutter in the conjunction with MgO-rich supplementary materials and a cleaning device to facilitate the removal of the viscous molten slag produced by the cutting process. A study of the cutting ability of a carbon dioxide laser as a function of numerous parameters to cut concrete and reinforced concrete has been performed by Yoshizawa, et al. entitled “Study on Laser Cutting of Concrete” and published in the April 1989 “Transactions of the Japan Welding Society,” Vol. 20, No. 1, p. 31 (hereafter referred to as “the Yoshizawa article”), which is incorporated in its entirety by reference herein. The Yoshizawa article provides data from laboratory experiments which monitored the depth of cuts generated by the laser as a function of laser power, assist gas pressure and direction, laser lens focal length, scanning speed of the laser spot across the concrete, and types and water content of the concrete. In addition, the Yoshizawa article concluded that laser energy densities greater than approximately 106 W/cm2 are necessary to cut concrete, and laser energy densities greater than approximately 107 W/cm2 are necessary to cut steel-reinforced concrete. In one embodiment of the present method, there is disclosed a method of seismic retrofitting a concrete structure. The method comprises removing material from a portion of the concrete structure by irradiating the portion with a laser beam having a laser energy density. The method further comprises positioning a stabilization structure in proximity to the portion of the concrete structure. The method further comprises attaching the stabilization structure to the portion of the concrete structure, whereby the stabilization structure provides structural support to the concrete structure. In another embodiment of the present method, there is disclosed a method of seismic retrofitting a concrete structure occupied by equipment and people. The equipment and people have a noise tolerance level, a vibration tolerance level, and a particulate tolerance level. The method comprises removing material from a portion of the concrete structure by irradiating the portion with a laser beam. Removing the material generates noise at a noise level less than the noise tolerance level, vibrations at a vibration level less than the vibration tolerance level, and particulates at a particulate level less than the particulate tolerance level. The method further comprises positioning a stabilization structure in proximity to the portion of the concrete structure. The method further comprises attaching the stabilization structure to the portion of the concrete structure, whereby the stabilization structure provides structural support to the concrete structure. In yet another embodiment of the present method, there is disclosed a method of seismic retrofitting a concrete structure. The method comprises removing material from a portion of the concrete structure by irradiating the portion with a laser beam. The method further comprises providing structural support to the concrete structure. For purposes of summarizing the invention and the advantages achieved over the prior art, certain objects and advantages of the invention have been described herein above. It is to be understood that not necessarily all such objects or advantages may be achieved in accordance with any particular embodiment of the invention. Thus, for example, those skilled in the art will recognize that the invention may be embodied or carried out in a manner that achieves or optimizes one advantage or group of advantages as taught herein without necessarily achieving other objects or advantages as may be taught or suggested herein. All of these embodiments are intended to be within the scope of the present invention herein disclosed. These and other embodiments of the present invention will become readily apparent to those skilled in the art from the following detailed description of the preferred embodiments having reference to the attached figures, the invention not being limited to any particular embodiment disclosed. FIG. 1 is a flowchart of one embodiment of a method 100 of seismic retrofitting a concrete structure 10. The method 100 comprises an operational block 110 comprising removing material from a portion 20 of the concrete structure 10 by irradiating the portion 20 with a laser beam 30 having a laser energy density. The method 100 further comprises an operation block 120 comprising positioning a stabilization structure 40 in proximity to the portion 20 of the concrete structure 10. The method 100 further comprises an operational block 130 comprising attaching the stabilization structure 40 to the portion 20 of the concrete structure 10. The stabilization structure 40 provides structural support to the concrete structure 10. By using a laser beam 30 to remove material from the portion 20 of the concrete structure 10, seismic retrofitting of the concrete structure 10 can be performed with significantly less noise, vibrations, and particulates than are produced using conventional drilling or cutting techniques. Typically, concrete structures 10, such as buildings, are occupied by equipment and people which have a noise tolerance level, a vibration tolerance level, and a particulate tolerance level. For example, in certain embodiments, the concrete structure 10 comprises a healthcare facility, such as a hospital, which is occupied by healthcare equipment, personnel, and patients which are particularly sensitive to disruptions and excessive noise, vibration, and particulates. The levels of noise, vibration, and particulates generated by the removal of material from the portion 20 of the concrete structure 10 by irradiating the portion 20 with the laser beam 30 can be less than the corresponding tolerance levels, thereby permitting the seismic retrofitting to be performed without disturbing the operations of the healthcare facility or its patients. In certain embodiments, the position, motion, scanning speed, and laser energy density of the laser beam 30 are all preferably controlled by a control system. The control system can be controlled by a programmable microchip, or can be operated manually to perform the desired removal of material as described herein. Persons skilled in the art are able to configure a control system in accordance with embodiments of the present invention. The laser beam 30 is generated by a laser system, which in certain embodiments comprises a hydrofluorine chemically driven laser, a carbon dioxide laser, a solid state laser such as neodymium glass, or other types of advanced lasers. In certain embodiments, the various operating parameters of the laser system, including but not limited to pulse length, frequency, laser energy density, and area and diameter of the laser beam 30, are controlled by the control system to provide optimal cutting and boring for the seismic retrofitting procedures being performed. In addition, the laser system of certain embodiments is adapted to permit the laser beam 30 to be positioned and scanned across the surface of the portion 20 of the concrete structure 10 to be irradiated. The laser system of certain embodiments is configured to avoid excessive heating of the concrete, thereby avoiding substantial damage to the structural integrity of the concrete structure 10. For example, the laser energy density and laser cutting speed are preferably optimized to provide a clean surface cut with a minimum of heat transferred to the concrete. Other embodiments include the use of water or other cooling fluids to limit heat damage to the concrete structure 10. The laser system of certain embodiments can also comprise an apparatus to assist the removal of slag from the cutting region. In certain embodiments, slag removal is assisted by a source of gases and a nozzle to generate a gas stream which accelerates the rate of laser beam penetration by blowing away the irradiated slag from the cutting region. In other embodiments, the gases comprise exothermically reactive gases which interact with a fluxing agent to assist the removal of material. In still other embodiments, the laser system comprises a source of MgO-rich supplementary material which is mixed with the molten slag, thereby making the slag more easily removable. Such embodiments can also comprise a cleaning device, such as a wire brush, scraping tool, or vacuum system, to remove the slag from the irradiated region. Timely removal of hot slag will further help control the heat transferred to the concrete, thus preferably reducing the heat damage to the concrete structure 10. Examples of laser systems compatible with embodiments of the present invention are described by the '582 patent of Price and the '814 patent of Hamasaki, et al., which are incorporated in their entirety by reference herein. FIGS. 2A, 2B, and 2C schematically illustrate one embodiment of seismic retrofitting a portion 20 of a concrete structure 10. In the embodiment schematically illustrated in FIG. 2A, the portion 20 comprises a wall 22. In one embodiment, material is removed from the wall 22 by irradiating the wall 22 with a laser beam 30 having a laser energy density, thereby boring a hole 24 into the wall 22. The hole 24 of certain embodiments can extend through the full width of the wall 22, while in other embodiments the hole 24 extends only partially through the width of the wall 22, as schematically illustrated in FIG. 2A. In certain embodiments, the laser beam 30 is configured such that a substantially cylindrical hole 24 is formed without substantial movement of the laser beam 30 across the surface of the wall 22. In other embodiments, boring the hole 24 comprises moving the laser beam 30 in a circular motion along a surface of the wall 22 such that a substantially cylindrical hole is formed. As described in the Yoshizawa article, the depth of a laser cut in concrete can be controlled, in part, by the speed at which the laser beam 30 is scanned across the surface of the concrete. The hole 24 can then be bored by making multiple passes of the laser beam 30 over an area of the concrete until a desired depth and width of material is removed. This procedure can also provide additional control of the heat transferred into the concrete to reduce thermal damage. In still other embodiments, the hole 24 has a generally conical shape or even an arbitrary shape. Persons skilled in the art are able to configure a laser to generate the laser beam 30 with an appropriate laser energy density to bore the hole 24 in accordance with embodiments of the present invention. As schematically illustrated in FIG. 2B, in certain embodiments, positioning a stabilization structure 40 in proximity to the wall 22 comprises positioning a rebar 50 in the hole 24 in the wall 22 and affixing the rebar 50 in the hole 24. Typically, the rebar 50 comprises steel or iron, and provides additional coupling between the portion 20 of the concrete structure 10 and the stabilization structure 40. The rebar 50 also provides additional structural strength to the stabilization structure 40. In certain embodiments, the rebar 50 is placed in the hole 24, epoxy 60 is applied between the rebar 50 and the hole 24, and the epoxy 60 is given time to set, thereby affixing the rebar 50 to the wall 22. Persons skilled in the art are able to select an appropriate epoxy 60 in accordance with embodiments of the present invention. In typical embodiments, more than one hole 24 is bored into the wall 22, each hole 24 having a rebar 50 affixed therein. In certain embodiments, the rebars 50 affixed to the wall 22 are coupled together by other rebars 52, thereby forming a rebar lattice structure 54, as schematically illustrated in FIG. 2B. Persons skilled in the art are able to configure the rebars 50, 52 in accordance with embodiments of the present invention. In certain embodiments, attaching the stabilization structure 40 to the wall 22 further comprises forming a stabilization wall 42 by pouring concrete 70 into a temporary mold built around the rebars 50. Upon setting, the poured concrete 70 forms the stabilization wall 42 which is contiguously coupled to the wall 22, and which comprises the rebars 50, 52, as schematically illustrated in FIG. 2C. In such an embodiment, the stabilization wall 42 provides structural support to the concrete structure 10. Persons skilled in the art are able to form a stabilization wall 42 in accordance with embodiments of the present invention. As schematically illustrated in FIG. 3A, in other embodiments of the present invention, the portion 20 of the concrete structure 10 comprises a wall 22 and removing material from the wall 22 comprises cutting a key 80 into the wall 22. The key 80 is a cutout from the surface of the wall 22, as schematically illustrated in FIG. 3A. In certain embodiments, cutting the key 80 comprises moving the laser beam 30 in multiple cutting passes along a surface of the wall 22 such that a generally rectangular key 80 is formed. In other embodiments, the key 80 has a circular shape or even an arbitrary shape. Typically, more than one key 80 is cut into the wall 22 to provide additional structural strength, as described in more detail below. Persons skilled in the art are able to configure keys 80 having dimensions and shapes compatible with the present invention. In certain embodiments, positioning a stabilization structure 40 in proximity to the wall 22 and attaching the stabilization structure 40 to the wall 22 comprises forming a stabilization wall 42 by pouring concrete 70 into a temporary mold built around a surface of the wall 22 with the keys 80, thereby filling the keys 80 with the poured concrete 70. Upon setting, the poured concrete 70 forms the stabilization wall 42 which is contiguously coupled to the wall 22 by an interlocking structure at the surface between the wall 22 of the concrete structure 10 and the stabilization wall 42, as schematically illustrated in FIG. 3B. In such an embodiment, the stabilization wall 42 provides structural support to the concrete structure 10, whereby the keys 80 resist shear stresses between the wall 22 and the stabilization wall 42. In certain embodiments, the keys 80 described herein are formed in conjunction with the holes 24 and rebars 50, 52 described above to form a stabilization wall 42 with additional structural stability. Persons skilled in the art are able to form a stabilization wall 42 in accordance with embodiments of the present invention. In certain embodiments, the portion 20 of the concrete structure 10 to be seismically retrofitted comprises rebars 56 which provide additional structural strength to the portion 20. For stronger structural support for the concrete structure 10, the stabilization structure 40 of certain embodiments is coupled to the rebars 56 of the portion 20. In such embodiments where the portion 20 of the concrete structure 10 comprises a rebar 56 embedded in the concrete structure 10, removing material comprises removing concrete to expose a portion of the rebar 56. In embodiments in which keys 80 are cut into the portion 20, the keys 80 can be cut by the laser beam 30 in proximity to the rebars 56 of the portion 20 and having dimensions such that the rebars 56 are exposed, as schematically illustrated in FIG. 4. The poured concrete 70 which comprises the stabilization structure 40 can then couple to the rebars 56, thereby providing additional structural strength. In certain embodiments, the rebars 56 are only partially exposed by the laser beam 30, while in other embodiments, portions of the rebars 56 have the surrounding concrete completely removed by the laser beam 30, such that the poured concrete 70 of the stabilization structure 40 surrounds the portions of the rebars 56. In other embodiments, the exposed rebars 56 can be coupled to additional rebars 50, 52 of the stabilization structure 40, thereby providing a more intimate coupling between the portion 20 of the concrete structure 10 and the stabilization structure 40. Similarly, in embodiments in which holes 24 are bored by the laser beam 30 into the portion 20, the holes 24 can be positioned and have dimensions to advantageously expose portions of the rebars 56 in the portion 20 of the concrete structure 10. In order to minimize damage to the rebar 56 in the portion 20 of the concrete structure 10 by the laser beam 30, in certain embodiments, removing material from the portion 20 of the concrete structure 10 further comprises detecting the rebar 56 and avoiding substantially irradiating the rebar 56, thereby avoiding substantially damaging the rebar 56. FIG. 5 schematically illustrates one embodiment of a configuration in which the laser beam 30 is cutting away a section of concrete in which a rebar 56 is embedded, the configuration comprising an electronic eye 90. The arrow indicates the scanning direction of the laser beam 30 across the concrete being cut. In certain embodiments, a relatively shallow depth of concrete is preferably cut away on each pass of the laser beam 30, with the passes being repeated until the rebar 56 is exposed and detected by the electronic eye 90. In certain embodiments, the electronic eye 90 is disposed such that the electronic eye 90 detects the rebar 56 by detecting light reflected from the rebar 56 as material is being removed and responding to differences in the reflectance of the rebar 56 and the concrete. The reflected light can be generated by the laser beam 30, ambient light, or other light source. In other embodiments, the electronic eye 90 is responsive to photospectrometry differences or other differences in the interactions of the rebar 56 and the concrete to the incident light. In still other embodiments, the electronic eye 90 is responsive to other characteristics of the rebar 56 which differ from those of the surrounding concrete. Persons skilled in the art can configure the electronic eye 90 in accordance with embodiments of the present invention. In certain embodiments, once light reflected from the rebar 56 is detected by the electronic eye 90, the laser beam 30 is advanced away from the rebar 56 to another section of concrete, thereby avoiding substantially irradiating the rebar 56. In alternative embodiments, the laser energy density of the laser beam 30 is reduced upon detecting light reflected from the rebar 56. As described in the Yoshizawa article incorporated by reference herein, the laser energy density of the laser beam 30 can be reduced to a level which can cut concrete but leaves rebar substantially undamaged. In this way, the concrete can be cut to an appropriate depth to ensure sufficient coupling between the concrete structure 10 and the stabilization structure 40, and damage to the rebar 56 within the concrete structure 10 is limited so as not to affect its structural integrity. In still other embodiments, the position of the rebar 56 within the concrete structure 10 can be located using x-rays. By imaging the rebar 56 within the portion 20 of the concrete structure 10 from a plurality of directions, the depth of the rebar 56 within the portion 20 of the concrete structure 10 can be determined, as well as the location of the rebar 56 along the surface of the portion 20 of the concrete structure 10. Such determinations of the locations of the rebars 56 can be performed before the laser beam 30 is positioned to remove material, thereby allowing a user to determine a suitable location at which to bore holes 24, cut keys 80, or remove material. Persons skilled in the art are able to utilize x-rays to locate the rebar 56 in accordance with embodiments of the present invention. As schematically illustrated in FIGS. 6A, 6B, and 6C, in certain embodiments, the portion 20 of the concrete structure 10 comprises a column 26 and removing material from the portion 20 comprises boring a hole 24 into the column 26. These holes 24 are used in certain embodiments to couple a stabilization structure 40 comprising a stabilization wall 42 to the column 26. In embodiments in which the column 26 comprises rebars 56, the locations of the existing rebars 56 are identified so that the holes 24 for new rebars 50 can be located in proximity to the existing rebars 56 in the column 26. In certain embodiments, as schematically illustrated in FIG. 6A, the locations of the existing rebars 56 in the column 26 are identified by removing material from the outer surface of the column 26 by irradiating the column 26 with the laser beam 30, thereby exposing the rebars 56. Typically, the rebars 56 are approximately 1.5″ below the surface of the column 26, thereby requiring approximately 1.5″ of concrete to be removed by irradiation with the laser beam 30 in the region where the column 26 is to be coupled to the stabilization wall 42. Persons skilled in the art recognize that the actual depth may vary depending on the particular column 26 being seismically retrofitted. Additionally, the removal of the surface material from the column 26 can be used to roughen the surface, thereby providing a stronger coupling between the column 26 and the stabilization wall 42. The holes 24 are bored by irradiating the column 26 with the laser beam 30 in proximity to the existing rebars 56 of the column 26, as schematically illustrated in FIG. 6B. In certain embodiments, boring a hole 24 into the column 26 comprises moving the laser beam 30 in a circular motion along a surface of the column 26 such that a substantially cylindrical hole 24 is formed, as described above in relation to boring a hole 24 in a wall 22. As described above in relation to seismic retrofitting a wall 22, the column 26 of certain embodiments is coupled to a stabilization wall 42, whereby the stabilization wall 42 provides structural support to the column 26. In such embodiments, rebars 50 are affixed by epoxy 60 in the holes 24 bored by the laser beam 30. In typical embodiments, more than one hole 24 is bored into the column 26, and each hole 24 has a rebar 50 affixed therein. In certain embodiments, the rebars 50 affixed to the column 26 are coupled together by other rebars 52, thereby forming a rebar lattice structure 54, as schematically illustrated in FIG. 6B. Persons skilled in the art are able to configure the rebars 50, 52 in accordance with embodiments of the present invention. In certain embodiments, coupling the stabilization structure 40 to the column 26 further comprises forming a stabilization wall 42 by pouring concrete 70 into a temporary mold built around the rebars 50. Upon setting, the poured concrete 70 forms the stabilization wall 42 which is contiguously coupled to the column 26, and which comprises the rebars 50, 52, as schematically illustrated in FIG. 6C. In such an embodiment, the stabilization wall 42 provides structural support to the column 26. Persons skilled in the art are able to form a stabilization wall 42 in accordance with embodiments of the present invention. Alternatively, or in addition to boring holes 24 in the column 26, removing material from the column 26 in certain embodiments comprises cutting a key 80 into the column. In certain embodiments, cutting a key 80 into the column 26 comprises moving the laser beam 30 in multiple cutting passes along a surface of the column 26, as described above in relation to cutting a key 80 in a wall 22. Upon setting, the poured concrete 70 forms the stabilization wall 42 which is contiguously coupled to the column 26 by an interlocking structure at the surface between the column 26 and the stabilization wall 42. In such an embodiment, the stabilization wall 42 provides structural support to the column 26, whereby the keys 80 resist shear stresses between the column 26 and the stabilization wall 42. Persons skilled in the art can select an appropriate removal of material from the column 26 in accordance with embodiments of the present invention. As schematically illustrated in FIG. 7, in certain embodiments, the portion 20 of the concrete structure 10 comprises a floor 28 and beam 29 and removing material from the portion 20 comprises boring holes 24 into the floor 28 and the beam 29 by irradiating the portion 20 with the laser beam 30. These holes 24 are used in certain embodiments to couple a stabilization structure 40 comprising a stabilization column 44 to the floor 28 and beam 29. In such embodiments, the laser beam 30 is used to bore holes 24 through the floor 28 and into the beam 29. Rebars 50 are affixed to the beam 29 as described above and rebars 52 are inserted through the holes 24 of the floor 28 and coupled to the rebars 50 to form a rebar lattice structure 54. In certain embodiments, coupling the stabilization structure 40 to the floor 28 and beam 29 further comprises forming a stabilization column 44 by pouring concrete 70 into a temporary mold built around the rebar lattice structure 54. Upon setting, the poured concrete 70 forms the stabilization column 44 which is contiguously coupled to both the floor 28 and beam 29, and which comprises the rebars 50, 52. In such an embodiment, the stabilization column 44 provides structural support to the concrete structure 10. Persons skilled in the art are able to form a stabilization column 44 in accordance with embodiments of the present invention. In other embodiments, as schematically illustrated in FIG. 8, holes 24 can be cut into a portion 20 of the concrete structure 10 by coring a cylindrical plug 90 using the laser beam 30, and then breaking off the cylindrical plug 90. To core a cylindrical plug 90, the laser beam 30 is moved in a circular motion while directed at the surface of the portion 20 of the concrete structure 10, thereby cutting around the circumference of the hole 24. Such embodiments are particularly useful for forming large holes 24 while reducing the likelihood of heat damage to the concrete by avoiding the large power incident onto the concrete for removing all the material in the hole 24 by laser beam irradiation. While illustrated in the context of retrofitting concrete structures, persons skilled in the art will readily find application for the methods and apparatus herein to other construction projects generally. Although this invention has been disclosed in the context of certain preferred embodiments and examples, it will be understood by those skilled in the art that the present invention extends beyond the specifically disclosed embodiments to other alternative embodiments and/or uses of the invention and obvious modifications and equivalents thereof. Thus, it is intended that the scope of the present invention herein disclosed should not be limited by the particular disclosed embodiments described above, but should be determined only by a fair reading of the claims that follow.
	abstract	A method and apparatus for maintaining or establishing a readiness state in a fuel cell backup system of a nuclear reactor system are disclosed. A method includes maintaining a readiness state of a fuel cell system within a set of readiness parameters, the readiness parameters a function of a characteristic of the nuclear reactor system. Another method includes monitoring a nuclear reactor system characteristic and, responsive to the monitored nuclear reactor system characteristic, establishing a readiness state of a fuel cell system. An apparatus includes a fuel cell system associated with a nuclear reactor system and a fuel cell control system configured to maintain a readiness state of the fuel cell system. Another apparatus includes a fuel cell system associated with a nuclear reactor system, a nuclear reactor characteristic monitoring system, and a fuel cell control system configured to establish a readiness state of the fuel cell system.
	summary
	abstract	A gauge is provided for measuring one or more characteristics of a construction material such as a road surface. The gauge includes a detector, a base that carries the detector, and a source housing carried by the base and defining a shield material circumferentially extending inwards. A source rod is positioned within the housing and carries a source that is translatable between a shielded position within the housing and a measuring position external of the housing. The source rod has a source shield on the top thereof and a shield material spaced-downwardly from the source such that the source is completely enclosed when contained within the base.
	summary
	summary
	claims	1. A nuclear reactor comprising:a nuclear reactor core volume configured to hold molten fuel salt during a sustained nuclear fission reaction;a neutron reflector assembly of a plurality of reflector elements separated by an interstitial space within a reflector volume surrounding the nuclear reactor core volume, the interstitial space configured to hold molten fuel salt;a fixed core barrel between the nuclear reactor core volume and the neutron reflector assembly; andthe neutron reflector assembly being further configured to adjust fast neutron flux and thermal neutron flux within the nuclear reactor core volume by altering reflectivity characteristics of reflector material in the reflector elements;wherein each reflector element is a reflector tube containing at least some neutron reflecting material and the interstitial space is separated from the nuclear reactor core by the fixed core barrel; andwherein the fixed core barrel is arranged to allow molten fuel salt to pass between the reactor core volume and the interstitial space between the reflector tubes in the reflector volume. 2. The nuclear reactor of claim 1 wherein the interstitial space contains a chloride salt. 3. The nuclear reactor of claim 2 wherein the chloride salt has an enriched amount of the Cl isotope. 4. The nuclear reactor of claim 1 wherein at least one of the reflector tubes is rotatable. 5. The nuclear reactor of claim 1 wherein at least one of the reflector tubes includes a neutron absorbing element in addition to the reflecting material. 6. The nuclear reactor of claim 5 wherein the neutron absorbing element is a partial liner inside a casing of the reflector tube. 7. The nuclear reactor of claim 1 further comprising:at least one insertable core barrel sized to fit within and adjacent to the fixed core barrel and, thereby, reducing the nuclear reactor core volume. 8. The nuclear reactor of claim 1 wherein at least two of the reflector tubes in the plurality of reflector elements have different radius values. 9. A nuclear reactor comprising:a nuclear reactor core volume configured to hold molten fuel salt during a sustained nuclear fission reaction;a neutron reflector assembly of a plurality of reflector elements separated by an interstitial space within a reflector volume surrounding the nuclear reactor core volume, the interstitial space configured to hold molten fuel salt;a fixed core barrel between the nuclear reactor core volume and the neutron reflector assembly; andthe neutron reflector assembly being further configured to adjust fast neutron flux and thermal neutron flux within the nuclear reactor core volume by altering reflectivity characteristics of reflector material in the reflector elements;wherein each reflector element is a reflector tube containing at least some neutron reflecting material and the interstitial space is separated from the nuclear reactor core by the fixed core barrel; andwherein at least one of the reflector tubes is rotatable. 10. The nuclear reactor of claim 9 wherein the interstitial space contains a chloride salt. 11. The nuclear reactor of claim 10 wherein the chloride salt has an enriched amount of the Cl isotope. 12. The nuclear reactor of claim 9 wherein the fixed core barrel is arranged to allow molten fuel salt to pass between the reactor core volume and the interstitial space between the reflector tubes in the reflector volume. 13. The nuclear reactor of claim 9 wherein at least one of the reflector tubes includes a neutron absorbing element in addition to the reflecting material. 14. The nuclear reactor of claim 13 wherein the neutron absorbing element is a partial liner inside a casing of the reflector tube. 15. The nuclear reactor of claim 9 further comprising:at least one insertable core barrel sized to fit within and adjacent to the fixed core barrel and, thereby, reducing the nuclear reactor core volume. 16. The nuclear reactor of claim 9 wherein at least two of the reflector tubes in the plurality of reflector elements have different radius values. 17. A nuclear reactor comprising:a nuclear reactor core volume configured to hold molten fuel salt during a sustained nuclear fission reaction;a neutron reflector assembly of a plurality of reflector elements separated by an interstitial space within a reflector volume surrounding the nuclear reactor core volume, the interstitial space configured to hold molten fuel salt;a fixed core barrel between the nuclear reactor core volume and the neutron reflector assembly; andthe neutron reflector assembly being further configured to adjust fast neutron flux and thermal neutron flux within the nuclear reactor core volume by altering reflectivity characteristics of reflector material in the reflector elements;wherein each reflector element is a reflector tube containing at least some neutron reflecting material and the interstitial space is separated from the nuclear reactor core by the fixed core barrel; andwherein at least two of the reflector tubes in the plurality of reflector elements have different radius values. 18. The nuclear reactor of claim 17 wherein the interstitial space contains a chloride salt. 19. The nuclear reactor of claim 18 wherein the chloride salt has an enriched amount of the Cl isotope. 20. The nuclear reactor of claim 17 wherein at least one of the reflector tubes is rotatable. 21. The nuclear reactor of claim 17 wherein at least one of the reflector tubes includes a neutron absorbing element in addition to the reflecting material. 22. The nuclear reactor of claim 21 wherein the neutron absorbing element is a partial liner inside a casing of the reflector tube. 23. The nuclear reactor of claim 17 further comprising:at least one insertable core barrel sized to fit within and adjacent to the fixed core barrel and, thereby, reducing the nuclear reactor core volume. 24. The nuclear reactor of claim 17 wherein the fixed core barrel is arranged to allow molten fuel salt to pass between the reactor core volume and the interstitial space between the reflector tubes in the reflector volume. 25. A nuclear reactor comprising:a nuclear reactor core volume configured to hold molten fuel salt during a sustained nuclear fission reaction;a neutron reflector assembly of a plurality of reflector elements separated by an interstitial space within a reflector volume surrounding the nuclear reactor core volume, the interstitial space configured to hold molten fuel salt;a fixed core barrel between the nuclear reactor core volume and the neutron reflector assembly; andthe neutron reflector assembly being further configured to adjust fast neutron flux and thermal neutron flux within the nuclear reactor core volume by altering reflectivity characteristics of reflector material in the reflector elements;wherein the core barrel is arranged to allow molten fuel salt to pass between the reactor core volume and the interstitial space between the reflector elements in the reflector volume. 26. The nuclear reactor of claim 25 wherein the interstitial space contains a chloride salt. 27. The nuclear reactor of claim 26 wherein the chloride salt has an enriched amount of the Cl isotope. 28. The nuclear reactor of claim 25 wherein each reflector element is an annular element containing at least some neutron reflecting material. 29. The nuclear reactor of claim 25 wherein each annular element is a channel containing neutron reflecting material. 30. The nuclear reactor of claim 25 wherein each reflector element is an annular element containing at least some neutron reflecting material. 31. The nuclear reactor of claim 25 wherein each reflector element is a reflector tube containing at least some neutron reflecting material. 32. The nuclear reactor of claim 31 wherein at least two of the reflector tubes in the plurality of reflector elements have different radius values. 33. The nuclear reactor of claim 31 wherein at least one of the reflector tubes is rotatable. 34. The nuclear reactor of claim 31 wherein at least one of the reflector tubes includes a neutron absorbing element in addition to the reflecting material. 35. The nuclear reactor of claim 34 wherein the neutron absorbing element is a partial liner inside a casing of the reflector tube. 36. The nuclear reactor of claim 25 further comprising:at least one insertable core barrel sized to fit within and adjacent to the fixed core barrel and, thereby, reducing the nuclear reactor core volume.
050680811	claims	1. A method of assembling a nuclear fuel assembly, comprising the steps of: preparing a plurality of grids each of which comprises a plurality of elongated straps intersected with each other to define a plurality of grid cells therein, and a plurality of pairs of dimples and springs formed on said straps for supporting a plurality of fuel rods, each pair of dimple and spring being disposed in facing relation to each other, on wall sections of the straps, which cooperate with each other to define one of the grid cells, the pair of dimples and spring projecting into the grid cell; subsequently inserting a deflecting jig into one of the grid cells defined in each of said grids, said deflecting jig being in the form of a rod having a diameter capable of being enlarged; subsequently enlarging the diameter of said deflecting jig to urge the spring associated therewith against resilient force of the spring to deflect the spring away from the dimple associated therewith; subsequently inserting a plurality of elongated key members, respectively along a longitudinal direction of the straps forming the grid, into the grid cells through a plurality of openings which are defined at intersections between the straps, each of said key members being formed with a plurality of hooks which are spaced a predetermined spacing from each other along the longitudinal direction of the key member; subsequently rotating each of said key members about its axis to cause the hooks of the key member to project from a wall surface of the strap associated with the key member, through the openings, in a direction opposite to the projecting direction of the springs formed on the strap; subsequently moving the key member forwardly in the longitudinal direction of the strap to engage the hooks of the key member with the wall surface of the strap, thereby fixedly mounting the key member to the strap to maintain the springs deflected; subsequently releasing the urging of the spring due to said deflecting jig to withdraw the same from the grid cell and, subsequently, inserting said fuel rods respectively into the grid cells; subsequently moving the key member rearwardly to release retention of the springs due to the hooks of the key member thereby bringing the springs into pressure contact with the fuel rods, respectively; and withdrawing said key members from the grid cells. 2. A method according to claim 1, wherein, when the respective springs are maintained deflected by the hooks of the key member, the pair of dimples and spring have a distance therebetween which is larger than a diameter of the fuel rod. 3. A method according to claim 1, in which each of the straps includes a plurality of ribs associated respectively with the springs formed on the strap, each of the hooks on the key member being able to be engaged with a corresponding one of the ribs. 4. A method according to claim 3, wherein each of the ribs is spaced from a corresponding one of the springs in a direction away from the grid cell associated with the spring. 5. A method according to claim 3, wherein each of the straps includes a plurality of pairs of said ribs, and wherein each spring is located between a corresponding pair of ribs. 6. A method according to claim 1, wherein said deflecting jig comprises a sleeve divided into a plurality of sleeve pieces and a tapered pin inserted into said sleeve for axial sliding movement along the same.
046577254	description	DETAILED DESCRIPTION FIG. 1 shows a core of a pressurized water nuclear reactor incorporating prismatic assemblies with hexagonal cross-sections placed side by side and occupying the entire height of the core. In contrast to the core of pressurized water nuclear reactors of the prior art, these assemblies are not all identical. Referring to FIGS. 1 and 2, assemblies 1 and 2 consist of clusters of rods 5 containing enriched uranium oxide and arranged according to a lattice providing interstices between the rods for the formation of layers of water of a sufficient thickness for moderating the neutrons as far as the thermal region. Some rods of the assembly lattice are replaced with guide tubes and into these guide tubes can be inserted rods of depleted uranium as described in French Pat. No. 2,535,508. The insertion of rods of depleted uranium into the guide tubes 4 of the assemblies of the type 1 and 2 during the first part of the fuel cycle makes it possible to displace water from these guide tubes, to harden the neutron spectrum and thus to increase the production of plutonium in the fuel. An additional hardening derives from the fact that the rods of depleted uranium absorb the low-energy neutrons. The production of plutonium is also increased by the fact that a part of uranium 238 present in the depleted uranium rods is converted into plutonium. In the assemblies of type 1, only the uranium rods which permit a spectral shift to be obtained are inserted in the guide tubes 4, while in the assemblies of type 2, some guide tubes are reserved for the movement of the rods controlling the reactivity of the reactor core during its operation. The guide tubes of these assemblies 2 therefore receive, on the one hand, the rods of depleted uranium of the device for spectral shift control and, on the other hand, the reactor control rods. The assemblies 1 and 2 form a group of zones which extend over the entire height of the reactor core where the uranium oxide fuel rods have interstices of a relatively large size. Between the zones formed by the assemblies 1 and 2, the core comprises assemblies 3 of a composition and structure which are completely different from the assemblies 1 and 2. The assemblies 3 are arranged as a checkboard between the assemblies 1 and 2. The assemblies 3 consist of rods 6 comprising mainly recovered plutonium containing 70% of fissile isotopes and 30% of non-fissile isotopes. These rods are arranged in a regular lattice whose interstices have a size which is much less than the size of the interstices in the assemblies 1 and 2. The interstices have an average size which is approximately three times less than the size of the interstices of assemblies 1 and 2. This small interstice between the plutonium rods can be obtained by winding spacer wires in a spiral on these tubes as in the assemblies of the reactors of the undermoderated type whose spectrum is intermediate between a thermal neutron spectrum and a fast neutron spectrum. In the assemblies 3, no control rods nor spectral shift control rods are inserted and the whole lattice consists of rods of recovered plutonium, independently of the components of the assembly required to ensure its rigidity. The whole of the core which can be seen in FIG. 1 therefore consists of a juxtaposition of zones each of which consists of an assembly of the type 1 or 2 or of type 3. A checkboard arrangement such as shown has the advantage that each of the assemblies 3 is surrounded by assemblies of the type 1 and 2 which produce the neutrons required to maintain the nuclear reactions. The assemblies 3 may be produced in the form of subcritical assemblies, that is to say whose neutron activity would be insufficient to maintain the neutron reaction. Inside the assemblies 3, the neutrons produce the fission of some of the nuclei of the odd-numbered isotopes of plutonium, which produces neutrons which are only very slightly moderated by the thin layer of water present between the rods of the assembly 3. These high-energy neutrons convert a part of the non-fissile plutonium into fissile plutonium, with the result that the latter is not degraded during the use of the reactor. A recycling of this plutonium can therefore be envisaged as for the assemblies containing uranium oxide. The core shown in FIG. 1 comprises 236 assemblies of types 1 and 2, namely 163 assemblies of the spectral shift type receiving only rods of enriched uranium and 73 assemblies receiving both rods of enriched uranium and reactor control clusters. This core comprises, inserted among these 236 assemblies 1 and 2, 90 assemblies of the type 3 which are undermoderated and contain plutonium. These 90 assemblies 3 contain an insufficient quantity of fissile material to produce neutron criticality by themselves, and they are therefore called sub-critical. The assemblies 1 and 2 which act as the neutron source for the assemblies 3 do not require a high initial enrichment since the spectral shift control rods permit the reactor to be operated with neutrons of an increased energy during the first part of the life of the reactor core. The core of a pressurized water nuclear reactor such as shown in FIG. 1 makes it possible to obtain a saving of fissile material of 30% relative to a fissile load containing only uranium, by virtue of the 90 assemblies containing rods of recycled plutonium. The fact that the assemblies containing plutonium are arranged checkboard fashion between the zones formed by the spectral shift control assemblies permits an additional hardening of the neutron spectrum relative to that obtained solely by the undermoderation in the assemblies 3 and therefore an increased production of fissile material which permits an additional gain of the order of 20%. However, the invention is not limited to the embodiment which has been described; on the contrary, it comprises all the alternative forms. Thus, the assemblies forming the first group of the core zones which are produced in a heterogeneous form could consist of conventional assemblies of a pressurized water nuclear reactor which are not intended to receive spectral shift control rods. However, in this case it is necessary to employ assemblies having a high initial enrichment so that they can fulfill their function as a source for the assemblies containing plutonium. This presents disadvantages if it is intended to use the fuel with high burn-up ratios. The assemblies forming the core can have a cross-section which is different from a hexagonal section, for example a square section, as is current practise for the assemblies forming the cores in pressurized water nuclear reactors. The zones of the first group containing uranium can consist of a single assembly, of several assemblies or even of a part of an assembly containing both uranium oxide rods and plutonium rods. In all these cases, however, the zones of the second group containing plutonium must be distributed between the zones of the first group containing uranium oxide, to permit a satisfactory neutron operation of the core. These zones must also have transverse dimensions which are sufficiently small to ensure a good neutron operation. Finally, the invention applies to all the watercooled nuclear reactors whose core consists of a juxtaposition of clusters of parallel fuel elements.
	description	The present invention mainly relates to a device for measuring physical quantities of nuclear material, more particularly a device for determining the chemical or physical properties of nuclear materials by resorting to electromagnetic radiation or particles to induce through activation a secondary neutron emission. The present invention also relates to a method of employing such a device. For example, for uranium (U), plutonium (Pu) and americium (Am), the physical quantities of quantitative type may be the masses, the spontaneous neutron emissions and induced neutron emissions, and of qualitative type, the multiplicity of spontaneous neutron emissions, the multiplicity of induced neutron emissions, the fissile nature of the materials and their isotopic composition. When the nuclear materials are irradiating and/or contaminating, it is necessary respectively to use screens and/or to ensure their confinement to guarantee the protection of the personnel. Nuclear installations thus comprise shielded cells in which the nuclear materials are processed or stored. The shielded cells are constituted of one or more sealed enclosures called caissons. The caisson or caissons is (are) surrounded by a radiological shielding also described as biological shielding. The shielded cells are equipped with devices enabling the bringing together of transportable shielded containers in order to introduce or evacuate the nuclear materials while at the same time also ensuring the continuity of the protection of the personnel against irradiation and contamination. It is necessary in the context of their processing or upon their evacuation to measure these nuclear materials. The one who requests these measurements may be the operator of the nuclear installation, but also external authorities such as the IAEA within the context of its control missions. To carry out these measurements, these nuclear materials ordinarily have to be isolated. In a known manner, the measurements to be performed on the nuclear materials are carried out at a distance from the shielded cells. To do this, the nuclear materials are extracted from the cell, they are isolated in a shielded container brought up against the shielded cell, then they are transferred to an installation dedicated to carrying out the measurements. Yet, for regulatory and safety reasons, the nuclear material may only be evacuated from the shielded cell if it meets certain specifications, of which the quantity of fissile material. Yet, in the installations in place, no means exist to carry out this measurement in situ which makes it possible to guarantee that these specifications are met. Within a context of derogatory procedures, the evacuation of the nuclear material may be carried out, but at the price of numerous, complex, long and costly operations which present risks. Indeed, during the transport of the nuclear material, an accident could lead to a pollution of the exterior environment. A device enabling the measurement of the dose rate of the nuclear material in a container is known from document FR 2 654 219, the device being brought up against the shielded cell. This device comprises a transportation flask, of “Padirac” type, mounted on a transport table. This flask comprises a cylindrical housing containing a transfer container. When the transportation flask is brought up against the outside wall of the shielded cell, a door provided in the wall of the shielded cell is opened, a hatch provided on the transportation flask is also opened. Then by means of a connecting poker introduced via an opening formed in the bottom of the housing of the transportation flask, the transfer container is introduced into the shielded cell, in which it is loaded with nuclear material. The transfer container is then partially reintroduced into the housing of the transportation flask. For the measurement, a dose rate measuring probe is introduced via the orifice through which has been introduced the poker, after its withdrawal. The introduction of this probe into the housing thus prevents the transfer container being able to enter completely inside the transportation flask, and to close the hatch of the transportation flask. This device provides a dose rate measurement, yet this physical quantity cannot be linked in an unequivocal manner to the physical quantities of the material present in the transfer container, without additional hypotheses on its physical-chemical nature. Moreover, the impossibility of being able to close the hatch of the transportation flask and thus to be able to isolate in a sealed manner the nuclear material to be measured from the rest of the shielded cell, hinders the measurement. Indeed, in this case the measured dose rate cannot be attributed exclusively to that of the material contained in the transfer container. It is disclosed in this document that, to avoid the measurements carried out inside the transportation flask being marred by errors resulting from the background noise coming from the shielded cell, it is possible to carry out, prior to the measurement of the dose rate, a measurement of the background noises also carried out by means of the probe introduced via the orifice through which is introduced the connecting poker. This measuring device thus necessitates an additional measurement step, which lengthens the time required to obtain a reliable measurement of the nuclear materials. Moreover, this requires hypotheses to be made, which thus reduces the precision and the accuracy of the measurements. Moreover, the fact of not being able to close the shielded cell imposes, over a certain time, having a reduced isolation of the nuclear material that it contains vis-à-vis the exterior environment. Furthermore, the use of the orifice of the connecting poker for the passage of the probe requires this to be of complex design. Indeed, it comprises a large number of parts, these parts being mechanically linked to each other, which increases all the more the risks of failure. Consequently, an aim of the present invention is to offer a measuring device offering a great ease of transport and use and a high safety of use, making it possible to carry out measurements of nuclear materials contained in several shielded cells. Another aim of the present invention is to offer a device for measuring physical quantities of nuclear materials contained in a shielded cell offering a high precision with regard to the measurements carried out. The previously formulated aims are attained by a measuring device comprising a transportation flask in which is confined the nuclear material to be measured, the flask being brought up against the cell in which is taken the nuclear material to be measured, this device comprising a casing covering the transportation flask, the casing being equipped with neutron detection sensors. The device can be brought up against and retracted from the shielded cell to be able to carry out measurements of nuclear materials contained in different shielded cells. The term brought of against (respectively retracted) signifies that the device is temporarily assembled and coupled (respectively disassembled and uncoupled) to the shielded cell, in a sealed manner, so as to introduce or evacuate nuclear materials in said cell, while at the same time ensuring the continuity of the protection of the personnel against irradiation and contamination. Moreover the device according to the present invention is very easy to dismantle, which enables its transport to different places to carry out measurements of nuclear materials contained in different cells. It is possible to measure physical quantities of the nuclear material placed inside the transportation flask, the housing of the transportation flask being isolated from the shielded cell during the measurement. Furthermore, this device does not necessitate the transport of the nuclear material, it enables a measurement of the physical quantities of this material before its transport, which makes it possible to comply with regulatory requirements. Advantageously, the device comprises a neutron emission module housed in a graphite support on which is placed the flask. The main subject-matter of the present invention is then a device for measuring physical quantities of nuclear material contained in a shielded cell (2), which device can be brought up against said shielded cell (2) and can be retracted therefrom, said device being intended to carry out the measurement in a position in which it is against the shielded cell, comprising a carriage, a support placed on the carriage, a shielded container containing a transfer container intended to store the nuclear material to be measured, said shielded container being placed on the support, the shielded container comprising an opening intended to be aligned with an opening in one wall of the shielded cell giving access to the nuclear material that it contains, in which said measuring device also comprises a casing covering the shielded container and measurement means fastened to said casing. The carriage, the support and the shielded container are advantageously capable of being separated to enable an easy dismantling and an assembly of said device with a view to its transport to another shielded cell and its use with said other shielded cell. Advantageously, the support comprises a housing accommodating a neutron emission or electromagnetic radiation module. The casing and the support form advantageously a caisson surrounding on five sides the shielded container, the sixth open side enabling communication with the shielded cell, this caisson reflecting the neutrons and confining them. The casing comprises, for example, two side walls, a bottom intended to be placed opposite the shielded cell in relation to the shielded container and a roof, said bottom comprising an opening to enable the connection of the shielded container to a poker. For example, two measurement means can be fasten on each side wall on the outside of the casing and two measurement means on the roof on the outside of the casing. The use of two “measurement means” makes it possible to obtain a measurement efficiency greater than the use of a single measurement means. Moreover the arrangement of these means just on the outside of the casing corresponds to the place where the neutron flux to be measured is the strongest. The measurement means each have an axis, the two measurement means per wall of the enclosure are then advantageously placed so as to have their axes parallel, and the measurement means of two different walls are advantageously orthogonal. This arrangement has the advantage of making it possible to acquire signals from which it will be possible to extract information on the localisation of the material in the transfer container, and thus make their measurement more precise. The pairs of measurement means are advantageously centred on the target of the emission module, to improve the measurements. For example, the measurement means comprise several detectors, for example 4 or 7. The casing and/or the support are advantageously made of graphite, graphite having the property of thermalising the flux of neutrons and reflecting this flux. It may be provided to cover the graphite with an anodised aluminium sheet to improve the mechanical strength and to facilitate decontamination if necessary. For example, the graphite is UCAR type purified graphite, with the reference CS 49 H. Advantageously, the measuring device according to the invention comprises a radiological protection covering the assembly formed by the carriage, the shielded container and the casing made of graphite so as to isolate said assembly from the exterior environment. This protection then allows operators to be near to the measuring device. The radiological protection comprises for example two side walls, a bottom and a roof, a first opening being formed in the bottom of the protection for the passage of supply cables and the control of the emission module and measurement means, said first opening is blanked off by a plug, and a second opening for the connection of the poker, said second opening being blanked off by a plug. Advantageously, means of guiding the radiological protection in relation to the assembly while the protection is being put in place around the assembly are provided to avoid damaging the assembly. The subject-matter of the present invention is also a method of assembling the measuring device according to the present invention, comprising the steps: putting in place the carriage, putting in place the support on the carriage, putting in place the shielded container on the support, putting in place the casing, putting in place measurement means on the casing. The method of assembly according to the invention comprises advantageously the step of putting in place the emission module in the support. This method of assembly may also comprise the later step of putting in place the biological protection. Another subject-matter of the present invention is a method of measuring with the measuring device according to the invention, comprising the steps: opening the shielded container, opening the access door inside the shielded cell, bringing the transfer container up against the caisson, withdrawing the plug from the transfer container, putting in place the nuclear material in the transfer container, replacing the plug on the transfer container, replacing the transfer container in the shielded container, closing the access door inside the shielded cell, closing the shielded container, measuring the physical quantities of the nuclear material. Advantageously, this method comprises “emission-measurement” cycles repeated at a frequency of the order to several tens of Hz, the emission being of neutron or electromagnetic type. In FIG. 1 may be seen the measuring device according to the present invention brought up against a shielded cell 2, of which it is desired to measure the nuclear material. The measuring device according to the present invention is intended to carry out measurements of the irradiation rate of any type of object, it may be nuclear material, but it may also be any type of object such as an out of service equipment that could be contained in a shielded cell and that it would be necessary to evacuate. Before its evacuation, the irradiation rate of this out of service equipment needs to be measured so as to check that it is less than the legal threshold for the transport of irradiated objects. If the irradiation rate is compliant, the equipment may be transported, for example in the transportation flask having served for the measurement as will be described below. The measuring device comprises a shielded container 4, intended to contain the nuclear material to be measured and inside of which the measurements will be carried out, a measuring structure 6 surrounding the shielded container 4 and comprising the measurement means, which will be described later, and a moveable carriage 8 enabling the device to be brought up against the shielded cell 2. The shielded cell 2 comprises a cavity 10, in which is stored the nuclear material (not represented), surrounded by a wall 12 forming the shielding. The wall 12 generally comprises a concrete core covered on both its faces with a lead sheet. Moreover, the cell comprises an access 14 to the cavity 10. This access is formed by a passage of cylindrical shape of circular section of axis Y1, and comprises sealed blanking off means formed, in the example represented, of a door 16, of revolving door type, moveable in rotation around a vertical X axis. The shielded container, represented in FIGS. 2 and 6, is of the known type and is for example disclosed in patent application FR 1 515 024. The shielded container is for example the “Padirac” flask type widely used in the nuclear sector. The shielded container, also called transportation flask, is formed by a body 18 delimiting a chamber 20 of cylindrical shape of Y axis and a removable blanking off device 22. The body 18 is for example made of lead covered inside and outside by a steel casing. The blanking off device is for example formed by a door capable of sliding along a direction orthogonal to the Y axis of the chamber 20. Moreover, a transfer container 24 is placed in the chamber 20, the transfer container 24 being able to be blanked off by a plug 26. The transfer container 24 is of cylindrical shape and is received in a tubular canister 28, itself housed in the chamber 20. The tubular canister 28 is capable of being displaced along the Y axis, to make it possible to take out the transfer container. The canister 28 forms a sealed mechanism of transferring the transfer container 24 from the inside of the flask to the outside of the flask, the displacement of this mechanism being controlled by means of a connecting poker 30 placed outside of the flask. Thus, the transfer mechanism forms an additional protection vis-à-vis the nuclear material. The connecting poker 30 is of structure known to those skilled in the art and will not be described in detail. The connecting poker 30 comprises one end intended to hook onto the bottom of the canister 28 to cause its axial displacement along the Y axis by displacement of the poker along the Y axis. In FIG. 1, the connecting poker 30 is in place. The connection to the bottom of the canister 28 is carried out, for example by a rotation of the connecting poker 30 around its axis. The sliding door 22 is mounted in rails formed in the body 18. The sliding motion of the door 22 is obtained by means of an opening key 36 visible in FIGS. 3A and 3B, its structure is also known to those skilled in the art and will not be described in detail. The opening key 36, represented in an isolated manner in FIGS. 3A and 3B, comprises a plate 38 provided with a port 40 of dimensions such that the port 40 enables the passage of the transfer container 24. The opening key 36 also comprises means 41 to maintain the door, these being shifted axially in relation to the port 40. The opening key 36 is mounted on the carriage, the flask is put in place so as to place its door on the means 41. During a sliding motion of the opening key 36 orthogonally to the Y axis, the door 22 slides and the port 40 is placed opposite the free end of the chamber 20. The key 36 also ensures the continuity of the protection against irradiation during the opening of the shielded container. A ring is provided for the handling of the opening key 36. The free end of the chamber 20 is intended to be aligned with the access 14 of the shielded cell. To do this, the Y axis of the chamber is aligned with the Y1 axis of the access 14, so as to form a continuous conduit. The carriage 8 supporting the flask comprises a horizontal shelf 9, forming a moving support for the device and enabling the device to be brought up against the shielded cell 2. Advantageously, rails 11 are provided to guide the carriage and obtain a precise alignment between the flask and the access 14 of the shielded cell, more particularly between the Y axis of the chamber and the Y1 axis of the access 14. Advantageously, the shelf 9 is height adjustable in order to facilitate an alignment between the flask 4 and the access 14. Means 42 for vertically displacing the opening key 36 are provided on the carriage 8. These are advantageously motorised. Vertical means for guiding the opening key 36 are also provided on the carriage, these guiding means are for example two vertical V-shaped slides. The means of displacement of the opening key 36 comprise, for example, two vertical screws connected by a crosspiece driving the key vertically. These screws are actuated by an electric motor through the intermediary of angle transmissions. The electrical box supplying the motor may be mounted on the carriage and the control is, for example, of the portable control box type accessible from the outside of the biological protection. The box is supplied by a cable from a casing implanted on the adjacent wall. Moreover, over-travel stops are provided to limit the movements of the opening key 36. The stopping in the lower position takes place on a mechanical stop provided on the carriage. Advantageously, the end of travel of the key takes place slightly lower to avoid leaving the screws of the means of displacement 42 under quasi permanent load. In the event of failure, it is advantageously provided to be able to operate the means of displacement manually, for example by leaving accessible a free end of the motor shaft, to which a crank may be fastened. The displacement of the carriage 8 may be manual or motorised. In the case of a manual displacement, means of assisting the displacement are advantageously provided for to facilitate the operating of the carriage. These means of assistance are, for example, formed by a ratchet wrench 43 cooperating with hexagonal forms borne by the wheels of the carriage placed on the side the furthest from the cell. The ratchet wrench is manipulated by the operating personnel. Means may also be provided to limit the adherence of the wheels, the adherence being caused in particular by the weight of the flask. The ratchet wrench 43 is represented in dashes in FIG. 1, it is obviously understood that it is used before the putting in place of the protection 60. In the example represented, the device also comprises a support 44 for the flask, formed for example of a parallelepiped made of graphite that participates in the measurement, as will be seen later. The support 44 is for example fastened to the carriage 8 by means of two screws. According to the present invention, the graphite support 44 comprises a housing 48 to receive a neutron emission module 50 (not represented in FIG. 1, represented alone in FIG. 4 and represented in the measuring device in FIG. 5G). The housing 48 is of cylindrical shape of circular section, oriented so that its axis is parallel to the axis of the access 14. The housing 48 is non traversing and its opening opens out into the face of the support opposite to that facing the shielded cell. In the neutron emission module, the “neutrogenic” zone 50.1 is virtually point-shaped and is designated by the term “target”. In addition, the neutrons are emitted “in all directions”. The housing is oriented so that the target 50.1 is centred on the container 24 and on the detection units. The use of graphite as material for the support of the neutron emission module 50 makes it possible to thermalise the neutron flux, in other words to change the energy spectrum of the neutrons emitted by the module, which are for example emitted at 14 MeV, in order to make them pass into the thermal domain. Moreover, graphite has the property of reflecting the neutron flux towards the transfer container. For example, the graphite is UCAR type purified graphite, with the reference CS 49H. It may be provided to protect the accessible faces of the graphite support by an anodised aluminium casing, just as the cavity accommodating the neutron emission module. For example, the upper face is equipped with an anodised aluminium sheet of 10 mm thickness to ensure a distribution of the weight of the flask. Indeed, it is this face that is going to support the flask, in particular by a positioning V. The neutron emission module 50 comprises electrical connections formed by a high voltage cable 51 exiting directly through an opening provided in a biological protection, which will be described later. This cable joins an electrical supply cabinet (not represented) provided outside of the measuring device. The neutron emission module 50 may also comprise short cables connected to a casing fastened to the face of the support made of graphite opposite the cell, and which can be dismantled rapidly, facilitating the dismantling of the device according to the present invention. To carry out the measurements, it is also possible to use to an electromagnetic radiation emission module. In the remainder of the description, the module 50 will be designated “emission module”. The output cables from this casing run, for example, inside the biological protection up to the cable outlet opening. A V-shaped component 52 to maintain the flask is provided on the support 44, the axis of the V being oriented so as to be contained in a vertical plane containing the Y1 axis of the access 14. According to the present invention, the measuring device also comprises a measurement casing 53 surrounding the flask, onto which the neutron detection units are fastened. In the example shown, the casing 53 comprises two side walls (visible in FIG. 7), a bottom 56 orthogonal to the Y axis and a roof 58, made of graphite. The walls 54, 56, 58 are assembled mechanically, for example with screws. The casing comprises advantageously chicanes to minimise radiological leaks, provided at the level of the connection between two walls. In a particular example, the measuring device comprises six neutron detection units 59 fastened to the outside of the side walls and on the roof. The outside faces of the side walls 54 and the roof 58 are provided with fastening systems for the detector units. Advantageously, two detection units are fastened to each face. The “measurement means” each comprise an axis. On a same wall, the axes of the measurement means are parallel. The detection means placed on different walls are advantageously placed so as to have their axes orthogonal. This arrangement makes it possible to acquire signals from which information can be extracted on the localisation of the material in the transfer container 24, and thereby make their measurement more precise. The pairs of detector units 59 are advantageously centred on the target 50.1 of the neutron emission module, as has been explained previously. In the upper part of the casing 53, a ring may be provided for the vertical handling of the casing without dismantling. The position of the prehension point is determined with care to avoid any rotation during handling. In the bottom 56 of the casing 53, an opening 57 enables the connection of an extension of poker 55 on the flask. The graphite of the casing may be identical to that of the support. The support 44 may be made for example of polyethylene, lead, boron, etc. for the implementation of other measurement methods specific to other physical quantities. By way of example, the casing 53 may have a thickness of 100 mm, each face of the casing being coated with anodised aluminium. In a particularly advantageous manner, the support 44 cooperates with the casing 53, so as to form a caisson of parallelepipedal shape, closed on five sides, the sixth side being open and being brought up against the wall of the shielded enclosure. Thus, the transfer container intended to contain the material to be measured is completely surrounded by graphite. As has already been mentioned, graphite has the property of reflecting the neutron flux, this flux is thus sent back to the transfer container, i.e. to the material, which makes it possible to improve the measurements. Moreover, this caisson improves the confinement of the neutrons. In the example represented, the support 44 comprises, in its upper part, a shelf 44.1, extending out towards the rear in relation to the part of the support accommodating the neutron emission module 50, which makes it possible to limit the size of the device. Advantageously, the shelf 44.1 comprises a groove 44.2 housing a lower end of the bottom 56 of the casing 53 which extends out in relation to the side walls, which increases the confinement of the neutrons. Concerning the bodies of the detection units, these are for example made of polyethylene covered with a sheet of cadmium. These detector units are, for example, equipped with four or seven detectors while at the same time offering an identical external size. By way of example, the detection units have the exterior dimensions: 780 mm long, 200 mm wide and 70 mm thick, for a mass of 10 kg. Each detector unit has a connecting cable to the cabinet, this cable passes via a notch 60.1 provided in the protection 60. The routing of the cables avoids that they are damaged during the displacement of the biological protection. The neutron emission module is particularly advantageous because it makes it possible to improve the measurements, but a measuring device comprising detection units without such a module does not go beyond the scope of the present invention. In one embodiment, provision is made in addition to cover the assembly with a radiological protection 60, also known as biological protection. This protection is for example made of polyethylene with 10% boron. The protection 60 entirely covers the casing covering the flask, itself placed on the support 44 fastened to the carriage 8. The protection 60 is, moreover, resting against the wall of the shielded enclosure around the access 14, when the device is in measuring position. The protection 60 comprises two side walls 60.2, a roof 60.4 and a bottom 60.6, assembled mechanically so as to form an assembly all in one piece. Advantageously, the different parts are provided with chicanes to limit radiological leaks, these chicanes are provided at the level of the connection between two walls of the enclosure. The protection 60 is advantageously mounted on wheels cooperating with rails (not represented) to enable a precise and easy bringing together. These rails make it possible to avoid the damage of equipment such as the detector units or the extension of the poker, while the protection is being put in place. The protection 60 may be displaced, like the casing 53, by means of a ratchet wrench 61 cooperating with adapted forms at the level of the wheels. An over-travel detection device may be provided between the protection 60 and the shielded cell 2 in order to signal the putting in place of the protection 60. This detector is advantageously connected to the system for controlling the neutron emission module 50, to bring about the emergency stop of the module 50 in the event of detection of a change of position of the protection 60. Means of securing the protection 60 on the wall of the shielded cell 2 are also provided to avoid any untimely displacement, for example by pins. As already disclosed previously, in the bottom 60.6 of the protection 60, a hatch 63 is also provided in the lower part enabling the connection of the high voltage cable 51 of the neutron emission module 50. The opening 63 can be blanked off with an additional protection component 64 enabling the passage of the cable from the emission module. The component 64 is a plug, in the example represented this is in two parts, which makes it possible to simplify production. The plug 64 is composed of a first part 64A comprising a boring of axis substantially parallel to the ground to enable the passage of the high voltage cable 51 and positioning itself without any means of fixation in the opening 63 and a second part 64B comprising a boring with a quarter circle shape, the upper end of the boring extending in the continuation of the boring of 64A and the lower end of the boring being substantially perpendicular to the ground, said boring enabling the passage of the high voltage cable 51. The half-plug 64B is fastened to the protection 60 by means of screws. The roof 60.4 of the protection 60 is provided on the side of the shielded cell 2 with a notch 68 for the passage for the complimentary key. An undercut on the side also enables the passage of the shaft for the manual control of the opening key. The protection 60 allows operators to remain near to the measuring device by isolating them from the radiations caused by the neutron emission module and by those emitted by the nuclear material contained in the flask 4. The bottom of the protection 60 also comprises an opening 62 for the passage of the poker, aligned with those in the bottom of the casing 53 and the flask 2. By way of example, the thickness of the walls of the protection 60 is of the order of 200 mm. A cabinet (not represented) for electronic equipment is also provided containing: the control module of the neutron emission module, neutron detector amplifiers, a computer for managing the measurement. A device for controlling the putting in place of the radiological protection 60 may also be provided for, this comprising several detectors of the opening of the accesses to the measuring device. Means for warning in an unequivocal manner of the operation of the neutron emission module 50 are also advantageously provided for, for example these are formed by a revolving warning light. The assembly and the putting in place of the measuring device according to the present invention near to a shielded cell will now be described, with the objective of carrying out measurements on the nuclear material that it contains, while referring to FIGS. 5A to 5G. Firstly, the rails 11 are put in place along a direction orthogonal to the wall of the shielded cell 2, in order to ensure the alignment of the flask 4 with the access 14. The carriage 8 is then put in place on the rails by means of lifting and displacement of a crane (FIG. 5A), of the bridge crane type. The opening key 36 is then mounted on the carriage 8 at the level of the means of displacement, again by means of a crane (FIG. 5B). The graphite support is then deposited on the carriage 8, the carriage 8 may be brought closer to the cell before this step (FIG. 5C). In a following step, the V-shaped support is placed on the graphite support 44, then the transportation flask 4 is deposited on the V-shaped support (FIG. 5D). The prehension ring of the key is removed and a biological protection part of same nature and thickness as the biological protection 60 is put in place to blank off the undercut of the upper face of the biological protection. The casing 53 is then put in place around the transportation flask 4, also by means of the crane (FIG. 5E). The carriage 8 may if necessary be displaced in the direction of the cell 2 before putting the casing 53 in place. The detector units 59 are mounted on the casing 53 and the emission module 50 is placed in its housing 48 in the support 44. In a similar manner, the bottom 56 of the casing 53 comprises an opening for the poker 30, provision is made, after assembly of an extension of the poker, to blank off the opening with a plug. During a following step, the assembly thereby formed is completely brought forward against the shielded cell 2 up to its operating position so that the transportation flask 4 is in front of the access 14 of the cell. The displacement of the carriage 8 is carried out by means of the ratchet wrench 43. The position of the carriage 8 is then locked up against the shielded cell 2 (FIG. 5F). FIG. 5G shows the radiological protection in place up against the shielded cell 2, the protection 60 has been displaced by means of the ratchet wrench 61. The protection 60 is then fastened to the wall of the cell 2, for example by means of pins. When the protection 60 is in place, the supply cables of the emission module pass through the opening in the bottom of the protection 60, the opening is blanked off around the cables by means of a plug. Moreover, the extension of the poker passes through the bottom of the protection 60, the poker 30 is then connected to this extension. The measuring device is ready to operate, the different steps of operating the device according to the present invention will now be described. The transfer of the transfer container 24 is carried out in the following manner: The poker 30 is connected to the transportation flask 4, more particularly to the bottom of the canister 28. The complementary key is mounted to open the transportation flask 4, by making the door 22 slide. The revolving door 16 of the shielded cell 2 is pivoted so as to leave the passage free. The transfer container 24 is then introduced into the shielded cell 2. The plug of the transfer container 24 is removed, and the nuclear material is laid down in the transfer container 24. Then, by carrying out the preceding operations in the reverse order, the transfer container 24 is brought back into the transportation flask 4. The revolving door 16 is made to pivot and the door of the flask 4 is closed by lowering the complementary key. The measurement then takes place. Only the measurement units 59 may be used in the case of a passive type measurement, or the neutron emission module may be used before carrying out the measurements to interrogate the nuclear material in the case of an active type measurement. In this latter case, “emission-measurement” cycles are repeated at a frequency of the order of several tens of hertz, the emission being of the neutron or electromagnetic type. This type of measurement forms part of the general knowledge of those skilled in the art, and is in particular disclosed in the document “Active nondestructive assay of nuclear materials NUREG/CR-0602 SAI-MLM-2585 January 1981” and in “Mesure nucléaire non destructive dans le cycle du combustible” (Non destructive nuclear measurement in the fuel cycle) Part 2 BN 3 406 of “Techniques de l'ingénieur”. At the end of the measurement, the measuring device is dismantled by following the assembly steps in the reverse order. After the measurement, the nuclear material may be evacuated by the transportation flask to another zone. The device according to the present invention is modular, its assembly and its dismantling are very easy and may be carried out without tools by personnel without particular skill, other than handling. It makes it possible furthermore to be very easily transported, in the form of separated parts, to different storage sites to carry out control measurements, for example by an international nuclear materials surveillance body. It may be shared between several shielded cells of a same site, and thus avoids having to equip each cell with a measuring device.
	summary
	claims	1. A method of estimating a noise map from reconstructed images, comprising:acquiring data for a predetermined first number of views;grouping the views into two groups with some of the views that are correlated between the two groups, one of the two groups having a predetermined second number of the views, the other one of the two groups having a predetermined third number of the views, either one of the predetermined second number and the predetermined third number being less than the predetermined first number of the views;reconstructing two images from the two groups of the views; and estimating variance based upon the two reconstructed images and a weight. 2. The method of estimating a noise map from reconstructed images according to claim 1 wherein the other one of the predetermined second number and the predetermined third number equals to the predetermined first number of the views. 3. The method of estimating a noise map from reconstructed images according to claim 1 wherein the variance is determined according toVar{F}=n/m−nVar{F−X}where F is a first reconstructed image based upon the predetermined first number m of the views, X is a second reconstructed image based upon the predetermined second number n of the views that is less than the predetermined first number m. 4. A method of estimating a noise map from reconstructed images, comprising:acquiring data for a predetermined first number of views;grouping the views into a predetermined second number of at least two groups with an unequal number of the views that are independent in each of the groups;reconstructing an image for each of the groups; andestimating variance based upon a sum of variance in intermediate images each generated by a difference between all combinations of two of the reconstructed images. 5. The method of estimating a noise map from reconstructed images according to claim 4 wherein the predetermined second number of the groups is at least three. 6. The method of estimating a noise map from reconstructed images according to claim 4 wherein the predetermined second number of the groups is two while the predetermined first number of views is m. 7. The method of estimating a noise map from reconstructed images according to claim 6 wherein the variance is determined according toVar{F}=(m−n)n/m2Var{Y−X}where F is a reconstructed image based upon two reconstructed images X and Y, which are respectively reconstructed from n images and m-n images, the n being smaller than the m. 8. A system for estimating a noise map from reconstructed images, comprising:a scanner for acquiring data for a predetermined first number of views;an image data processor connected to said scanner for grouping the views into two groups with some of the views that are correlated between the two groups, one ofthe two groups having a predetermined second number of the views, the other one of the two groups having a predetermined third number of the views, either one of the predetermined second number and the predetermined third number being less than the predetermined first number of the views;an image reconstructing unit connected to said image data processor for reconstructing two images from the two groups of the views; anda variance estimation unit connected to said image reconstructing unit for estimating variance based upon the two reconstructed images and a weight. 9. The system for estimating a noise map from reconstructed images according to claim 8 wherein the other one of the predetermined second number and the predetermined third number equals to the predetermined first number of the views. 10. The system for estimating a noise map from reconstructed images according to claim 8 wherein the variance is determined according toVar{F}=n/m−nVar{F−X}where F is a first reconstructed image based upon the predetermined first number m of the views, X is a second reconstructed image based upon the predetermined second number n of the views that is less than the predetermined first number m. 11. A system for estimating a noise map from reconstructed images, comprising:a scanner for acquiring data for a predetermined first number of views;an image data processor connected to said scanner for grouping the views into a predetermined second number of at least two groups with an unequal number of the views that are independent in each of the groups;an image reconstructing unit connected to said image data processor for reconstructing an image for each of the groups; anda variance estimation unit connected to said image reconstructing unit for estimating variance based upon a sum of variance in intermediate images each generated by a difference between all combinations of two of the reconstructed images. 12. The system for estimating a noise map from reconstructed images according to claim 11 wherein the predetermined second number of the groups is at least three. 13. The system for estimating a noise map from reconstructed images according to claim 11 wherein the predetermined second number of the groups is two while the predetermined first number of views is m. 14. The system for estimating a noise map from reconstructed images according to claim 13 wherein the variance is determined according toVar{F}=(m−n)n/m2Var{Y−X}where F is a reconstructed image based upon two reconstructed images X and Y, which are respectively reconstructed from n images and m−n images, the n being smaller than the m.
	summary
	description	The present invention relates, in general, to molten glass discharging devices and, more particularly, to a molten glass discharging device which is provided in the bottom of a melting furnace that constitutes a waste vitrification apparatus so that the device can control the melting or cooling of molten materials, thereby preventing glass from adhering to a molten material discharging port of the furnace and easily discharging adhered glass from the furnace. Safe treatment, preservation and management of wastes, particularly, of hazardous wastes, such as radioactive wastes, are very important processes. As an example of the processes of treating, preserving and managing the wastes, waste vitrification that is a process of treating the wastes using glass has been proposed and used, in which radioactive wastes, sludge, contaminated soil, industrial wastes etc. are captured in a glass structure and are prevented from leaking to the surrounding environment, thereby permanently keeping the wastes in isolation. To perform waste vitrification using a waste vitrification apparatus, a glass forming agent and wastes are melted in a melting furnace. Here, volatile components of the wastes can be exhausted through an exhaust treatment process and hazardous materials, such as radioactive atomic species and heavy metals, stay in the furnace for a predetermined lengthy period of time while being heated to form a part of a glass reticular structure, thereby forming a homogeneous molten glass mixture. Thereafter, the molten glass mixture is discharged from the furnace so that the poisonous materials are formed as a vitreous solid. A variety of melting furnaces that are classified according to heating types have been proposed. Of the melting furnaces, a cold crucible induction melter (CCIM) is an induction melting furnace which includes a cylindrical melting chamber that has an insulating material placed between a plurality of metal sectors through which a coolant circulates. Further, a high frequency induction coil is provided at a location outside the melting chamber and supplies electricity so that materials contained in the melting chamber can be melted. The above-mentioned cold crucible induction melter is provided with a molten material discharging part that functions to discharge materials after melting the materials. For example, U.S. Pat. No. 6,620,372 (Date of Patent: Sep. 16, 2003.) and Korean Patent No. 611358 (Date of Patent: Aug. 3, 2006.) disclose molten material discharging devices in which a discharging port is formed through the bottom of a melting chamber and a sliding gate is provided in the discharging port so that a molten material can be discharged through the discharging port by an on/off motion of the sliding gate. As another example, a cylindrical discharging port that extends to a predetermined length is formed in the bottom of a melting furnace, and a heating unit, such as an induction coil, is provided in the cylindrical discharging port so that a molten material can be discharged from the melting furnace. However, this technique is problematic in that it requires a substantial lengthy period of time for cooling the cylindrical discharging port so that it is impossible to control the flow of the material to be discharged. Another problem of the technique resides in that, when glass is adhered to the cylindrical discharging port, it may not be easy to discharge the adhered glass from the furnace. Accordingly, the present invention has been made keeping in mind the above problems occurring in the related art, and is intended to provide a molten glass discharging device, which is installed in a molten material discharging port that is formed in a bottom of a melting furnace so that the device can control the melting or cooling of molten materials that are discharged through the molten material discharging port, thereby preventing glass from adhering to the molten material discharging port and easily discharging adhered glass from the furnace. In an aspect, the present invention provides a molten glass discharging device provided in a bottom of a melting furnace so as to control discharging of a molten material from the melting furnace, the molten glass discharging device including: an induction heating unit having a discharging passage along a discharging port that is formed in the bottom of the melting furnace; an induction coil provided outside the induction heating unit; and a cooling unit supporting the induction heating unit and having a cooling conduit through which a cooling fluid circulates. In the molten glass discharging device of the present invention, the induction heating unit is characterized in that it includes two or more cylindrical heating elements that are symmetrically arranged along the discharging passage. Further, in the molten glass discharging device of the present invention, the cooling unit is characterized in that it includes a pair of cooling units that are symmetrically arranged on opposite lengthwise ends of the induction heating unit so that the cooling units are parallel to each other in directions perpendicular to the induction coil. Further, the molten glass discharging device of the present invention is characterized in that it further includes a magnetic field shielding element provided outside the induction coil so as to realize magnetic field shielding. Further, the magnetic field shielding element may include a ferrite core. Further, the magnetic field shielding element may be provided with a second cooling conduit through which a cooling fluid circulates. As described above, the molten glass discharging device of the present invention includes: an induction heating unit that has a discharging passage along a discharging port which is formed in the bottom of the melting furnace; an induction coil that is provided outside the induction heating unit; and a cooling unit that supports the induction heating unit and has a cooling conduit through which a cooling fluid circulates. The molten glass discharging device can realize repeated discharging of the molten material by induction heating or cooling of the induction heating unit. Further, even when glass is adhered to the discharging port, the device can easily discharge the adhered glass from the furnace so that the device can improve the molten glass discharging efficiency. Description of reference characters of important parts 10: discharging passage110: induction heating unit120: induction coil130: cooling unit131: cooling conduit Hereinbelow, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings. As shown in FIGS. 1 and 2, a molten glass discharging device according to the present invention is provided in the bottom of a melting furnace, and controls the discharging of a molten material from the melting furnace. The molten glass discharging device includes: an induction heating unit 110 that has a discharging passage 10 along a discharging port which is formed in the bottom of the melting furnace; an induction coil 120 that is provided outside the induction heating unit 110; and a cooling unit 130 that supports the induction heating unit 110 and has a cooling conduit through which a cooling fluid circulates. The induction heating unit 110 is an element in which an induced current is induced in a high frequency magnetic field so that heat is generated. To discharge the molten material in a downward direction, the discharging passage 10 is provided in the induction heating unit. In the present invention, a variety of heating conductors, such as a plane-type heating element or a stick-type heating element made of a conductor, may be used as the induction heating unit. However, it is preferred that the induction heating unit be formed by two or more cylindrical heating elements 111 which are symmetrically and horizontally arranged in parallel to each other along the discharging passage 10. As shown in FIG. 2, two groups of cylindrical heating elements are symmetrically arranged, in which three cylindrical heating elements are arranged in each side in such a way that one is arranged over another. The discharging passage 10 through which the molten material (molten glass) is discharged is formed between the two cylindrical heating element groups 111 and 112. Here, it should be understood that the number of cylindrical heating elements may be increased or reduced. The induction heating unit 110 is induction-heated by the induction coil that is provided outside the induction heating unit so that the induction heating unit generates high-temperature heat. Here, the induction heating unit may be formed using an ultrahigh temperature heating material, such as MoSi2, iridium and platinum metal. Reference numeral 111 denotes an induced current supply line that is connected to the induction coil 120 and supplies electricity. The induction coil 120 may be formed using a high frequency coil that generates a high-frequency wave. Here, two induction coils are symmetrically arranged at opposite locations outside the induction heating unit 110. It is preferred that the induction coils be arranged in such a way that the magnetic fluxes thereof do not interlink with the magnetic flux of a main induction coil that is installed in the cold crucible induction melting furnace. To realize this object, the induction coils may be arranged in parallel to a molten material discharging direction in which the molten material is discharged from the cold crucible induction melting furnace. The cooling unit 130 supports the induction heating unit 110 and is provided with the cooling conduit therein for realizing the circulation of the cooling fluid. As shown in FIG. 2, the cooling unit 130 has a square plate shape and is provided with the cooling conduit therein so that the cooling fluid can circulate. Here, two cooling units 130 are symmetrically arranged on opposite lengthwise ends of the induction heating unit 110 so that the cooling units can firmly support the induction heating unit 110 in directions perpendicular to the induction coils 120. Each cooling unit 130 is connected to an outside circulation system by a first pipe 131 so that the cooling fluid can circulate through the cooling unit. In the present invention, a magnetic field shielding element 140 may be provided outside each induction coil 120 so as to realize magnetic field shielding. To efficiently realize the magnetic field shielding, a ferrite core may be used as the magnetic field shielding element. Here, the magnetic field shielding element 140 may be placed closely outside each induction coil 120 so that the magnetic field shielding element 140 can cover the magnetic flux of the main induction coil that is provided in the cold crucible induction melting furnace so as to heat the interior of the furnace, and can shield surrounding metal materials from the magnetic flux. Further, the magnetic field shielding element 140 may be provided with a second cooling conduit so that a cooling fluid can circulate through the second cooling conduit and can restrict heating of the magnetic field shielding element. The cooling fluid that flows through the above-mentioned second cooling conduit may be supplied by an additional cooling fluid circulation system that is different from the circulation system for supplying a cooling fluid to the cooling unit 130. However, as shown in FIG. 1, a second cooling conduit 141 that is connected to the cooling unit 130 through a second pipe 132 may be arranged at a location close to the magnetic field shielding element 140 so that a cooling fluid can be supplied both to the cooling unit and to the second cooling conduit by one cooling fluid circulation system. The above-mentioned molten glass discharging device of the present invention is installed in the bottom of the cold crucible induction melting furnace in such a way that the discharging passage 10 of the induction heating unit 110 can be aligned with a discharging port (not shown) of the melting furnace. Thereafter, an induced current is supplied from the outside through the induced current supply line 113 so that a high frequency wave is generated in each induction coil 120. The high frequency current that has been applied to the induction coils 120 induces an induced current to the induction heating unit 110 that is placed between the induction coils 120 so that the induction heating unit 110 can generate heat. Accordingly, solid glass that is placed around the discharging port of the bottom of the cold crucible induction melting furnace is melted and the molten material is discharged from the cold crucible induction melting furnace through the discharging passage 10. When the molten material is completely discharged from the cold crucible induction melting furnace or when it is required to stop the discharging of the molten material, the electricity supply to the induction coils 120 is stopped and the cooling fluid is supplied to the cooling units 130, thereby cooling the molten material in the furnace. When the molten material is cooled and becomes solidified, the solidified material closes the discharging port of the cold crucible induction melting furnace and stops the discharging of the material. The above-mentioned molten glass discharging device of the present invention is advantageous in that electricity is supplied to the induction coil and the molten glass can be easily discharged from the cold crucible induction melting furnace. Particularly, even when glass is adhered to the discharging port of the bottom of the cold crucible induction melting furnace, the adhered glass can be easily discharged from the furnace by heat of a heating element. Further, it is possible to control the cooling fluid that is supplied to the cooling unit which supports the induction heating unit so that the present invention can easily control the discharging of the molten material. Although the embodiments of the present invention have been disclosed for illustrative purposes, those skilled in the art will appreciate that the scope and spirit of the invention are not limited to the accompanying drawings or to the embodiments.
	claims	1. A method for controlling charged particle energy, comprising the steps of:providing circulating charged particles traversing a circulation beam path of a synchrotron, said circulation beam path comprising a pathlength;applying a radio-frequency across a first pair of blades to convert the circulating charged particles to oscillating circulating charged particles, said radio-frequency comprising a frequency time period, said frequency time period in phase with the oscillating charged particles passing between said first pair of blades in the circulation beam path;determining a pre-extraction energy of the oscillating circulating charged particles, related to a velocity of the oscillating circulating charged particles, using said pathlength and said frequency time period;said step of applying the radio-frequency transmitting the oscillating circulating charged particles through an extraction material with a resultant energy loss to form a reduced energy charged particle beam;applying at least five hundred volts across a second pair of blades, wherein said second pair of blades redirects the reduced energy charged particle beam to a deflector and out of said synchrotron yielding an extracted charged particle beam; andcalculating energy of the extracted charged particle beam via reduction of the pre-extraction energy of the oscillating charged particles by the energy loss. 2. The method of claim 1, further comprising the step of:a controller controlling an accelerator in said synchrotron and the frequency time period of the radio-frequency to yield an energy of the extracted charged particle beam matching requirements of a tumor treatment plan as a function of time. 3. The method of claim 2, said time period of the radio-frequency comprising an integer multiple of an interval time of the oscillating charged particles passing between said first pair of extraction blades. 4. The method of claim 3, said integer multiple comprising an integer greater than one. 5. The method of claim 3, further comprising the step of:said controller controlling an amplitude of the radio-frequency, said amplitude correlated with a number of the oscillating circulating charged particles transmitting through said extraction material, wherein an intensity of the extracted charged particle beam is proportional to the number of oscillating circulating charged particles transmitting through said extraction material. 6. The method of claim 3, said step of applying the radio-frequency further comprising the step of:controlling an intensity of the circulating charged particles striking the extraction material via controlling an amplitude of the radio-frequency. 7. The method of claim 5, further comprising the step ofsaid controller controlling the radio-frequency in combination with x/y-pencil beam scanning of a tumor of the patient using the extracted charged particles. 8. The method of claim 7, further comprising the step of:said controller controlling timing of application of the radio-frequency to coordinate with patient re-positioning. 9. The method of claim 8, the circulating charged particles comprising positively charged particles. 10. The method of claim 9, said oscillating circulating charged particles comprising betatron oscillating circulating charged particles. 11. The method of claim 1, further comprising the step of:calculating the energy loss using: density of the extraction material and pathlength of the oscillating circulating charged particles through said extraction material. 12. The method of claim 1, further comprising the step of:determining the energy loss using a calibration model. 13. A method for controlling an energy of an extracted charged particle beam, comprising the steps of:using a synchrotron to circulate charged particles along a circulation beam path, said circulation beam path comprising a pathlength;a controller receiving a cancer treatment plan comprising a requested beam energy;said controller controlling a peak-to-peak time period of a radio-frequency applied across the circulation beam path of said synchrotron, said peak-to-peak time period comprising a periodic time equal to an integer multiple of a time period of circulation of the charged particles along the circulation beam path;said controller redirecting the charged particles through an extraction material resultant in an energy loss and the charged particles traversing an extraction path;calculating an energy of the charged particles at a time of extraction using the pathlength and the peak-to-peak time period; andreducing the energy of the charged particles by the energy loss to yield the energy of the extracted charged particle beam.
	description	The present invention relates generally to using existing emissions to obtain electric energy. Energy conservation and use are hotly discussed topics. Traditionally, electric energy has been transformed, for example, from heat, water, wind, coal, and manmade chemical reactions. Such resources are currently plentiful, however, many must be resourced and replenished for the continued obtainment of electric energy. Consequently, scientists have looked elsewhere for additional sources of electric energy, especially sources which may be readily converted and in a clean fashion, or, if possible, recycling used resources. Various battery types are available in the current market. Some may use an energy source which provides energy from a beta voltaic effect. Beta decay of electrically charged particles is used to provide energy. A beta decay is electrically charged particle expelled from a nucleus. A moving charged particle, such as beta decay, yields a magnetic field. Energy is stored in the magnetic field. When the moving charged particle is absorbed, for example, the magnetic field essentially collapses and produces an electromagnetic field (EMF). The energy released from this event is very large. Such is referred to as the beta voltaic effect. In embodiments of the present invention, this effect is utilized as an energy source for a contained energy device such as a battery. For example, in an impedance/capacitor/resistance (“LCR”) resonant tank circuit system, from energy of a beta voltaic effect, the LCR tank circuit oscillates at a self-resonating frequency. The energy is then removed through a high-quality transformer impedance in the circuit, thus ultimately providing energy from beta decay. Unfortunately, the LCR system requires the use of various components which can fail overtime, long before the energy source is depleted. This then can lead to a waste of useful energy sources, as well as of other robust components of the battery system such as, for example, the protective housing. Some attempts at using nuclear sources were based on thermo-electric generators, providing additional resource waste. Accordingly, there exists a need for such additional sources and methods for energy conversion. Further, there exists a need for methods which provide for a recharging of energy sources. Further, there exists a need for systems which provide for longer lasting components, or redundancy in components, for long-lasting energy sources. The present invention provides a system and a method for safe and proper use of materials for transforming into electric energy. The present invention provides a system and a method for safe and proper storage of materials for transforming into electric energy. The present invention provides for a system and a method for recharging a power source for a battery cell or the like. The present invention provides for a system and a method for self-recharging of a power source for a battery cell or the like. Embodiments of the present invention provide for a method and system for the production of a self charging electric cell with a long shelf life. For example, Strontium-90 (Sr-90) radionuclide is a nuclear byproduct or waste product that emits beta electrons with a half-life of 28.8 years. In embodiments of the present invention, the emitted electrons can be applied efficiently in generating electricity. For example, the emitted electrons can be applied into a lithium ion or other cell needing electrons for recharging purposes. For example, the emitted electrons can be applied to ionizing water to supply hydrogen molecules to a nickel-hydrogen or other cell needing hydrogen molecules. For example, the emitted electrons can be converted directly into electric energy for subsequent use. Embodiments of the present invention provide for portable containment of an essentially self-charging battery cell. Embodiments of the present invention can be used to provide stored energy for use during times of extra consumption needs. Embodiments of the present invention provide for a relatively inexpensive and efficient provision of stored energy. Embodiments of the present invention provide a method and system for a self-charging battery cell, having a Strontium-90 source, the Strontium-90 source having a beta emission. A sensor device is activated by the beta emission. The sensor device converts an intake from the beta emission into electric energy. The electric energy generated by the sensor device can be in the form of electric current, electric voltage, and/or electric power. In embodiments of the present invention, the sensor device is at least one of a semiconductor light sensor, a thermoelectric heat sensor, a photodiode, PMT, and/or a photocell. Embodiments of the present invention provide a method and system for a self-charging battery cell which is usable in a Lithium ion cell. Embodiments of the present invention provide a method and system for a battery cell which is configured to restore a Lithium ion cell to full charge using the generated electric energy from the Strontium-90 source. Embodiments of the present invention are used in a plurality of Lithium ion cells. In embodiments of the present invention, the radionuclide Sr-90 is used. The half-life of Sr-90 has been determined to be 28.8 years. The decay scheme of Sr-90 is: Sr-90→Yitrium-90→Zirconium-90 (stable). The beta emissions from the first and second steps in the decay are 0.546 MeV and 2.28 MeV, respectively. Embodiments of the present invention provide for a method and system for a battery cell having a Strontium-90 source. The beta emission of a Strontium-90 source is converted into light using a scintillation device. The light then activates a sensor—whether by the frequency of the light, by the heat of the light, or by another property of the light which can be sensed by a sensor. The sensor then converts the light into at least one of electric current, voltage, energy, and power. Such electricity in its generated form can then be used to power small or large electricity-needing devices, as designed. In embodiments of the present invention, the scintillation device is at least one of a scintillation crystal, an organic scintillation crystal, and an inorganic scintillation crystal. In embodiments of the present invention a scintillation device is used to convert electrons from a beta emission of a Strontium-90 source into one or more one flashes of light. In embodiments of the present invention, at least one scintillation device is disposed near at least one Strontium-90 source. In embodiments of the present invention, the scintillation device is disposed near enough to the Strontium-90 source that the scintillation device can intake electron(s) from the at least one beta emission from the Strontium-90 source and convert the at least one beta emission into light. In embodiments of the present invention, at least one sensor device is disposed near the at least one scintillation device. In embodiments of the present invention, the sensor device is disposed near enough to the scintillation device so that the sensor device can be activated by the light emitted by the scintillation device. In embodiments of the present invention, the sensor device converts the received light into electric energy. In embodiments of the present invention, the scintillation device is at least one of a scintillation crystal, an organic scintillation crystal, an inorganic scintillation crystal. In embodiments of the present invention, one or more scintillators are used. A scintillator is a material which, when excited by ionizing radiation, exhibits luminescence. For example, when such luminescent material is struck by an incoming ionizing radiation particle, the luminescent material absorbs the energy of the of the striking particle, and then emits that absorbed energy as light. For example, the light is a small flash of light in the visible range. In addition or in the alternative, the light is in the nonvisible range. Generally, scintillators have a high efficiency for converting energy, as well as a short rise time which allows it to be used in fast timing applications. Example scintillators include: organic scintillators (e.g., aromatic hydrocarbon compounds containing linked or condensed bezene ring structures), pure crystals (e.g., anthacene, stilbene, and naphthalene), organic liquids (e.g., organic scintillator in an organic solvent), plastic (e.g., polymerized solution of organic scintillators), in organic crystals (e.g., alkali metal halides with a small activator impurity (e.g., thallium)), and gaseous scintillators (e.g., nitrogen and the noble gases such as helium, argon, krypton, etc.). In embodiments of the present invention, various devices can be used to receive, convert, and/or use the emitted light from a device such as a scintillator. For example, a photomultiplier tube (PMT), photocell, and/or photodiode can be used. A photomultiplier tube effectively absorbs the emitted light, and emits it in the form of electrons. The electrons may then result in an electrical pulse. In embodiments of the present invention, the Strontium-90 is essentially sandwiched between at least two scintillation devices. In embodiments of the present invention, at least one sensor device is disposed adjacent or near to each of the at least two scintillation devices. In embodiments of the present invention, a Strontium-90 source is surrounded by at least one scintillation device which forms an effective cylindrical wall around the Strontium-90 source. In a further embodiment, at least one sensor device is disposed outside the effective cylindrical wall. Embodiments of the present invention provide for a battery cell housed in a compact sealed container. Embodiments of the present invention wherein the battery cell is used to at least one of recharge existing battery cells and/or serve as the battery cell to provide electric energy for an existing device or electronic device. Embodiments of the present invention provide for a battery cell method and system having a Strontium-90 source, the Strontium-90 source having a beta emission, and exposing at least one water molecule H2O to the Strontium-90 beta emission. In embodiments, the Strontium-90 beta emission effects a production of hydrogen from the at least one water molecule. Embodiments of the present invention provide for charging a nickel-hydrogen battery cell with the production of hydrogen. Embodiments of the present invention provide for a longlife, inexpensive, reliable, relatively easy to make, and relatively easy to use system and method. Strontium-90 is a product or waste product of a nuclear reaction, and is converted into a useful source from which electric current/voltage can be obtained in embodiments of the present invention. It is appreciated that in the embodiments disclosed herein, each of the features such as a sensor or sensor device, a scintillation device, and a source of the beta emission of electrons can each/some/all be solo devices used within a system or method, or can be a plurality of one or more devices used within a system or method. It is also understood that other and/or additional sources can be used. For example, a source that behaves in a similar useful manner as Strontium-90 can be used in conjunction with or in place of Strontium-90. The following description provides specific details for a thorough understanding of, and enabling description for, various embodiments of the technology. One skilled in the art will understand that the technology may be practiced without many of these details. In some instances, well-known structures and functions have not been shown or described in detail to avoid unnecessarily obscuring the description of the embodiments of the technology. It is intended that the terminology used in the description presented below be interpreted in its broadest reasonable manner, even though it is being used in conjunction with a detailed description of certain embodiments of the technology. Although certain terms may be emphasized below, any terminology intended to be interpreted in any restricted manner will be overtly and specifically defined as such in this Detailed Description section. FIG. 1A illustrates a diagram of an example battery cell system 100 according to available systems. Specifically, the diagram shows a discharging battery cell system which indicates the basic functionality of the resulting flow of electrons for use. FIG. 1B illustrates a diagram of an example battery cell system 110 according to available systems. Specifically, the diagram shows a recharging battery cell system which indicates the basic functionality of the resulting flow of electrons. In embodiments of the present invention, Sr-90 (or a source having such emissions) provides beta emissions which can be used to produce hydrogen molecules for a nickel-hydrogen battery cell system. In an embodiment, water or other hydrogen compound is exposed to the beta emissions of Sr-90. Those beta emissions have an ionizing effect on the hydrogen compound, thus releasing the bond between at least the hydrogen and the oxygen in H2O, for example. That is:H2O→H+OH−The hydrogen molecule is then provided by available means in the battery cell system to re-supply the hydrogen source, thus, effectively in-part recharging the battery. For a nickel-hydrogen battery cell (Ni—H2), during normal operation, the reaction of the nickel-hydrogen cell is as follows: Thus, embodiments of the present invention can be used to produce hydrogen to the hydrogen electrode. Various embodiments are contemplated regarding how to dispose of the remnant hydrogen oxide, for example, it could be released in its gaseous state. Or, it could be combined with other remnants to form water molecules or other molecules to provide more hydrogen mining efforts for use in recharging the nickel-hydrogen battery cell, or for other uses such as other battery cell systems, or for other purposes needing hydrogen molecules. Embodiments of the present invention can be used in alternative ways/methods. For example, the beta emissions of Sr-90 can be used to produce “recharging” electrons for a lithium ion cell. For example, the reaction of a lithium-ion cell is as follows: In such embodiments, the Sr-90 emits a beta emission. The beta emission includes electrons which can be directly used to recharge the electrons used in the lithium ion battery cell. Such process can be used with other battery cells, e.g., ZnCl2 cell, nickel-cadmium cell, which require electrons for recharging. In embodiments of the present invention, since the half-life of Sr-90 is about 28.8 years, that provides an effective self-charging battery—at least for those parts chargeable by the Sr-90 as described herein—for several years. In embodiments of the present invention, the beta emission of the Sr-90 requires light shielding. Thus, the inclusion of the Sr-90 source in a compact sealed container assists this requirement. In embodiments of the present invention, the Sr-90 battery cell embodiments of the present invention can be housed in a compact sealed container. For embodiments of the present invention, radiation safety regulations are adhered to in the use of proper materials to house and/or store nuclear products such as Sr-90. For example, the Radiation Safety and Security may control the distribution and disposal of the battery cell containing Sr-90 or other energy source having similar properties by registration. FIG. 2 shows a diagram of an example battery cell housed in a sealed container 200. For example, inside a battery cell housing 208, there is cathode material 206 and anode material 204. For each, respectively, there is a current collector: cathode current collector 207 and anode current collector 203. In the battery cell housing 208, there is a separator 205 to keep separate the cathode material 206 and the anode material 204. The electrolyte 201 is the source for the energy, when activated, of the battery cell. For safety purposes, there are container seals 202 within the battery cell housing 208 to keep the various materials from creeping unnecessarily into each other and outside the battery cell housing 208. In embodiments, a battery housing is used which protects against leakage of the specific materials to be placed inside. For example, if Sr-90 is used, the battery housing or container is one which prevents radiation leakage. In embodiments, the battery housing is provided with a registration number so that the battery and contents are not misused. The registration number is provided to a safety committee or team which keeps track of the Sr-90 source batteries. In embodiments, the Sr-90 source is pure. In an embodiment, the Sr-90 source is combined with another material to make it easier to use and/or manipulate. For example, the Sr-90 source is provided in an alloy with silver or another metal. By combining Sr-90 with one or more metals or other elements, it can make the manipulation and use of the Sr-90 easier. In embodiments, the manipulation and handling of the Sr-90 can be effected by a machine. FIG. 3 shows a flow chart of an embodiment of the present invention. In FIG. 3, a high-level view of the charging/recharging process is shown. In step 301, the source Sr-90 electrons are provided via the Sr-90 beta emissions. In step 302, a photocell, for example, is activated by the Sr-90 electrons. The photocell or other applicable device for accepting the beta emissions and translating that into a form that can be transmitted or used is usable. In the present case of the photocell, the photocell is activated by the Sr-90 electrons, and in response electric voltage or current is provided 303. Such electric voltage or current can then be used to power a device or machine 304. Alternatively, such electric voltage or current can be combined with other voltage or current sources. FIG. 4 shows a side view of an embodiment of the present invention. In FIG. 4, a source, i.e., Sr-90, 401 is shown situated between photocells 402, 403. The photocells 402, 403 can be one elongated photocell which wraps around the source. Alternatively, the photocells 402, 403 can be more than one photocell. Alternatively, the photocells 402, 403 is a plurality and/or grid of photocells. FIG. 5 shows a cylindrical-shaped example of an embodiment of the present invention. In FIG. 5, a source 501, e.g., Sr-90, is surrounded by one or more photodiodes 502. For example, the one or more photodiodes 502 is a grid of photodiodes. Alternatively, the grid of photo diodes is usable in different shapes which cover some or all of the available space of the Sr-90 source. In an embodiment, the photodiode(s) are placed as near to the Sr-90 source as possible so that the flow of electrons is sufficiently encouraged towards the photodiodes. FIG. 6 shows a flow chart of an embodiment of the present invention. In FIG. 6, the source Sr-90 electrons or beta emission are provided 601. A scintillator or other such device receives 602 the electrons from the source. The electrons excite or activate the scintillator or other such device and consequently, emit or exhibit luminescence or light. This light then activates a photodiode or such device 603 into producing electric voltage and/or current 604. The electric voltage and/or current can then be used to activate a machine or device, or be combined with other power sources, or be put to use to charge and/or activate an electrolyte or battery cell 605. FIG. 7 shows a side view of an embodiment of the present invention. In FIG. 7, an energy source 701, e.g., Sr-90, is shown disposed between one or more luminescent materials 703, 704. Such luminescent material(s) 703, 704 can be one or more type of scintillators. For example, an organic and an inorganic scintillators can be used. Or, for example, one or more inorganic scintillators can be used. A discussion concerning some of the available scintillators is included herein and can be used in embodiments of the present invention. Adjacent or near to the luminescent material 703, 704 is one or more photodiodes 702, 705. The one or more photodiodes 702, 705 is disposed close enough to the luminescent material in order to receive the light sufficiently in order to transform the light into electric voltage or current. In embodiments, a photocell or PMT or other such device that can intake luminescence or light and transform that into electric current/voltage/energy, can be used in place of or in addition to the photodiode. FIG. 8 shows a cylindrical-shaped example of an embodiment of the present invention. In FIG. 8, an energy source 801, e.g., Sr-90, is surrounded completely or in part by one or more luminescent materials 802. In embodiments, the one or more luminescent materials 802 is one or more types of scintillators. The one or more luminescent materials 802 is surrounded completely or in part by one or more light/heat sensor devices, e.g., a photodiode, photocell, PMT, etc. In embodiments of the present invention, the volume of Sr-90 to be used in a specific battery depends upon the type and use of the battery. For example, in batteries for large machinery, a larger amount of Sr-90 may be used—relative to that used in a battery for a small handheld machine—in order to increase the amount of beta emissions which are detected by the luminescent material and/or sensors for the generation of electric current and/or voltage. Accordingly, for any specific situation, the volume of Sr-90 can be determined in a calculation of energy needs, battery housing size, number of sensors/detectors, etc. It should be understood that there exist implementations of other variations and modifications of the invention and its various aspects, as may be readily apparent to those of ordinary skill in the art, and that the invention is not limited by specific embodiments described herein. Features and embodiments described above may be combined with and/or without each other. It is therefore contemplated to cover any and all modifications, variations, combinations or equivalents that fall within the scope of the basic underlying principals disclosed and claimed herein.
	abstract	A radiation protection device is disclosed in the embodiment of the present invention. The radiation protection device is used for a system which is configured to perform safety inspection of a cargo or a vehicle by a ray. The radiation protection device comprising: at least one container, and a radiation protection part disposed within the container. The radiation protection material may comprise at least one of concrete, sandstone, and water, or the radiation protection part may comprise a steel-lead protection wall or a concrete protection wall. With the radiation protection device according to the embodiment of the present invention, after the container is transported to the site, it can be directly put in place to be capable of shielding rays without needing operation or with only simple operation. The amount of on-site work, construction time, and construction cost are low.
042658616	abstract	A method is described for reducing the volume of radioactive waste produced during the solution mining of uranium and for recovering uranium from it. The recovery leach, which contains uranium in solution and is supersaturated with calcium carbonate, is treated with bicarbonate and made basic which precipitates calcium carbonate and some of the uranium. The precipitated calcium carbonate is dissolved with acid and the uranium in the solution is removed by extraction or precipitation. The remaining solution is contacted with sulfate ions and barium or strontium ions to precipitate BaSO.sub.4.RaSO.sub.4 or SrSO.sub.4.RaSO.sub.4, the principal radioactive constituent in the solid waste product.
043269176	abstract	A method and apparatus for controlling a nuclear reactor in response to a variable average reactor coolant temperature set point (79) is disclosed. The set point (79) is dependent upon percent of full power load demand. A manually-actuated (85) "droop mode" of control is provided whereby the reactor coolant temperature is allowed to drop below the set point (79) temperature a predetermined amount wherein the control is switched from reactor control rods exclusively to feedwater flow.
	summary
	abstract	The measurement device comprises a real-time measurement-signal acquisition module (25) and means (23, 24) for connecting the cables for picking up the voltage from electrical windings for measuring the movement of the control rods to the acquisition module (25), in order to deliver, to the acquisition module (25), voltage signals corresponding to the voltage induced in the windings while the control rods are being dropped. The signal acquisition module (25) is thus permanently connected to the voltage-signal pickup cables (29) and the signals relating to the set of nuclear reactor control rods may be recorded simultaneously. Means (26, 27) for using the voltage signals delivered by the acquisition system (25) allow the drop times of the control rods to be determined.
047626712	description	DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the invention will now be described with reference to the drawings. In FIG. 3 an injection device main body 40 is suspended within the downcomer 8 by means of a wire rope 52 that hangs from above a refuelling platform 41 provided above the RPV 1. Reference numeral 43 indicates a suspension mechanism (for example a winch). The injection device main body 40 is constructed as shown in FIG. 4 and FIG. 5. Reference numeral 44 in the drawings indicates a casing. This casing 44 is shaped approximately as a rectangular box, whose face 45 facing the RPV 1 matches the internal shape of the RPV 1 and which has a longitudinal groove 46 formed in the middle thereof and extending over the entire height of the face 45. This groove 46 corresponds in position to a sample mounting bracket 20 that is mounted on the RPV 1. The groove 46 enables the injection device main body 40 to be lowered without interferring with this bracket 20. The bottom end of the casing 44 is arcuate so as to match the shape of the upper surface of thermal sleeve 15. Thus, the injection device main body 40 is automatically positioned by seating on the thermal sleeve 15. A pair of slit-shaped injection nozzles 47 and 48 are mounted at positions facing each other on the left and right at the bottom end of casing 44. Water is supplied to the injection nozzles 47 and 48 from a water feed pipe 49 arranged within the casing 44 and connected to the injection nozzles 47 and 48. This water feed pipe 49 is connected to a water feed unit, not shown, disposed on the refuelling platform 41. A plurality of electromagnets 50 are mounted on the face 45 of the casing 44 opposite the RPV 1. The inside surface of the RPV 1 is covered with a lining (not shown) of austenitic stainless steel, which is non-magnetic. This lining is normally about 5 mm thick. It has been thought that since this lining is made of non-magnetic steel, it would be impossible to fix any appliances to it by electromagnetic force. However, from the experimental results of FIG. 6, it was found that since the matrix of the RPV 1 is low alloy steel, a sufficient attractive force for the injection device can be obtained. FIG. 6 shows the results of measuring the attractive force of the electromagnets 50 in the case of an austenitic stainless steel lining (thickness 5 mm) and a low alloy steel RPV matrix. The designations ".phi.90 mm" and ".phi.80 mm" in the figure indicate the diameter of the respective electromagnetic coils. In this embodiment, the attraction between the injection device main body 40 and the RPV 1, due to the electromagnets 50, is sufficient to withstand the reaction produced when high pressure water is introduced from the injection nozzles 47 and 48. As shown in FIG. 5, an underwater television camera 51 and underwater lights 52 are arranged on the injection device main body 40. In fact two underwater lights 52 are provided, one on each side of the underwater television camera 51. The relative positions etc. of the injection device main body 40 and thermal sleeve 15 etc. can be observed using the underwater television camera 51 and the underwater lights 52. As shown in FIG. 4, a pair of touch sensors 53 are mounted at the bottom end of the casing 44. These can be used to ascertain when the injection device main body 40 is seated on the thermal sleeve 15. A further pair of touch sensors 54 are mounted on the surface of the casing 44 facing the RPV 1. These sensors 50 can be used to ascertain when the casing 44 has been attracted onto the RPV 1. As shown in FIG. 7, the injection outlets of the injection nozzles 47 and 48 are in the form of slits running along the length of the aperture formed by the annular gap 17, which extends around the thermal sleeve 15. Alternatively, the injection outlets may consist of a plurality of circular outlets which are arranged in an arcuate row along the length of the aperture formed by the annular gap 17. As shown in FIG. 8, the injection nozzles 47 and 48 are mounted so as to make a positive radial or dip angle of 0.degree. to 45.degree. with respect to a cylindrical plane concentric with the axis of the inlet nozzle 13 and directed toward this axis. The mode of operation of the device constructed as above will now be described. First of all, the injection device main body 40 is lowered from refuelling platform 41 using the wire ropes 42 into a position immediately above the recirculation inlet nozzle 13 into which the high-pressure water is to be introduced. Thus the injection device is suspended between the branch pipes 16 of the jet pumps 12 and the RPV 1. Its position is checked using the underwater television camera 51, the underwater lights 52 being switched on for this purpose. If the device is lowered to the location where the bracket 20 is mounted on the RPV 1, it is adjusted so that the groove 46 of the casing 44 is aligned with the bracket 20. Thus the injection device main body 40 is lowered until it is seated on the thermal sleeve 15. Seating of the injection device main body 40 can be ascertained remotely by means of the touch sensors 53. Current is then passed through the electromagnets 50 to cause the injection device main body 40 to be attracted to the RPV 1. This attraction operation is remotely monitored using the touch sensors 54. High-pressure water is then introduced into the annular gap 17 through the injection nozzles 47 and 48, either to remove accumulations of radioactive substances in this annular gap 17, or to effect forced cooling during IHSI. Different flow configurations within the annular gap 17 result from different mounting positions of the injection nozzles 47 and 48 in the circumferential direction of the recirculation inlet nozzle 13, and these will now be explained with reference to FIG. 9 to FIG. 11. These figures were obtained by experimental observation of the flow configuration in the annular gap 17 of thickness 5 mm in a recirculation inlet nozzle 13 of bore 287 mm. FIG. 9 shows the case wherein the mounting positions of two adjacent nozzles 47 and 48 are spaced by not more than 7.5.degree. from a vertical plane passing through the center axis of recirculation nozzle 13 and wherein both the injection nozzles 47 and 48 are operated simultaneously. In this case, the two jet flows have a cooperative guiding effect on each other which causes the jet flow to penetrate to the furthest recesses of the anular gap. Next, FIG. 10 shows the case wherein the mounting positions of the two adjacent nozzles 47 and 48 are separated so as to be spaced by more than 7.5.degree. from a vertical plane through the center axis, both the injection nozzles 47 and 48 being operated simultaneously. In this case, the two jet flows are dispersed in the central region of the annular gap 17 and bounce off each other, so the jet flow energy is lost, and the jet flows do not reach the most interior region of the annular gap 17. This gives rise to a stagnant region 55 in the most interior portion of annular gap 17. With such a nozzle arrangement, it is therefore more effective to operate the injection nozzles one at a time, rather than operating them both simultaneously. That is, if water is injected from only a single injection nozzle 48, the jet flow can then reach the innermost portion of annular gap 17, as shown in FIG. 11. In the case of cleaning the annular gap 17, since the amount of water delivered by the injection nozzles 47 and 48 can be adjusted remotely, such adjustment can be performed while monitoring the diminution in radiation dosage, and in the case of carrying out IHSI, adjustment can be performed while monitoring the temperature of the recirculation inlet nozzle 13. The amount of water delivered per injection nozzle is suitably 0.2 m.sup.3 /h. A device constituting a further embodiment of this invention for introducing high-pressure water onto the inside surface of a jet pump instrumentation nozzle 22 will now be described with reference to FIG. 12 and FIG. 13. Internal instrumentation piping 60 constituted by a plurality of pipes is arranged in the jet pump instrumentation nozzle 22, forming a narrow gap 61 between the piping 60 and the inside of jet pump instrumentation nozzle 22. An injection device main body 70 for introducing water into this gap 61 has practically the same construction and action as the injection device main body 40 of the previous embodiment. However, since the jet pump instrumentation nozzle 22 is smaller than the recirculation inlet nozzle 13, the casing 71 is smaller, and the bottom end of the casing 71 is formed with bifurcated portions 72 which straddle the entire internal piping 60. In this case, since electromagnets 73 can be provided in both bifurcated portions 72, there is the advantage of improved stability of the coupling between the casing 71 and the inside wall of the RPV 1. The construction of the touch sensor and the injection nozzles, etc. (not shown) is the same as in the previous embodiment. The injection nozzles 47 and 48 can be strings of small circular pores instead of slits. The following advantages are obtained by the embodiments described above. (i) Water can be introduced remotely into the interior of the vessel nozzles (the recirculation inlet nozzle 13 and the jet pump instrumentation nozzle 22) that are in not easily accessible positions at the lower part of the RPV 1. Thanks to the fact that the injection device main body 40 or 70 is accommodated in a casing 44 or 71, having a face 44 or 71 opposite the RPV 1 which is of a shape matching the RPV 1 and having the groove 46, and thanks to the fact that operation can be continually monitored using an underwater camera 51, fitting or removal of the device and introduction of high-pressure water can be performed while being able to realiably prevent interference with reactor structures, particularly the bracket 20. (ii) Since the bottom end of the casing 44 is arcuate and of the same shape as thermal sleeve 15 of the recirculation inlet nozzle 13, or since the bottom end of the casing 71 is bifurcated so that the internal piping 60 of the jet pump instrumentation nozzle 22 can be inserted between the bifurcations, the injection device main body 40 or 70 can be located in position simply by seating the casing 44 or 71 on the thermal sleeve 15 or the internal piping 60. Thus complicated construction or operations for the purpose of locating are entirely unnecessary. (iii) Thanks to the provision of the touch sensors 53 and 54 on the casing 44, the injection device main body 40 can be monitored using these touch senors 53 and 54, so the device can be operated with ease and in a reliable manner. (iv) High-pressure water can be effectively introduced into the annular gap 17 or the gap 61 thanks to the fact the injection outlets of the injection nozzles of 47 and 48 of the present embodiment are slit-shaped or shaped as strings of small pores and are symmetrical from left to right and are set at dip angles of 0.degree. to 45.degree., and thanks to the fact that fluid is injected simultaneously from one or more injection nozzle mounting positions in the circumferential direction of recirculation inlet nozzle 13 or the jet pump instrumentation nozzle 22. (v) The flow amount of high-pressure water can be set to a value of 0.2 m.sup.3 /h or more; water can be introduced while monitoring the cleaning effect or the progress of IHSI; and water can be effectively introduced into the annular gap 17 or into narrow and not easily accessible spaces. (vi) Since fixing of the injection device main body 40 is by means of a simple electromagnet 50 construction, complication of the device and therefore complicated operational procedures can be effectively avoided. Obviously, numerous (additional) modifications and variations of the present invention are possible in light of the above teachings. It is therefore to be understood that within the scope of the appended claims, the invention may be practiced otherwise than as specifically described herein.
052415783	claims	1. A grid alignment system for use in a portable radiographic apparatus for aligning x-ray film with an x-ray source within said portable radiographic apparatus, comprising: a grid cassette, movable relative to said x-ray source, including an x-ray film holding portion, an anti-scatter grid substantially fixed relative to said x-ray film holding portion and positionable between said x-ray film holding portion and said x-ray source, and a reflector element substantially fixed relative to said grid, said reflector element including a reflective surface for reflecting said incident light beam to produce a reflected light beam, and an imaging surface for producing images of said incident light beam and said reflected light beam, said images providing an indication of alignment between said grid cassette and said x-ray source; and a light beam projector substantially fixed relative to said x-ray source, said light-beam projector projecting said incident light beam upon said reflector element to provide said indication of alignment between said grid cassette and said x-ray source. at least one pair of radiopaque markers, a first of said at least one pair of markers being positioned on a first side of said grid, and a second of said at least one pair of markers being positioned on a second side of said grid, said at least one pair of markers being positioned to produce images of said markers on an x-ray film in said film holding portion upon exposure to x-radiation, said marker images being indicative of an amount of angulation alignment error between said x-ray source and said grid cassette. an x-ray source adjustable in orientation to allow the exposure of radiographs of portions of a patient in a plurality of orientations at bedside; a grid cassette including an anti-scatter grid and a film cassette holding portion, said grid cassette being positional relative to said x-ray source to produce radiographs of said patient; a light beam projector substantially fixed relative to said x-ray source, for projecting a light beam toward said grid cassette, said light beam being substantially parallel to a central x-ray beam of said x-ray source; a reflector element, substantially fixed relative to said grid cassette, for receiving said light beam, and for producing an indication of angulation alignment between said grid cassette and said x-ray source, said reflector element including a reflective surface for reflecting said incident light beam to produce a reflected light beam, and an imaging surface for producing images of said incident light beam and said reflected light beam, said images providing said indication of alignment between said grid cassette and said x-ray source. a collimator housing including a collimator light and a collimator image carrying surface which together project a shadow of said collimator image onto said patient and said grid cassette during alignment of said x-ray source and said grid cassette, said collimator image including a focus line which casts a focus indicating shadow on a surface of said grid cassette, coincidence between said light beam and said focus indicating shadow being indicative of location of said grid cassette at a proper focal distance from said x-ray source. 2. The alignment system as recited in claim 1, said reflector element being integrally formed with said grid cassette. 3. The alignment system as recited in claim 1, said reflector element being removably attached to said grid cassette. 4. The alignment system as recited in claim 1, said grid cassette further comprising an integrally formed hand hold. 5. The alignment system as recited in claim 1, said incident light beam forming an incident light line on said reflector element. 6. The alignment system as recited in claim 5, said reflective surface reflecting said incident light line to produce a reflected light line, and said imaging surface producing images of said incident light line and said reflected light line, a distance between said light line images being indicative of alignment between said grid cassette and said x-ray source. 7. The alignment system as recited in claim 5, said incident light line being substantially parallel to a longitudinal dimension of grid lines within a said anti-scatter grid. 8. The alignment system as recited in claim 1, said incident light beam forming an incident light spot on said reflector element. 9. The alignment system as recited in claim 8, said reflective surface reflecting said incident light spot to produce a reflected light spot, and said imaging surface producing images of said incident light spot and said reflected light spot, a distance between said light spot images being indicative of alignment between said grid cassette and said x-ray source. 10. The alignment system as recited in claim 1, said grid cassette further comprising: 11. The alignment system as recited in claim 1, said light beam projector comprising a semiconductor laser. 12. The alignment system as recited in claim 11, said semiconductor laser producing a light beam having a substantially elliptical cross-section, said light beam projector further comprising a cylinder lens for converting said light beam having a substantially elliptical cross-section into a fan-shaped light beam. 13. A portable x-ray apparatus which is sufficiently mobile to be brought to bedside for making radiographs of a patient, comprising: 14. The portable x-ray apparatus as recited in claim 13, further comprising: 15. The portable x-ray apparatus as recited in claim 13, said light beam projector producing an incident light spot upon said reflector element. 16. The portable x-ray apparatus as recited in claim 15, said reflective surface reflecting said incident light spot to produce a reflected light spot, and said imaging surface producing images of said incident light spot and said reflected light spot, a distance between said light spot images being indicative of an angulation alignment error between said x-ray source and said grid cassette. 17. The portable x-ray apparatus as recited in claim 13, said light beam projector producing a substantially fan-shaped light beam which forms an incident light line upon said reflector element. 18. The portable x-ray apparatus as recited in claim 17, said reflective surface reflecting said incident light line to produce a reflected light line, and said imaging surface producing images of said incident light line and said reflected light line, a distance between said light line images being indicative of an angulation alignment error between said x-ray source and said grid cassette. 19. The portable x-ray apparatus as recited in claim 17, said incident light line being substantially parallel to grid lines within said anti-scatter grid.
	summary
	claims	1. A method for precipitating at least one solute in a reactor comprising:a) contacting, in co-current circulation in a reactor,(i) a first liquid phase comprising the at least one solute and(ii) a second liquid phase comprising a solute precipitation reagent, forming a mix comprising precipitate particles of the at least one solute in suspension, and(iii) a third liquid phase forming a dispersing phase for said mix; andb) entraining said mix by the third liquid phase by fluidization, said fluidization comprising putting drops containing said precipitate particles into suspension in an upwards fluid flow, said drops containing said precipitate particles forming a fluidized bed and the upwards fluid flow being composed of the third liquid phase. 2. The method according to claim 1, in which the first liquid phase and the second liquid phase are miscible with each other, while the third liquid phase is immiscible with the mix formed from the first liquid phase and the second liquid phase. 3. The method according to claim 1, wherein the reactor comprises a height having an upper part and a lower part and the first liquid phase and the second liquid phase are injected into the reactor at the same height, while the third phase is injected into the reactor below the height of the first liquid phase and the second liquid phase, injection of the first liquid phase, the second liquid phase and the third liquid phase being done in the lower part of the reactor forming an injection zone. 4. The method according to claim 1, wherein the reactor comprises a height having an upper part and a lower part and the first liquid phase and the second liquid phase are injected into the reactor at the same height, while the third liquid phase is injected into the reactor above the height of the first liquid phase and the second liquid phase, injection of the first liquid phase, the second liquid phase and the third liquid phase being done in the upper part of the reactor forming an injection zone. 5. The method according to claim 1, wherein the third liquid phase is injected into the reactor at a supply flow greater than the supply flow of the first liquid phase and/or the second liquid phase. 6. The method according to claim 1, further comprising a sedimentation step of the mix originating from step b), after step b). 7. The method according to claim 6, further comprising collecting the precipitate particles, after the sedimentation step. 8. The method according to claim 1, further comprising a recycling step of the third liquid phase. 9. The method according to claim 3, wherein the method is conducted in a fluidised bed reactor with a vertical principal axis comprising:a lower part used for injection of the first liquid phase, the second liquid phase and the third liquid phase;an intermediate part used for fluidisation of the mix formed from the first liquid phase and the second liquid phase by the third liquid phase; andan upper part used for sedimentation of the precipitate particles. 10. The method according to claim 4, wherein the method is conducted in a fluidised bed reactor with a vertical principal axis comprising:an upper part used for injection of the first liquid phase, the second liquid phase and the third liquid phase;an intermediate part used for fluidisation of the mix formed from the first liquid phase and the second liquid phase by the third liquid phase; anda lower part used for sedimentation of the precipitate particles. 11. The method according to claim 1, wherein the solute is an actinide element. 12. The method according to claim 11, wherein the method is a method for oxalic precipitation of at least one actinide element. 13. The method according to claim 11, wherein:the first liquid phase is an aqueous solution, comprising at least one actinide element as solute;the second liquid phase is an aqueous solution containing a precipitation reagent of the actinide element(s) present in the first liquid phase, this precipitation reagent comprising oxalic acid; andthe third liquid phase is an organic solution comprising an organic solvent immiscible with the first liquid phase and the second liquid phase. 14. The method according to claim 13, wherein the organic solvent is dodecane or hydrogenated tetrapropylene. 15. The method according to claim 1, wherein the first liquid phase and the second liquid phase are injected simultaneously into the reactor such that the first liquid phase and the second liquid phase come into contact immediately, forming the mix comprising precipitate particles of the at least one solute in suspension. 16. The method according to claim 1, wherein the first, second and third liquid phases are mixed by the supply flows of the first, second and third liquid phases into the reactor. 17. The method according to claim 16, wherein the reactor does not contain a stirrer. 18. The method according to claim 1, wherein the first, second and third liquid phases are injected continuously into the reactor. 19. The method according to claim 1, wherein the first, second and third liquid phases are injected semi-continuously into the reactor.
	description	The present application relates generally to nuclear fuel rods; and more particularly to, a system for assembling or disassembling a segmented rod of a nuclear fuel bundle used within a nuclear reactor pressure vessel. FIG. 1 is a schematic illustrating an environment in which an embodiment of the present invention may operate. FIG. 1 illustrates a typical nuclear processing facility 10, which may comprise a spent fuel pool 12, and a reactor pressure vessel (RPV) 15. FIG. 2 is a schematic illustrating the RPV 15 of FIG. 1. During operation of the reactor, cooling water circulating inside a RPV 15 is heated by nuclear fission produced in the nuclear fuel core 35. Feedwater is admitted into the RPV 15 via a feedwater inlet 17 and a feedwater sparger 20. The feedwater flows downwardly through a downcomer annulus 25, which is an annular region between RPV 15 and a core shroud 30. The core shroud 30 is a stainless steel cylinder that surrounds the nuclear fuel core 35, which includes nuclear fuel bundle assemblies 40, only a few are illustrated in FIG. 2, having a plurality of segmented fuel rods 43. A top guide 45 and a core plate 50 support each fuel bundle assembly 40. The cooling water flows downward through the downcomer annulus 25 and into the core lower plenum 55. Then, the water in the core lower plenum 55 flows upward through the nuclear fuel core 35. In particular, water enters the fuel bundle assemblies 40, wherein a boiling boundary layer is established. A mixture of water and steam exits the nuclear fuel core 35 and enters the core upper plenum 60 under the shroud head 65. The steam-water mixture then flows through steam separators 70 on top of the shroud head 65 and enters the steam dryers 75, which separate water from steam. The separated water is recirculated back to the downcomer annulus 25 and the steam flows out of the RPV 15 and to a steam turbine, or the like, which is not illustrated in the Figures. The BWR also includes a coolant recirculation system, which provides the forced convection flow through the nuclear fuel core 35 necessary to attain the required power density. A portion of the water is drawn from the lower end of the downcomer annulus 25 via recirculation water outlet 80 and forced by a recirculation pump (not illustrated) into a plurality of jet pump assemblies 85 via recirculation water inlets 90. The jet pump assemblies 85 are typically circumferentially distributed around the core shroud 30 and provide the required reactor core flow. A typical BWR may have between sixteen to twenty-four inlet mixers 95. As illustrated in FIG. 2, a conventional jet pump assembly 85 comprises a pair of inlet mixers 95. Each inlet mixer 95 has an elbow welded thereto, which receives pressurized driving water from a recirculation pump via an inlet riser 97. A type of inlet mixer 95 comprises a set of five nozzles circumferentially distributed at equal angles about an axis of the inlet mixer 95. Here, each nozzle is tapered radially inwardly at the nozzle outlet. This convergent nozzle energizes the jet pump assembly 85. A secondary inlet opening may be located radially outside of the nozzle exits. Therefore, as jets of water exit the nozzles, water from the downcomer annulus 25 is drawn into the inlet mixer 95 via the secondary inlet opening, where mixing with water from the recirculation pump then occurs. During the shutdown of the nuclear reactor, some of the segmented rods 43 may be removed from a fuel bundle assembly 40. These segmented rods 43 are then disassembled for further processing. The disassembly process is time consuming, delaying the processing and preparation of the segmented rods 43 before reentry into the RPV 15. For the aforementioned reasons, there is a need for a system for disassembling a plurality of segmented rods 43 of a nuclear reactor core. The system should allow for simultaneously disassembling multiple segmented rods 43. The system should reduce the disassembly time and lower operator exposure to radioactivity. In accordance with an embodiment of the present invention, a system for positioning at least one segmented rod, the system comprises: a channel assembly for receiving a plurality of segmented rods, wherein the channel assembly encloses the plurality of segmented rods and comprises a channel and a lifting mechanism, wherein the lifting mechanism positions the plurality of segmented rods to allow for the assembly or disassembly of each of the plurality of segmented rods. Here, the system of claim may further comprise a holder assembly located at a top end of the channel assembly, wherein the holder assembly comprises: a separate holder for each segmented rod, wherein the holder secures the segmented rod in a position allowing for assembly or disassembly; a mechanism for opening and closing each holder; wherein the mechanism opens and closes all holders in unison; and an opening that allows for integrating the lifting mechanism with the holder assembly, wherein the lifting mechanism may lift the plurality of segmented rods in unison. In accordance with another embodiment of the present invention, a system for positioning segmented rods of a nuclear reactor, the system comprises: a nuclear processing facility comprising: a spent fuel pool, a reactor pressure vessel (RPV); wherein the RPV comprises a fuel bundle comprising segmented rods; and a segmented rod positioning chamber comprising, wherein the segmented rod positioning chamber comprises: a channel assembly for receiving the segmented rods, wherein the channel assembly encloses segmented rods and comprises a channel and a lifting mechanism, wherein the lifting mechanism moves the segmented rods within the channel; and wherein the lifting mechanism allows for the assembly or disassembly of the plurality of segmented rods. Here, the system may further comprise a collet assembly located at a forward end of the channel assembly, wherein the collet assembly comprises: a plurality of collets, wherein an individual tapered collet is designated for each segmented rod, wherein each collet secures a single segmented rod in a position allowing for assembly or disassembly of each of the plurality of segmented rods; and a mechanism for opening and closing each collet. Certain terminology is used herein for convenience only and is not to be taken as a limitation on the invention. For example, words such as “upper”, “lower”, “left”, “front”, “right”, “horizontal”, “vertical”, “upstream”, “downstream”, “fore”, “aft”, “top”, “bottom” merely describe the configuration shown in the Figures. Indeed, the components may be oriented in any direction and the terminology, therefore, should be understood as encompassing such variations unless specified otherwise. An embodiment of the present invention takes the form of a system that allows for simultaneously assembling or disassembling multiple segmented nuclear fuel rods (hereinafter “segmented rods”). An embodiment of the present invention, may receive, secure, and move the segmented rods 43 into a position that allows for performing the tasks of either assembly or disassembly; allowing for an operator to use a tool to complete the aforementioned tasks. An embodiment of the present invention may be used with a wide variety of segmented rods 43 used within an RPV 15. Referring again to the Figures, where the various numbers represent like parts throughout the several views. FIG. 3 is a schematic illustrating an isometric view of a segmented rod positioning chamber 1000, in accordance with an embodiment of the present invention. FIG. 3 provides an overview of an embodiment of the present invention. The segmented rod positioning chamber 1000 may comprise a channel assembly 500 having a length approximately equal to that of a fully assembled segmented rod 43. A holder assembly 200, for controlling the movement of the plurality of segmented rods 43 within the channel assembly 500, may be connected to an upper end of the segmented rod positioning chamber 1000. A basin 100 for catching loose rod segments or rod components may surround the holder assembly 200. FIGS. 4A-4C, collectively FIG. 4, are schematics illustrating isometric, front, and top views of a basin 100 of a segmented rod positioning chamber 1000, in accordance with an embodiment of the present invention. The basin 100 may help to ensure that segments of a segmented rod 43 do not fall from the segmented rod positioning chamber 1000. An operator of the segmented rod positioning chamber 1000 may be positioned above a spent fuel pool 12 (illustrated in FIG. 1) of a nuclear power plant. Here, the basin 100 may reduce the chance of a segment falling into the spent fuel pool 12. FIG. 4A illustrates a perspective view of an embodiment of the basin 100, which may comprise drainage holes 110 and a mounting surface 120. The drainage holes 110 may allow for the fluid of the spent fuel pool 12 to flow through the basin 100; and lighten the overall weight of the segmented rod positioning chamber 1000. The drainage holes 110 may be located at an aft end of the basin 100. The mounting surface 120 may provide a bearing surface when connecting the basin 100 with the top end of a segmented rod positioning chamber 1000. The basin 100 may have a bottom opening 130 that allows for the basin 100 to surround the holder assembly 200. The basin 100 may have a top opening 140 that allows an operator to access the holder assembly 200. The basin 100 may be formed of any shape that may surround the holder assembly 200, as illustrated in FIG. 4B. In an embodiment of the present invention, the top opening 140 may be larger than the bottom opening 130, allowing an operator greater access to the holder assembly 200 and the surrounding area, as illustrated in FIG. 4. FIG. 5 is a schematic illustrating an exploded view of the holder assembly 200 of a segmented rod positioning chamber 1000, in accordance with an embodiment of the present invention. The holder assembly 200 generally serves to control the movement of the segmented rods 43 within the channel assembly 500. The holder assembly 200 may move and secure each segmented rod 43 in a position that allows an operator to remove the exposed segment. Next, the holder assembly 200 may secure the segmented rods 43 in a position that allows for the removal of the next exposed segment. Alternatively, the holder assembly 200 may secure the segmented rods 43 in a position that allows for connecting the next segment. The process may be repeated until all segments of the plurality of segmented rods 43 have been removed or assembled, respectively. In an embodiment of the present invention, the support plate 205 forms a top surface of the holder assembly 200. The holder assembly 200 may comprise a plurality of holders 215, with one holder 215 for one segmented rod 43. Each holder 215 may mate with a housing 210; and the plurality of housings 210 may mount onto a top surface of the support plate 205; which may be connect to an inside surface of the vertical segment 290 of the brace 280. Also, mounted on the top surface of the support plate 205 may be an adjustment device 250 for securing and releasing the plurality of segmented rods 43 within the holders 215. A holder bushing 245, which mates with the adjustment device 250; may be positioned between the support plate 205 and an activation plate 225. Furthermore, a sleeve 255, which may be part of an adjustment lifting mechanism 505 (illustrated in FIG. 7), may also be positioned between the support plate 205 and the activation plate 225. A bottom end of each holder 215 may be secured to the activation plate 225 by a fastener 240. This may allow the activation plate 225 to tighten or loosen each holder 215 when the adjustment device 250 is moved. A plurality of guides 230 may connect to the support plate 205 and slide through the activation plate 225. The support plate 205 may mount to a brace 280; which may comprise vertical segments 290 and horizontal segments 295. The brace 280 may allow for the activation plate 225 to linearly move therein when the adjustment device 250 is moved. FIGS. 6A-6C, collectively FIG. 6, are schematics illustrating isometric, top, and sectional views of a holder assembly 200 of FIG. 5, in accordance with an embodiment of the present invention. FIG. 6A illustrates an isometric view of an assembled holder assembly 200 with a plurality of segmented rods 43, and mounted on the channel assembly 500. In an embodiment of the present invention, the holder assembly 200 may hold five segmented rods 43. This may allow for simultaneously disassembling all of the segmented rods 43 in a fuel bundle assembly 40. In an embodiment of the present invention, the support plate 205 may be a square plate upon which components of the holder assembly 200 mount. Here, the support plate 205 may form the top of the holder assembly 200 and along with the vertical and horizontal segments 290, 295 form the shell of the holder assembly 200. The activation plate 225 may also be a square plate of a size that allows linear movement within the shell of the holder assembly 200. The activation plate 225 may serve as the means by which the plurality of holders 215 simultaneously open and close around the plurality of segmented rods 43. In an embodiment of the present invention, the holder 215 may have the form of a tapered collet. Here, the holder 215 may slide into the housing 210, which may have the form of a hollow cylinder. A connector 220 may fasten the housing 210 to the top surface of the support plate 205, after the housing 210 has been threaded into the support plate 205. Alternatively, connector 220 may have the form a machined hex flange on a top surface of the housing 210, allowing for the housing 210 to be screwed into the support plate 205. An aft end of the holder 215 may allow for connection with the activation plate 225 via a fastener 240. An embodiment of the adjustment device 250 may have the form of a partially threaded rod that mates with the holder bushing 245. Here, as the adjustment device 250 is rotated, the holder bushing 245 moves linearly along with the activation plate 225. The head of the adjustment device 250 may have a hex-shape, or the like, that allows for a tool to rotate the adjustment device 250. The head of the adjustment device 250 may be accessible from a top surface of the support plate 205. A head of a lifting rod 510 of the lifting mechanism 505 (illustrated in FIG. 7) may also be accessible from a top surface of the support plate 205, as illustrated in FIG. 6A. A portion of each guide 230 may be accessible from the top surface of the support plate 205. In an embodiment of the present invention, the guide 230 may have the form of a partially threaded rod. The guide 230 may slide through the activation plate 225 and screw into the support plate 205. The guides 230 may help assemble and position the activation plate 225 with respect to the support plate 205. The guides 230 may keep the activation plate 225 in alignment with the support plate 205, to prevent binding of the activation plate 225 within the brace 280. FIG. 6B illustrates a top view of the holder assembly 200, in accordance with an embodiment of the present invention. FIG. 6B illustrates the holder assembly 200 without segmented rods 43. FIG. 6B illustrates an embodiment of a layout that may be used to orientate some of the components of the holder assembly 200 on the support plate 205. Here, the lifting rod 510 may be centrally located on the support plate 205 within the sleeve 255; the adjustment device 250 may be located near a first corner of the support plate 205; and a guide 230 may be located in each of the remaining corners of the support plate 205. FIG. 6C is section view along line 6C-6C of FIG. 6B. FIG. 6C illustrates how the components of the holder assembly 200 may be internally connected. For example, but not limiting of, the holder 215, in the form of a collet, is within the housing 210; which is secured to the support plate 205 via the connector 220. Alternatively, connector 220 may have the form of a machined hex flange on a top surface of the housing 210, allowing for the housing 210 to be screwed into the support plate 205. An end portion of the holder 215 is secured to the activation plate 225 via fastener 240. FIG. 6C also illustrates that the activation plate 225 resides within the boundaries of the brace 280. The components of the holder assembly 200 may be created out of any material that can withstand the operating environment to which the segmented rod positioning chamber 1000 may be exposed. For example, but not limiting of, the holder assembly 200 may be created of materials that can withstand the environment of a nuclear spent fuel pool 12 (illustrated in FIG. 1). Referring now to FIGS. 7A-7E, collectively FIG. 7, are schematics illustrating elevation, top, and bottom views of a channel assembly 500 of the segmented rod positioning chamber 1000, in accordance with an embodiment of the present invention. An embodiment of the channel assembly 500 of present invention may comprise: a channel 503; a lifting mechanism 505 comprising: a sleeve 255; a lifting rod 510; a plurality of windows 515; spacers 520; a positioning plate 530; a channel support plate 535; and alignment tabs 545. The channel 503 may serve to contain the plurality of segmented rods 43 during the disassembly process. As illustrated, for example in FIG. 7A, the channel 503 may have the form of a hollow and square column. A top end of the channel 503 may be open to allow for connection with the holder assembly 200. As illustrated in FIG. 7C, a channel support plate 535 may enclose the bottom end of the channel 503. The channel support plate 535 may aide with maintaining the square shape of the channel 503. In an embodiment of the present invention, the channel support plate 535 may have a plurality of holes. These holes may reduce the weight of the channel support plate 535 and thus the overall weight of the segmented rod positioning chamber 1000; while allowing for fluids that may be present within the channel 503 to drain. The lifting mechanism 505 may linearly move the plurality of segmented rods 43 within the segmented rod positioning chamber 1000. The lifting mechanism 505 may be located within the hollow portion of the channel 503. In an embodiment of the present invention, the lifting mechanism 505 may comprise a lifting rod 510, a plurality of spacers 520, and a positioning plate 530. The lifting rod 510 may include threaded portions. A head end of the lifting rod 510 may have a hex shape, or the like; allowing for a tool to actuate the lifting mechanism 505. A bottom end of the lifting rod 510 may be connected with the channel support plate 535. As illustrated, for example, in FIG. 7B, the positioning plate 530 may be connected to the lifting rod 510 near an aft end, above the channel support plate 535. A portion of the positioning plate 530 may comprise a means to mate with the lifting rod 510. Here, as the lifting rod 510 rotates, the positioning plate 530 moves linearly, as described. In an embodiment of the present invention, the positioning plate 530 may comprise a series of threads that mate with the screw portions of the lifting rod 510. This may allow the positioning plate 530 to move linearly, while the lifting rod 510 is rotated. As illustrated in FIG. 7, spacers 520 are located throughout the channel 503. The spacers 520 may serve to prevent each segmented rod 43 from bowing while inside the channel assembly 500. FIG. 7E illustrates a spacer 520 of an embodiment of the present invention. The spacer 520 may have the form of the square plate with multiples holes, wherein each hole may allow for a segmented rod 43 to slide through. The spacer 520 may also have a center opening for allowing the lifting rod 510 to slide through. FIGS. 7B and 7D illustrate an example of how each spacers 520 may be positioned on the lifting rod 510. The spacers 520 may be equally positioned along the lifting rod 510, wherein each spacer 520 is located above the positioning plate 530. In an embodiment of the present invention, a series of keys 540 may be located around the periphery of each spacer 520. The keys 540 may have the form of a notch, or the like. Each key 540 may mate with an alignment tab 545, which may be located within the channel 503. The plurality of keys 540 and alignment tabs 545 may form a system that limits the movement of each spacer 520 located within the channel 503. This may provide an effective way of ensuring that each spacer 520 consistently returns to a designated position of being moved by the positioning plate 530. Here, the location of each key 540 and corresponding alignment tab 545 may be unique to each spacer 520 located within the channel 503. This system may allow for each spacer 520 to return to a designated positioned when the lifting rod 510 lowers or raises the positioning plate 530. This system may also allow for the spacers 520 to directly or indirectly collapse upon the positioning plate 530 when being raised by the lifting rod 510. The channel 503 may also comprises windows 515 along at least one side, as illustrated in FIGS. 7A to 7D. The windows 515 may allow for fluid of the spent fuel pool 12 (illustrated in FIG. 1) to flow through the segmented rod positioning chamber 1000. The windows 515 may also lighten the overall weight of the channel assembly 500. The windows 515 may also reduce the chance of debris becoming lodged within the segmented rod positioning chamber 1000 and a visual aid during the operation of the segmented rod positioning chamber 1000. The channel 503 of the channel assembly 500 may be created out of a transparent material allowing for viewing the plurality of segmented rods 43 within the channel assembly 500. The remaining components of the channel assembly 500 may be created out of any material that can withstand the operating environment to which the segmented rod positioning chamber 1000 may be exposed. For example, but not limiting of, the holder assembly 200 may be created of materials that can withstand the environment of a nuclear spent fuel pool 12. FIGS. 8A-8C, collectively FIG. 8, are schematics, illustrating isometric views of the segmented rod positioning chamber 1000 in use, in accordance with an embodiment of the present invention. As discussed, an embodiment of the present invention allows an operator to quickly arrange a plurality of segmented rods 43 for disassembly. In an embodiment of the present invention, the holder assembly 200 may use collets to maneuver several segmented rods 43, as illustrated in FIG. 8. FIG. 8A illustrated the engagement of the keys 540 with the alignment tab 545, while the positioning plate 530 is located near the bottom of the channel 503. Here, the length of each segmented rod 43 may be the original length before disassembly has started. FIGS. 8B and 8C illustrate the segmented rod positioning chamber 1000 having the spacers 520 collapsed upon the positioning plate 530. Here, an operator, as described, has removed the majority of segments. In an embodiment of the present invention, an operator may use a tool to actuate the lifting rod 510 to raise the positioning plate 530 to a level where a first segment may be removed from the segmented rod 43. The operator may then actuate the adjustment device 250 of the holder assembly 200, to tighten and/or loosen the holders 215 around the segmented rods 43. Here, an operator may use a tool to remove the first segments from the segmented rods 43. Next, the operator may repeat the aforementioned process until all segments of the segmented rods 43 are removed. If additional segmented rods 43 need to be disassembled, an operator may actuate the adjustment device 250 to loosen the holders 215 and actuates the lifting rod 510 to lower the positioning plate 530. Here, additional full length segmented rods 43 may be inserted into segmented rod positioning chamber 1000 and the aforementioned process may be repeated. Although the present invention has been shown and described in considerable detail with respect to only a few exemplary embodiments thereof, it should be understood by those skilled in the art that we do not intend to limit the invention to the embodiments since various modifications, omissions and additions may be made to the disclosed embodiments without materially departing from the novel teachings and advantages of the invention, particularly in light of the foregoing teachings. Accordingly, we intend to cover all such modifications, omission, additions and equivalents as may be included within the spirit and scope of the invention as defined by the following claims.
	claims	1. A method of preparing, inspecting, and/or repairing a canister containing radioactive material in a canister storage system, the method comprising:(a) mounting a travel system on a surface of a fixed canister storage module configured for storage of only a single closed canister containing radioactive material, wherein the canister storage module is an overpack designed for storage of the canister, wherein the travel system includes a support structure, at least one traveling device, and a base for supporting the traveling device and providing for rotational movement of the traveling device relative to the support structure, wherein the surface of the module includes an opening to a containment area of the module, and wherein the travel system is mounted on the surface of the module such that the base is aligned with the opening;(b) rotating the base and the traveling device relative to the support structure and a fixed canister and moving the base to move the positioning of the traveling device relative to the support structure to travel along a circumferential path of the cylindrical body of the canister; and(c) fixing the base and moving the canister relative to the fixed base and the traveling device. 2. The method of claim 1, wherein the module is one of a horizontal canister storage module or a vertical canister storage silo. 3. The method of claim 1, wherein the at least one traveling device is selected from the group consisting of a sensing device, a preparation device, and a repair device. 4. The method of claim 3, wherein the sensing device is a non-destructive sensing device. 5. The method of claim 3, wherein the sensing device is selected from the group consisting of dye penetrant sensors, ultrasonic examination sensors, eddy current examination sensors, laser ultrasonic examination sensors, and visual inspection sensors. 6. The method of claim 3, wherein the repair device is selected from the group consisting of grinders, welding heads, abrasive nozzles, peening nozzles, surface coating spray nozzles, and surface cleaning spray nozzles. 7. The method of claim 1, mounting the at least one traveling device on the base in one or more mounting positions. 8. The method of claim 1, wherein the travel system includes a plurality of traveling devices. 9. The method of claim 8, wherein traveling devices may be positioned about 180 degrees from each other on the base. 10. The method of claim 1, moving the traveling device in multiple degrees of movement freedom relative to the support structure. 11. The method of claim 1, moving the traveling device along a weld on the canister. 12. The method of claim 1, further comprising actuating the travel system using an actuation system. 13. The method of claim 12, wherein the actuation system includes a timing belt driven by a stepper motor. 14. The method of claim 1, further comprising moving the base relative to the support structure using a bearing system. 15. The method of claim 14, wherein the bearing system includes a guide ring, an external bearing ring assembly, and an internal bearing ring assembly. 16. The method of claim 1, further comprising moving the traveling device in multiple degrees of freedom relative to the base, including forward and back movement relative to the base, radial rotation relative to the base, and pivotable movement relative to the base. 17. A method of preparing, inspecting, and/or repairing a canister containing radioactive material in a canister storage system, the method comprising:(a) mounting a travel system on a surface of a fixed canister storage module configured for storage of only a single closed canister containing radioactive material, wherein the canister storage module is a horizontal canister storage module comprising an overpack designed for storage of the canister, wherein the travel system includes a support structure, at least one traveling device, and a base ring for supporting the traveling device and providing for rotational movement of the traveling device relative to the support structure, wherein the surface of the module includes an opening to a containment area of the module, and wherein the travel system is mounted on the surface of the module such that the base ring is aligned with the opening, and moving the traveling device in multiple degrees of freedom relative to the base ring, including forward and back movement relative to the base ring, radial rotation relative to the base ring, and pivotable movement relative to the base ring;(b) rotating the base ring and the traveling device relative to the support structure and a fixed canister; and(c) fixing the base ring and moving the canister relative to the fixed base ring and the traveling device. 18. A method of preparing, inspecting, and/or repairing a canister containing radioactive material in a canister storage system, the method comprising:(a) mounting a travel system on a surface of a fixed canister storage module configured for storage of only a single closed canister containing radioactive material, wherein the fixed canister storage module is an overpack designed for storage of the canister, wherein the travel system includes a support structure, at least one traveling device, and a base ring for supporting the traveling device and providing for rotational movement of the traveling device relative to the support structure, wherein the surface of the module includes an opening to a containment area of the module, and wherein the travel system is mounted on the surface of the module such that the base ring is aligned with the opening;(b) moving the canister from a stored position in the module to a protruding position, wherein at least a portion of the canister protrudes from the opening of the module;(c) rotating the base ring and the traveling device relative to the support structure and a fixed canister and moving the positioning of the base ring and the traveling device relative to the support structure to travel along a circumferential path of the cylindrical body of the canister, wherein the traveling device is a preparation device;(d) rotating the base ring and the traveling device relative to the support structure and a fixed canister and moving the positioning of the base ring and the traveling device relative to the support structure to travel along a circumferential path of the cylindrical body of the canister, wherein the traveling device is a sensing or repairing device;(e) fixing the base ring and moving the canister relative to the fixed base ring and the traveling device, wherein the traveling device is a preparation device; and(f) fixing the base ring and moving the canister relative to the fixed base ring and the traveling device, wherein the traveling device is a sensing or repairing device.
	description	This patent application claims the priority benefit under 35 U.S.C. § 119(e) of U.S. Provisional Application No. 62/629,339 filed on Feb. 12, 2018, the contents of which are herein incorporated by reference. This invention pertains generally to thermal sleeves and, more particularly, to thermal sleeves that can be relatively easily installed and replaced. This invention also pertains to methods of installing and replacing thermal sleeves. In response to operational experience at a number of nuclear plants there is a clear need for a quickly deployed thermal sleeve replacement for the thermal sleeves in the reactor vessel closure head penetration adapter housing. Thermal sleeve flange wear is a phenomenon first identified domestically in 2014 when a part-length sleeve failed. Since then inspections have been recommended and acceptance criteria have been developed. More recently (December 2017), two additional thermal sleeve failures at rodded locations were identified. A sectional view of an example arrangement of a conventional thermal sleeve 10 positioned in a guide funnel 12 of a reactor head penetration adaptor 14 within a control rod drive mechanism (CRDM) 16. When a thermal sleeve 10 fails at an upper flange 18 location at a rodded location, the only current repair is the complex removal of the CRDM 16 and reinstallation of a new sleeve 10 and guide funnel 12. This replacement can take several weeks and is required, because the upper flange 18 is integral to the thermal sleeve 10 and fully captured in the head penetration adapter 14. Accordingly, it is an object of this invention to provide a new thermal sleeve design and method of installation that will reduce the time required for thermal sleeve replacement and avoid the requirement to remove the CRDM. This invention achieves the foregoing objective in one embodiment by providing a replacement thermal sleeve comprising an elongated tubular sheath having a wall with a radially, outwardly extending flange at one end of the wall and an axis extending along the elongated dimension. A plurality of slots extend axially in the wall of the elongated tubular sheath with the slots extending through the flange and along the sheath a preselected distance that does not extend to another end of the wall of the sheath. In one such embodiment the slots have a width sufficient to facilitate compression of the flange to narrow an outside diameter of the flange in the compressed state to an extent necessary to clear any obstruction in an opening of a tubular member in which the thermal sleeve is to be inserted. The slots define a flexible leaf between each two adjacent slots. In one embodiment the plurality of slots are two slots formed 180 degrees apart around the circumference of the wall. In one such alternate embodiment the plurality of slots are three slots formed 120 degrees apart around the circumference of the wall. In still another such embodiment, the plurality of slots are four slots formed 90 degrees apart around the circumference of the wall. In another embodiment, in a relaxed state, at the flange, the leafs substantially touch each adjacent leaf and the leafs are configured so that if spread apart at the flange to a point where the width of the slot is sufficient to seat the flange in a recess in the opening of the tubular member in which the flange is to be seated to lock the replacement thermal sleeve in the opening, then the leafs experience plastic deformation. The invention also includes a method of replacing a damaged thermal sleeve in a reactor vessel head adapter that connects a control rod drive mechanism to a reactor vessel head. The method includes the step of accessing the damaged thermal sleeve from an underside of the reactor vessel head. The method then removes the damaged thermal sleeve and, in one embodiment, obtains a replacement thermal sleeve. The replacement thermal sleeve has an elongated tubular sheath having a radially, outwardly extending flange at one end; an axis extending along the elongated dimension; and a plurality of axially extending slots in and through the wall of the elongated tubular sheath. The slots extend through the flange and along the sheath a preselected distance that does not extend to another end of the wall of the sheath and have a width sufficient to narrow an outside diameter of the flange to at least an extent necessary to clear any obstruction in an opening of the reactor head adapter in which the thermal sleeve is to be inserted, when adjacent sections of the flange in between the slots substantially touch. The slots define a leaf in between each two adjacent slots. The method then alters the diameter of the flange on the replacement thermal sleeve to an extent necessary to clear any obstruction in the opening in the tubular member that will be encountered while inserting the replacement thermal sleeve to a location within the opening originally occupied by the damaged thermal sleeve; and inserts the replacement thermal sleeve through the opening from the underside of the reactor vessel head. Finally the method expands the diameter of the flange into a recess in the opening in the reactor head adapter. In one embodiment, the activation of the steps of altering the diameter of the flange, comprises exerting a compressive force to compress adjacent sections of the flange together, and expanding the diameter of the flange, comprises removing the compressive force, and both steps are performed from the underside of the reactor vessel head. In such an embodiment the steps of compressing the flange and releasing the compressed flange is preferably performed by either a tool inserted from the underside of the reactor vessel head that grips recesses in an upper surface of the flange or a retention strap installed below the flange. In still an alternate embodiment of the method the step of altering the diameter of the flange is performed during manufacture of the replacement thermal sleeve and the step of expanding the diameter of the flange is performed from the underside of the reactor vessel head adapter. The invention also contemplates a replacement thermal sleeve having a plurality of longitudinal wall sections, with each wall section having a radially outwardly extending flange segment at one end, that when the longitudinal wall sections are fitted together, configure a tubular wall of the replacement thermal sleeve. This latter embodiment of the replacement thermal sleeve also includes a fastener for fastening the plurality of longitudinal wall sections together. One such embodiment for replacing a thermal sleeve in a reactor closure head penetration adapter may configure the longitudinal wall sections to be inserted one at a time into an opening in an underside of the reactor head adapter and the fastener is configured to be applied from an underside of the reactor closure head penetration adapter. The plurality of longitudinal wall sections may also comprise three wall sections. The invention further contemplates a method for installing the latter embodiment of the replacement thermal sleeve. The method comprises accessing the damaged thermal sleeve from and underside of the reactor vessel head adapter. The damaged thermal sleeve is removed and a replacement thermal sleeve is obtained, with the replacement thermal sleeve divided into a plurality of longitudinal wall sections. The plurality of longitudinal wall sections are inserted into an opening in the underside of the reactor vessel head adapter, one at a time. Then the longitudinal wall sections are arranged within the opening into a tubular housing of the replacement thermal sleeve. The longitudinal wall sections are then fastened together from the underside of the reactor vessel head adapter. One object of the present invention is to avoid the requirement to remove the CRDM in order to access and remove the thermal sleeve to shorten the time it takes to replace a thermal sleeve in a reactor head adapter. Reducing the time required for a thermal sleeve replacement and providing options on how to do so will be tremendously valuable to the industry as thermal sleeve failures become more prevalent and regular inspections are performed to identify such failures. This invention is a re-design of the thermal sleeve that can be installed without the CRDM removal process. To achieve this, embodiments of the present invention provide for the flange on the lead end of the thermal sleeve to be deformed or disassembled in various ways such that the flange can pass through the narrowest inner diameter of the opening in the reactor head adaptor through which the flange is to be inserted. Referring now to FIGS. 2A and 2B, a thermal sleeve 20 in accordance with an example embodiment of the present invention is shown. Thermal sleeve 20 is formed generally as an elongated tubular body 22 disposed about a central longitudinal axis 24 and extending between a bottom end 26 and a top end 28. Thermal sleeve 20 includes a flanged region 30 disposed at or about top end 28 which extends radially outward from tubular body 22 (i.e., away from axis 24). As shown shifting from FIG. 2A to FIG. 2B, flanged region 30 may be deformed inward (i.e., toward axis 24) when a predetermined force F is applied to flanged region 30. To provide for such deformation of flanged region 30, thermal sleeve 20 includes a plurality (three are shown in the illustrated example) of slots 32 defined in tubular body 22, with each slot 32 extending through and from top end 28 toward bottom end 26. As a result of such slots 32, flanged region 30 is thus divided in a plurality of segmented flange lugs 33, with each flange lug 33 being spaced from each adjacent flange lug by a respective slot 32 of the plurality of slots 32. Each slot 32 extends a predetermined distance L along tubular body 22 without extending through bottom end 26 thereof. Additionally, each slot 32 has a maximum width W (generally circumferential to axis 24) which is sufficient to narrow a maximum outside diameter of flanged region 30 from a first diameter D1 (FIG. 2A) to a second diameter D2 (FIG. 2B) in order to clear any obstruction in an opening of a tubular member in which thermal sleeve 20 is to be inserted. As shown in FIGS. 3A and 3B, such slotted design allows for elastic compression of the slotted portion of tubular body 22, and thus flanged region 30 thereof, such that the resulting outer diameter D2 of flanged region 30 is less than the narrowest inner diameter ID of opening 34 in head penetration adapter 14 (shown in section in FIGS. 3A and 3B, see also FIG. 1) through which thermal sleeve 20 it is to be inserted. As shown in FIGS. 4A-4E, temporary compression of flanged region 30 of thermal sleeve 20 may be achieved with specialized tooling 40 that interfaces with a top flange face 42 of thermal sleeve 20, e.g., via retractable arms 43 of tooling 40 selectively engaging recesses 44 (FIG. 2A) formed therein or a retention strap stored below the flange (not shown in the figures). Once compressed, replacement sleeve 20 is inserted through the bottom of the head penetration adaptor 14, such as shown in FIG. 4A. Once sleeve 20 is positioned at an installation elevation, tooling 40 releases the compression in a controlled manner and disengages flanged region 30, such as shown in FIGS. 4C and 4D. The tooling 40 is then removed downward through the shaft of head penetration adaptor 14, such as shown in FIG. 4E. Referring to FIG. 5, thermal sleeve 20 may be provided as a full-length thermal sleeve. Such embodiment is for use after the entirety of the original thermal sleeve has been completely removed and is installed in the head penetration adaptor 14 in the same manner such as previously discussed. In such embodiment, the bottom end 26 of tubular body 22 may include a funnel 50 to allow guidance of the drive rod into thermal sleeve 20. Funnel 50 may be integral to tubular body 22 or attached separately via any suitable process or arrangement. Referring to FIG. 6, thermal sleeve 20 may be of a sufficiently short length so as to be fully contained within the head penetration housing 14. In such example, tubular body 22 may include a boss 52 positioned at the bottom end 26 thereof having a greater outer diameter than tubular body 22 in order to assist in centering the thermal sleeve 20 within the head penetration housing 14. The inner diameter of the bottom end 26 of tubular body 22 includes a lead-in chamfer to aid in drive rod insertion thereto. This design can be used with an extension tube attached directly to the bottom of the head penetration housing 14. This embodiment may be used with a guide sleeve adaptor 54 also formed from a tubular body 56. Guide sleeve adaptor 54 includes a plurality of alignment tabs 58 that each extend from a top end 60 thereof and that are positioned so as to align top end 60 of guide sleeve adaptor 54 with bottom end 26 of tubular body 22 of short thermal sleeve 20. Once in place, guide sleeve adaptor 54 solidly attaches to short thermal sleeve 20 and thus generally functions as a guide sleeve. Referring now to FIGS. 7 and 8A-8C, a compressible thermal sleeve 120 in accordance with another example embodiment of the present invention is shown. Thermal sleeve 120 is of generally similar design as thermal sleeve 20 (previously discussed) except thermal sleeve 120 further includes a plurality of inserts 160 which extend generally from bottom end 126 to flanged region 130 at or about top end 128 of tubular body 122 in each of slots 132, such that each slot 132 is generally divided into two by each insert 160. Accordingly, in such arrangement, each insert 160 is disposed circumferentially between a pair of segmented flange lugs 133 in a manner that prevents adjacent flange lugs 133 from moving inward towards axis 124. Radial compression of sleeve 120 after installation is a concern because downward loads on sleeve 120 could cause flanged region 130 thereof to compress radially inward and slide down the penetration and/or contact the control drive rod. Unlike each of flange lugs 133 which are particularly arranged so as to interact with a head penetration adaptor 14 (similar to flange lugs 33 previously discussed), each insert 160 does not extend outward and thus does not interface with head penetration adaptor 14 (and thus are not forced inward when sleeve 120 is pulled downward). Because inserts 160 are not forced to move radially, they will remain circumferentially between, and thus be “pinched” by the flange lugs 133 as flange lugs 133 are pushed radially inward. The interference between flange lugs 133 and inserts 160 prevents lugs 133 from moving inward enough to contact the drive rod or fit into the narrower portion of head penetration adaptor 14. As shown in FIG. 8B, the plurality of inserts 160 are designed to be able to fit within the space (not numbered) of the flange lugs 133 when the sleeve 120 is in the collapsed configuration. Pre-installation manipulation is required to place sleeve 120 in this configuration, so it cannot be achieved during operation. To achieve this configuration for installation into the penetration adapter opening, inserts 160 are first compressed by first forces F1 (FIG. 8A) into the center of the flange opening, as shown in the end view of FIG. 8B and the perspective view of FIG. 8C. Next the flange lugs 133 are compressed by a second force F2 (FIGS. 8A and 8C) until they are substantially touching as shown in the end view of FIG. 8B and the perspective view of FIG. 8C. Inserts 160 spring back into their required position between each of flange lugs 133 in the same manner as the flange lugs 133 when the thermal sleeve 120 is fully inserted in the head penetration adapter 14. Referring now to FIGS. 9A, 9B, 10A-10C, and 11A-11E, a compressible thermal sleeve 220 in accordance with another example embodiment of the present invention is shown. Thermal sleeve 220 is of generally similar design as thermal sleeve 20 (previously discussed) except thermal sleeve 220 further includes/utilizes a flanged region 230 which is expandable. By manufacturing thermal sleeve 220 with a flanged region 230 having an initially reduced outer diameter D2, a replacement sleeve 220 may be installed through the narrowest inner diameter ID of the opening 34 in head penetration adapter 14 (shown in section in FIG. 3, see also FIG. 1) through which thermal sleeve 220 it is to be inserted. Installation of thermal sleeve 220 relies on plastically deforming flange segments 233 radially outward. This process is figuratively illustrated in FIGS. 10A-10C and 11A-11E. Such plastic deformation is achieved through a tool 240 (FIGS. 11A-11E), such as a mandrel. Installation tooling 240 is initially inserted through sleeve 220 so as to be disposed above top end 228 to engage at the top of flanged region 230. Once thermal sleeve 220 has been inserted into head penetration adaptor 14 (with tooling 240 at the leading end of thermal sleeve 220), such as generally shown in FIG. 11B, tooling 240 is disengaged from thermal sleeve 220 and is pulled down through thermal sleeve 220 for removal, such as generally shown in FIGS. 11C-11E. During such removal, each of flanged segments are expanded (or swaged) such that they are plastically deformed to the larger outer diameter D1 which is greater than the inner diameter ID of head penetration adaptor 14. Referring now to FIGS. 12-20, a thermal sleeve 320 in accordance with yet another example embodiment of the present invention is shown. Thermal sleeve 320 includes a tubular body 322 comprised of at least three separate leafs 322A, 322B, 322C which each extend axially (i.e., parallel to axis 324) from bottom end 380 to top end 328 of sleeve 320. More particularly, thermal sleeve 320 is sectioned into three leafs that respectively have a maximum width WMAX (FIG. 13) that is less than narrowest inner diameter ID of head penetration adapter 14. As discussed below, leafs 322A, 322B and 322C are secured to a spacing collar 382 via a nut 384. Referring to FIG. 13, each leaf 322A, 322B, 322C is of similar construction and includes a flange lug 333 disposed at or about top end 328 and a tab 370 disposed at an opposite end 380. During assembly, each leaf 322A, 322B, 322C is first inserted through nut 384 which is slid part-way up leafs 322A, 322B, 322C so as to generally be out of the way. Next, each leaf 322A, 322B and 322C is inserted into head penetration adaptor 14 individually, and then arranged in a circular pattern underneath the reactor vessel head as described in detail in FIGS. 14A-14F, as well as FIG. 15, which illustrates how the at least one of leafs (e.g., 322C), must be generally elevated (i.e., protruded further into adaptor 14) such that the flange lug 333 thereof will clear the other two leafs (e.g., 322A and 322B) as they are moved into the finished circular/tubular arrangement such as shown in FIG. 16. After leafs 322A, 322B and 322C are arranged in the final arrangement shown in FIG. 16, spacing collar 382 (e.g., FIG. 17) is positioned generally radially within, and circumferentially between, tabs 370 of leafs 322A, 322B, 322C, such as shown in FIG. 18. The arrangement of tabs 370 and spacing collar 382 is then secured with a nut 384 which is slid down along the arrangement of leafs 322A, 322B, 322C and down around tabs 370 thereof and spacing collar 382 which generally forces each tab 370 toward spacing collar 382. Nut 384 is then threadingly engaged with spacing collar 382 and then crimped into place on spacing collar 382, such as shown generally at 386 in FIG. 20, to prevent disassembly of the combination of leafs 322A, 322B, 322C, spacing collar 382 and nut 384. The current thermal sleeve replacement procedure can take as much as 6-8 weeks, in an emergency situation. Since such a repair would not be a planned outage activity, it would likely extend the plant outage critical path. Such an extension of a plant outage could cost millions of dollars in downtime. The anticipated time for the removal of the existing sleeve (or remnants) and installation of this replacement is on the order of a few days or less. The components of this invention are simple and relatively inexpensive to manufacture. They are very similar to the original thermal sleeve design, so the experience to manufacture them already exists. While specific embodiments of the invention have been described in detail, it will be appreciated by those skilled in the art that various modifications and alternatives to those details could be developed in light of the overall teachings of the disclosure. Accordingly, the particular embodiments disclosed are meant to be illustrative only and not limiting as to the scope of the invention which is to be given the full breadth of the appended claims and any and all equivalents thereof
	abstract	A defect repair apparatus for an EUV mask has an ion beam column that scans and irradiates the EUV mask with a focused hydrogen ion beam such that no region of the EUV mask receives an amount of beam irradiation exceeding 4×1016 ions/cm2. The ion beam column comprises a gas field ion source having an emitter with a pointed tip end that emits hydrogen ions that form the hydrogen ion beam, and an ion optical system that focuses and scans the hydrogen ion beam onto the EUV mask. A detector detects secondary charged particles generated from the EUV mask when irradiated with the hydrogen ion beam, and an image forming section forms and displays an observation image of the EUV mask on the basis of an output signal from the detector so that a defect in the EUV mask and the progress of the defect repair can be observed.
053533194	description	DESCRIPTION OF THE PREFERRED EMBODIMENT Illustrated schematically in FIG. 1 is an exemplary boiling water reactor (BWR) 10 which includes an annular reactor pressure vessel 12 having a nuclear reactor core 14 submerged in coolant water 16. In this exemplary embodiment, the reactor illustrated is a simplified boiling water reactor (SBWR) which relies on natural recirculation of the water 16 therein instead of driven pumps for circulating the water therein. Accordingly, a conventional annular chimney 18 extends upwardly from the core 14 and includes a plurality of vertical, spaced apart partitions (not shown) for channeling upwardly the water heated by the core 14 to generate steam 16a. Disposed at the top of the chimney 18 are a plurality of conventional steam separators 20 having conventional tubular standpipes disposed in flow communication with the chimney 18. A portion of the steam 16a is separated from the water vapor and is further channeled upwardly into a conventional steam dryer 22 which removes further water vapor therefrom prior to discharging the steam 16a from the vessel 10 through a conventional outlet nozzle 24. To replenish the water 16 lost from the vessel 12 due to the steam 16a discharged therefrom, a feedwater sparger assembly 26 which is removable in accordance with the present invention is provided at the top of the chimney 18 around the inner circumference of the pressure vessel 12. The assembly 26 includes one or more conventional feedwater nozzles 28 through the vessel 12 which provide feedwater 16b into the vessel 12 from a suitable external source. The core 14 and the chimney 18 are spaced radially inwardly from the inner circumference of the vessel 12 to define an annular downcomer 30 therebetween in which flows downwardly by natural circulation the relatively cold feedwater 16b mixed with the water 16 in the vessel 12. The core 14 heats the reactor water 16 which decreases its density and causes it to rise upwardly through the chimney 18, while the relatively cool and denser water in the downcomer 30 flows downwardly to the bottom of the pressure vessel 12, wherein it turns upwardly and enters the core 14. Accordingly, a recirculation flowpath is created by the water and steam which flows upwardly through the chimney 18 and then laterally into the top of the downcomer 30 wherein the heated reactor water 16 is mixed with the cooler feedwater 16b and flows downwardly in the downcomer 30. During a maintenance outage, the top head of the pressure vessel 12 is conventionally removed, followed in turn by the steam dryer 22 and the steam separators 20 if required. And, in order to get access to the downcomer 30 below the sparger assembly 26 for inspection and maintenance in the downcomer 30, the sparger assembly 26 is removable in accordance with the present invention. Referring to FIG. 2, the assembly 26 may include one or more arcuate feedwater spargers 32. The sparger 32 includes an arcuate, horizontal header pipe 34 having a plurality of circumferentially spaced injector nozzles 36 disposed in flow communication therewith at the top thereof for injecting the feedwater 16b into the downcomer 30. Although the sparger 32 and the header pipe 34 may be full 360.degree. rings, in the exemplary embodiment illustrated in FIGS. 1 and 2, four identical circumferentially spaced apart arcuate header pipes 34 are used which collectively extend about 270.degree. of the full circumference of the downcomer 30. As shown with more particularity in FIGS. 3 and 4, the sparger 32 includes a conventional reducing or coupling pipe tee 38 disposed at an intermediate portion of the header pipe 34, with the trunk of the tee 38 defining a vertical inlet pipe 40 for the sparger 32 for channeling the feedwater 16b through the two branches of the tee 38 circumferentially in opposite directions into the header pipe 34 for discharge from the injector nozzles 36. As illustrated in cross-section in FIG. 5, the inlet pipe 40 has an annular distal end 40a and an intermediate portion 40b spaced longitudinally upwardly therefrom. Referring to both FIGS. 3 and 5, a supply pipe 42 includes a 90.degree. elbow 42a and an integral cylindrical thermal sleeve 42b extending horizontally from the elbow 42a in conventional flow communication with the inside of the feedwater nozzle 28 for receiving therefrom the feedwater 16b. The supply pipe elbow 42a has an upwardly facing outlet end 42c as illustrated in FIG. 5 for receiving therein the inlet pipe distal end 40a in flow communication therewith for channeling the feedwater 16b from the supply pipe 42 to the inlet pipe 40 to feed the sparger 32. The supply pipe outlet end 42c includes an annular, radially outwardly extending retention flange 44 which mates with a tubular sleeve or coupling 46 joined to the inlet pipe 40. The coupling 46 is shown in cross-section in FIG. 5 and in perspective in FIG. 6 and includes an annular band 46a at a proximal end thereof fixedly joined coaxially with the intermediate portion 40b of the sparger inlet pipe 40 by a conventional weld 48. The coupling 46 also includes a plurality of circumferentially spaced, elongate fingers 46b extending longitudinally and vertically from the band 46a and integral therewith. The fingers 46b are removably hooked or joined to the retention flange 44 for maintaining the sparger inlet pipe 40 in flow communication with the supply pipe 42, while allowing relatively easy disassembly thereof during the maintenance outage. As illustrated in FIG. 5, the retention flange 44 is preferably cylindrical and defines with an outer surface of the supply pipe 42 an annular, horizontal outer seat or ledge 44a for capturing the coupling fingers 46b thereon. The retention flange 44 also defines with an inner surface of the supply pipe 42 an annular, horizontal inner seat or ledge 44b for receiving therein the inlet pipe distal end 40a in a male and female coupling arrangement. An elastic or flexible annular seal 50 rests on the inner ledge 44b and is disposed between the inlet pipe distal end 40a and the inner ledge 44b and is sized for being elastically compressed therebetween upon engagement of the fingers 46b and the retention flange 44. In the exemplary embodiment illustrated in FIGS. 5 and 7, the seal 50 is a conventional Belleville seal made from a suitable metal which provides both sealing and elastic compression capability. Other types of suitable seals such as metallic O-rings or resilient metal seals may also be used. As shown in FIGS. 6 and 7, each of the fingers 46b includes an elongate, flexible beam 52 extending integrally from the band 46a and spaced parallel to adjacent ones of the beams 52. Disposed at a distal end of each of the beams 52 is a hook 54 defined by a flat seat 54a disposed parallel to the outer ledge 44a as illustrated in FIG. 5 for retention thereon, and a ramp 54b inclined radially outwardly from the seat 54a and integral therewith. As illustrated with more particularity in FIG. 7, the ramp 54b is configured for engagement with the supply pipe outlet end 42c by having an initially smaller diameter relative thereto to displace radially outwardly or elastically expand the fingers 46b over the retention flange 44 upon installation and translation downwardly of the inlet pipe 40 into the supply pipe 42 until the hooks 54 contract or snap radially inwardly and latch the outer ledge 44a as illustrated in FIG. 5. The lengths of the fingers 46b are selected to ensure that the seal 50 is slightly compressed between the inlet pipe distal end 40a and the inner ledge 44b upon engagement of the hooks 54 with the outer ledge 44a. This ensures an effective seal for reducing or preventing leakage of the feedwater 16b through the joint between the inlet pipe 40 and the supply pipe 42 as well as provide a vibration-resistant joint. Since the supply pipe outlet end 42c faces upwardly, and the sparger inlet pipe 40 extends vertically with the distal end 40a thereof facing downwardly toward the supply pipe outlet 42c, the sparger 32 may be readily installed by simple downward movement and insertion of the sparger inlet pipe 40 into the supply pipe outlet end 42c, with engagement of the fingers 46b with the retention flange 44 maintaining the assembly together. In order to allow relatively easy disassembly of the sparger 32 from the supply pipe 42, an annular release collar 56 as illustrated in FIGS. 5 and 7 is loosely or slidably disposed around the supply pipe 42 adjacent to and below the retention flange 44 and the fingers 46b. The release collar 56 includes a frustoconical, or simply conical cam surface 56a for selectively engaging the fingers 46b upon longitudinal upward translation thereof to displace the fingers 46b radially outwardly from the retention flange 44 for disengagement therewith as illustrated in phantom line in FIG. 7. As illustrated in FIG. 7, the hook ramp 54b is also configured for engagement with the release collar cam surface 56a upon translation of the cam surface 56a upwardly against the several ramps 54b to expand radially outwardly the fingers 46b to disengage the hooks 54 from the outer ledge 44a for removing the inlet pipe 40 and the sparger 32 from the supply pipe 42. As shown in FIGS. 5 and 7, an annular support collar 58 is fixedly joined to the supply pipe 42, on the elbow 42a, by welding for example, and below the release collar 56 for supporting the release collar 56 and maintaining it in ready position. Accordingly, when desired, the release collar 56 may be manually translated upwardly, using suitable pneumatic jacks for example, to spread apart the fingers 46b and release the coupling 46 from the retention flange 44 to remove the sparger 32. As illustrated in FIG. 5, the retention flange 44 is preferably sized to fit completely within the coupling 46 axially between the band 46a and the hooks 54 and radially inwardly of the beams 52. In this way, a compact joint is created which does not reduce the inner diameter or flow area between the supply pipe 42 and the inlet pipe 40. The various components of the sparger assembly 26 are made of conventional metals for the nuclear environment. However, in a preferred embodiment of the present invention, the coupling 46 preferably is made of a material such as conventional Inconel X-750, which has a lower coefficient of thermal expansion than the materials of the supply pipe 42 and the inlet pipe 40 cooperating therewith so that differential thermal expansion therebetween upon heating thereof in the reactor environment will additionally compress the seal 50 for increasing its effectiveness. In this way, the fingers 46b will expand less than the supply pipe 42 and the inlet pipe 40 between the coupling band 46a and the hooks 54 to tighten the seal joint during operation upon heating thereof. Although the coupling 46 is joined to the inlet pipe 40 and the retention flange 44 is joined to the supply pipe 42 in the preferred embodiment, they may be interchanged in an alternate embodiment as shown in FIG. 8. In this embodiment, the retention flange 44A is integral with the distal end of the inlet pipe 40, the coupling 46A is joined to the supply pipe 42 by suitable pins 60, and the release collar 56A surrounds the inlet pipe 40. The joint still functions the same in this embodiment. While there have been described herein what are considered to be preferred and exemplary embodiments of the present invention, other modifications of the invention shall be apparent to those skilled in the art from the teachings herein, and it is, therefore, desired to be secured in the appended claims all such modifications as fall within the true spirit and scope of the invention. Accordingly, what is desired to be secured by Letters Patent of the United States is the invention as defined and differentiated in the following claims:
053735382	claims	1. A system for detecting a substance liable to be contained in an object, comprising: a source of irradiation to irradiate said object with neutrons; at least one gamma radiation detector to detect gamma radiation emitted by said object; an electronic processor to process signals supplied by said gamma radiation detector, said electronic processor being provided for: counting the gamma photons corresponding to each line i of a plurality of characteristic lines of at least one chemical element of said substance; determining, for each line i, a false detection probability PFi for the chemical element associated with said line, wherein the probability PFi is the probability that the detected signal, corresponding to the said line i, is due to a background noise; determining the product of these false detection probabilities; comparing said product with a threshold fixed by the system user; and notifying said user that the product is below the threshold fixed by said user, the object then being assumed to contain the substance. determining, for each line i, an information quantity Ii relative to line i and defined by the formula: ##EQU11## determining the sum of these information quantities; comparing said sum with a threshold fixed by the system user; and notifying said user if said sum exceeds the threshold with which it is compared, the object then being assumed to contain the substance. determining, for each line i, an information quantity Ii relative to said line i and defined by the formula: ##EQU12## in which K and a are stored functions of a background noise M'2i relative to the line i and N1i is the integral part of the difference Ni-M'2i, Ni representing the count, during a time Dt, which corresponds to the line i and which is due to nuclear reactions induced by neutrons and also to the background noise M'2i relative to the line i and for the time Dt; determining the sum of these information quantities; comparing said sum with a threshold fixed by the system user; and notifying said user if said sum exceeds the threshold with which it is compared, the object then being assumed to contain the substance. irradiating the object with an irradiation source; detecting gamma radiation emitted by said object with a detector; processing the signal supplied by said detector, said processing including: counting the gamma photons corresponding to each line i of a plurality of characteristic lines of at least one chemical element of the substance; determining, for each line i, a false detection probability PFi for the chemical element associated with said line, wherein the probability PFi is the probability that the detected signal, corresponding to the said line i, is due to a background noise; determining the product of these false detection probabilities; comparing said product with a threshold fixed by the system user; and notifying said user of the product is below the threshold fixed by them, the object then being assumed to contain the substance. determining, for each line i, an information quantity Ii relative to line i and defined by the formula: ##EQU14## determining the sum of these information quantities; comparing said sum with a threshold fixed by the system user; and notifying said user if said sum exceeds the threshold with which it is compared, the object then being assumed to contain the substance. determining, for each line i, an information quantity Ii relative to said line i and defined by the formula: ##EQU15## in which K and a are stored functions of a background noise M'2i relative to the line i and N1i is the integral part of the difference Ni-M'2i, Ni representing the count during a time Dt, which corresponds to the line i and which is due to nuclear reactions induced by neutrons and also to the background noise M'2i relative to the line i and for the time Dt; determining the sum of these information quantities; comparing said sum with a threshold fixed by the system user; and notifying said user if said sum exceeds the threshold with which it is compared, the object then being assumed to contain the substance. 2. The system according to claim 1, wherein each probability PFi is determined by the formula: ##EQU10## in which Ni represents the count during a time Dt, which corresponds to the line i and which is due to the nuclear reactions induced by the neutrons and also to a background noise M'2i relative to the line i and for the time Dt. 3. The system according to claim 2, wherein each background noise M'2i is determined by forming the sum of a physical background noise M2i, relative to the line i, and the upper limit Ci of counts relative to the said line i, during the time Dt, on objects liable to contain the substance, but known not to contain the substance. 4. The system according to claim 1, wherein said electronic processor is provided for: 5. The system according to claim 1, wherein the electronic processor is provided for: 6. The system according to claim 1, wherein the irradiation source comprises a fast neutron source and an enclosure for thermalizing these fast neutrons, in which is located the source and which serves to receive the object. 7. The system according to claim 1, wherein the irradiation incorporates a fast neutron source for irradiating the object. 8. The system according to claim 1, wherein said detector comprises a plurality of gamma radiation detectors and that the electronic processor comprises a plurality of detection chains respectively associated with the detectors. 9. The system according to claim 1, wherein said gamma radiation detector is a high resolution detection means. 10. The system according to claim 1, wherein the gamma radiation detector is protected from direct radiation from the irradiation source and wherein said irradiation source is a source of neutrons and said neutrons are collimated towards said object. 11. The system according to claim 1, wherein irradiation source comprises a pulsed neutron source for supplying neutron bursts and wherein said electronic processor cooperates with the detector in order to carry out measurements in time intervals during which it is certain that detection will only take place of one of the categories of gamma photons produced during the irradiation of the object by neutrons. 12. The system according to claim 1, wherein the irradiation source comprises a source of 14 MeV neutrons produced by fusion reactions. 13. A process for detecting a substance liable to be contained in an object, comprising: 14. The process according to claim 13, wherein each probability PFi is determined by the formula: ##EQU13## in which Ni represents the count during a time Dt, which corresponds to the line i and which is due to the nuclear reactions induced by the neutrons and also to a background noise M'2i relative to the line i and for the time Dt. 15. The process according to claim 14, wherein each background noise M'2i is determined by forming the sum of a physical background noise M2i, relative to the line i, and the upper limit Ci of counts relative to the said line i, during the time Dt, on objects liable to contain the substance, but known not to contain the substance. 16. The process according to claim 13, wherein the processing includes: 17. The process according to claim 13, wherein the processing includes: 18. The process according to claim 13, wherein the object is irradiated by a source including a fast neutron source, and further including an enclosure for thermalizing these fast neutrons, and which serves to receive the object. 19. The process according to claim 13, wherein the irradiation source incorporates a fast neutron source for irradiating the object. 20. A process according to claim 13, wherein the detector comprises a plurality of gamma radiation detectors and that the processing comprises a plurality of detection chains respectively associated with the detectors, and wherein the irradiation source comprises a pulsed neutron source for supplying neutron bursts and in that the electronic processor cooperates with the detector in order to carry out measurements in time intervals during which it is certain that detection will only take place for one of the categories of gamma photons produced during the irradiation of the object by neutrons.
055641040	summary	FIELD OF THE INVENTION This invention relates to the processing of liquid radioactive waste containing radioactively labeled biological molecules. More specifically, this invention relates to the use of solid phase binders to remove radioactively labeled biological molecules from liquid radioactive waste solutions. BACKGROUND OF THE INVENTION There is widespread use of radioactively labeled biological molecules in research, medicine, industry and for environmental testing. For example, a variety of assays employing radiolabled biological molecules are used in biological research and medicine. For instance, there are many different types of immunoassays used in clinical laboratories and in research. There are also a many clinical assays and research procedures using radioactively labeled nucleic acids. A number of different isotopes are used in these different applications including .sup.14 C, .sup.3 H, .sup.125 I, .sup.131 I, .sup.32 P and .sup.57 Co. Many of the assays using radioactively labeled biological molecules generate relatively large volumes of low level radioactive waste, which then become a disposal problem. For example, in a typical radioimmunoassay procedure, small amounts of radioactively-labeled material are dispersed into liters of aqueous or organic solutions. These solutions often contain relatively low levels of radioactivity, but nonetheless must be disposed of as radioactive waste according to federal and state regulations. Disposal of large volumes of low level radioactive liquid waste generated by radioimmunoassays and other procedures is particularly expensive and difficult. Transportation of radioactive waste materials to federal waste disposal sites has become increasingly difficult and expensive. Disposal of low level liquid radioactive waste by transportation to radioactive waste disposal sites is also an inefficient use of space at these sites. Therefore, most institutions try to reduce or eliminate disposal of radioactive waste by this method. An additional method of radioactive waste disposal involves storing the radioactive waste material on site until the material is no longer radioactive. Fortunately, some of the most commonly used radioisotopes, such as .sup.125 I and .sup.57 Co, have relatively short halflives. Because of this, some institutions store radioactive waste containing such isotopes until the waste is no longer radioactive, and then dispose of the waste as nonradioactive material. However, it is difficult to store large volumes of low level radioactive liquid waste for a period of months or years. There is a need for methods to remove the radioactively labeled biological molecules in concentrated form from liquid radioactive waste solutions. If this can be accomplished, the concentrated radioactively labeled biological molecules can then more feasibly be stored on site until the radioactivity decays and the waste becomes nonradioactive. Alternatively, the amount of radioactive waste material that must be transported to a radioactive waste disposal site can be dramatically reduced. In either case, the expense associated with liquid radioactive waste disposal can be markedly decreased. SUMMARY OF THE INVENTION This invention provides for methods of removing radioactively labeled biological molecules from liquid radioactive waste solutions. The liquid radioactive waste solution is contacted with a solid phase binder to form a solid phase binder:radioactively labeled biological molecule complex, which is then separated from the liquid radioactive waste solution. The radioactively labeled biological molecule can be labeled with a gamma emitting radioisotope such as .sup.125 I or .sup.57 Co. Examples of .sup.125 I-labeled biological molecules include .sup.125 I thyroxine and .sup.125 I folate. .sup.57 Co vitamin B12 is an example of a .sup.57 Co-labeled biological molecule. More than one radioactively labeled biological molecule can be removed from a liquid radioactive waste solution, by more than one solid phase binder. A variety of different solid phase binders can be added to a liquid radioactive waste solution to form the solid phase binder:radioactively labeled biological molecule complex. For example, the solid phase binder can be a solid phase adsorbent, such as talc, glass wool, glass beads or a charcoal adsorbent. As an additional example, the solid phase binder can be a solid phase immunochemical binder. Preferably, the solid phase immunochemical binder is an antibody attached to a solid phase. An antibody in liquid phase can be added to a liquid radioactive waste solution to bind to a radioactively labeled biological molecule. The liquid phase antibody is then bound by a solid phase immunochemical binder to form the solid phase binder:radioactively labeled biological molecule complex. The solid phase binder:radioactively labeled biological molecule complex can be removed from the liquid radioactive waste solution in a variety of ways. For example, the solid phase binder can be present in a column and the liquid radioactive waste solution can be passed through the column. The solid phase binder in the column can be, for example, a mixture of celite and charcoal or a polymer resin containing adsorbent particles, such as adsorbent charcoal particles. The column solid phase binder can also be an immunochemical binder, such an antibody attached to a glass bead. This invention further provides for methods of removing radioactively labeled biological molecules from liquid radioactive waste solutions by contacting a magnetizable particle binder with a liquid radioactive waste solution to form a magnetizable particle binder:radioactively labeled biological molecule complex. The complex is then separated from the liquid radioactive waste solution. For instance, the magnetizable particle binder can be adsorbent particles, such as charcoal adsorbent particles, attached to a magnetizable polymer, such as a magnetizable polyacrylamide gel. For example, charcoal particles can be entrapped in a magnetizable polyacrylamide gel to form a magnetizable particle binder. This magnetizable particle binder can be used, for example, to remove .sup.125 I folate and .sup.57 Co vitamin B12 from a liquid radioactive waste solution. The magnetizable particle binder can also be, for example, a magnetizable particle immunochemical binder, such as an antibody attached to a magnetizable polymer. An antibody in liquid phase can also be added to a liquid radioactive waste solution to bind to a radioactively labeled biological molecule. The liquid phase antibody is then bound by a magnetizable particle immunochemical binder to form the magnetizable particle binder:radioactively labeled biological molecule complex. For example, a mouse antithyroxine antibody can be added in liquid phase to a liquid radioactive waste solution to bind .sup.125 I thyroxine. The liquid phase antibody is then bound with a magnetizable particle binder containing a sheep antimouse antibody, in order to remove the .sup.125 I thyroxine from the liquid radioactive waste solution.
	summary
044906161	abstract	A shield used to prevent an excessive amount of radiation to be absorbed by a patient during a cephalometry procedure. The shield consists of a lead sheet which is supported by a cephalometric head holder. A hole is provided in the shield for cooperation with the cephalometric head holder to insure proper positioning of the shield. Additionally, a brad, staple, screw or the like is used to insure that the head holder remains immobile during the cephalometry procedure.
	description	The present application is a national phase entry under 35 U.S.C. § 371 of PCT/CN2019/106665 filed on Sep. 19, 2019 which claims priority to Chinese Patent Application No. 2018116440391, filed on Dec. 30, 2018, entitled “Spherical Element Detecting and Positioning Device”, each of which is incorporated herein by reference in its entirety. The present application relates to the field of reactor engineering technologies, and particularly to a spherical element detecting and positioning device. A pebble bed high temperature gas-cooled reactor employs the on-line continuous multi-pass refueling strategy with spherical fuel elements, the running and operating of a fuel loading and unloading system will directly affect the reactivity change of the reactor. An on-line burnup measurement device measures the burnup of the fuel elements unloaded from the core. The elements that have not reached the target burnup are returned to the core, and the spent fuel elements that have reached the target burnup level are unloaded into a spent fuel storage tank. The HTR-10 high temperature gas-cooled experimental reactor is equipped with an lifter at the downstream of a damage fuel separator to cooperate with the burnup measurement device to perform burnup measurement. The lifter performs dual functions of positioning distribution of burnup measurement and pneumatic conveyance. The lifter has to be interlocked with the damage fuel separator at the upstream, and it is greatly affected by the downstream airflow, therefore it cannot meet the operating requirements for the burnup measurement and directional conveyance of a large number of spherical elements in commercial power plants. In order to meet the high-frequency cycling requirement of the core fuel elements, equipment assemblies and pipes for performing functions of pipeline temporary storage, single conveyance, positioning of burnup measurement, directional distribution, pneumatic conveyance, and etc. are arranged on the pebble bed modular high temperature gas-cooled reactor commercial nuclear power plants after core unloading and crushed spheres sorting, so as to decouple the burnup measurement from the functions of core unloading and pneumatic conveyance, thereby improving the reliability of the system, equipment and control. A device for accurately positioning the spherical elements to be measured is disposed at the burnup measurement point of the fuel loading and unloading system, and is matched with a collimator of the burnup measurement device, so that a high-activity y spectrometer can be used to measure the burnup on-line. Since the on-line burnup measurement is based on the y-spectrum energy of the relevant nuclides, the radiation effects of adjacent spherical elements must be excluded. On the other hand, the measurement times of the spherical elements with different burnup are different, while the unloading speed of the upstream unloading device is basically constant. Therefore, a certain number of spherical elements must be temporarily stored in the pipe sections waiting for burnup measurement. In order to accurately measure the burnup of the spherical elements one by one to ensure the reliability and stability of automatic operations such as unloading, burnup measurement, directional conveyance and etc., in addition to the radiation measurement device and the distributor, corresponding spherical element control device must be arranged at the upstream of the sphere flow pipeline. Burnup measurement is a key process for the automatic operation of the fuel loading and unloading system and even the pebble bed high temperature reactor, and it involves a plurality of devices mentioned above and many control points. These devices work in a high-temperature, high-pressure, and radioactive helium environment. Especially, for the single conveyor or the spacer conveyor, the burnup measurement positioner and the steering gear, the daily number of operations reaches 3000, 3000 and 200 times respectively in an HTR-PM demonstration project, which brings great challenges to the thermal fit and tolerance of the moving parts, friction and wear of the shafting with the oil-free lubricant bearings, the sealing of highly permeable helium at the pressure boundary, the interlocking control of the devices and fault tolerance, etc. One objective of the present disclosure is to provide a spherical element detecting and positioning device that can achieve triple functions of automatic material separation, precise positioning and directional conveyance of spherical elements. In order to solve the technical problem above, the present disclosure provides a spherical element detecting and positioning device, including a pressure-bearing casing, an internal member and an execution part; the pressure-bearing casing includes a tank body, one sphere inlet adapter pipe and two sphere outlet adapter pipes respectively arranged on the tank body; one rotor counter-bored hole, one collimating counter-bored hole, one sphere inlet through hole and two sphere outlet through holes are arranged in the tank body; the sphere inlet through hole communicates with the sphere inlet adapter pipe, the two sphere outlet through holes correspondingly communicate with the two sphere outlet adapter pipes, respectively, and the sphere inlet through hole and the sphere outlet through hole respectively communicate with the rotor counter-bored hole; the internal member is arranged in the rotor counter-bored hole, and includes a lining ring which is a ring structure with a notch, both ends of the lining ring are connected with an arc-shaped limit ring; a cross-section of the limit ring is smaller than that of the lining ring, and a rotation gap is provided between an outer surface of the limit ring and an inner surface of the rotor counter-bored hole; the limit ring is provided with a sphere inlet hole passage which communicates with the sphere inlet through hole; the lining ring is provided with two sphere outlet hole passages that are correspondingly in communication with the two sphere outlet through holes respectively; the execution part includes a turntable and two support lugs; the turntable is arranged in the lining ring of the internal member and is able to rotate within the lining ring; a sphere-passing through hole penetrating in a radial direction is provided in the turntable, and the two support lugs are mounted on the front and back sides of the sphere-passing through hole, and the two support lugs are able to rotate in the rotation gap; the two support lugs are both in inverted L shape and opposite to each other, and an isolation space is provided between the two support lugs; a side corresponding to the collimating counter-bored hole of the turntable is provided with a thinning groove; when the turntable is at a detecting position, a groove bottom surface of the thinning groove is parallel to a bottom surface of the collimating counter-bored hole, and a projected circle of the collimating counter-bored hole on the bottom surface of the thinning groove is enveloped by the bottom surface of the thinning groove. Specifically, the execution part further includes a rotating shaft connected to the turntable through a spline. Specifically, a limit groove is provided on the turntable, and a limit post matching the limit groove is provided on the tank body. Specifically, the pressure-bearing casing further includes an end face flange connected to the tank body through a first fastening assembly, and a first sealing assembly is provided between the end face flange and the tank body. Further, the device also includes a transmission part including an outer magnetic assembly, an isolation hood arranged in the outer magnetic assembly, and an inner magnetic assembly arranged in the isolation hood; the rotating shaft is arranged in the inner magnetic assembly. Specifically, the transmission part further includes a support arranged outside the outer magnetic assembly; the support is connected to the end face flange through a second fastening assembly, and the isolation hood cooperates with the support through a flange. Specifically, a second sealing assembly is provided between the end face flange and the transmission part. Further, the device also includes a power part including a motor, a reducer connected to the motor, and a coupling connected to the reducer; the coupling is connected to the rotating shaft. Specifically, the power part further includes a shield sleeve in which the motor, the reducer and the coupling are arranged. Specifically, the shield sleeve is connected and fixed to the support. The technical solutions above of the present disclosure have the following advantages. The spherical element detecting and positioning device provided by the present disclosure uses a turntable with support lugs and a sphere-passing through hole to achieve the separation and single conveyance functions of the spherical elements in strings, so as to eliminate the mutual influence between adjacent spherical elements. By arranging the thinning groove on the turntable and arranging the collimating counter-bored hole in the tank body, the accurate positioning is achieved and thus the cooperative measurement precision is ensured. Through the cooperative arrangements of the spherical element conveying passages between the pressure-bearing casing, the internal member and the execution part, the directional distribution of the spherical elements after detection is achieved. The spherical element detecting and positioning device provided by the present disclosure integrates the functions of material separation, single conveyance, measurement positioning, directional distribution and etc. Compared with the prior art, the spherical element detecting and positioning device has compact structure, small space occupation, significantly reduced IO control points, saved cost and higher operational reliability. Compared with the existing lifter, the spherical element detecting and positioning device provided by the present disclosure has a high operation efficiency, has no jamming impact and zero drift, no control logic interlocking, and is not affected by the upstream sphere flow conveying speed and the downstream air flow. Therefore, the operational reliability and maintenance safety are higher. In the drawings: 100 power part; 101 AC servo motor; 102 planetary gear reducer; 103 shield sleeve; 104 metal coupling; 200 transmission part; 201 outer magnetic assembly; 202 support; 203 inner magnetic assembly; 204 isolation hood; 205 second fastening assembly; 206 second sealing assembly; 207 flange; 300 execution part; 301 spline; 302 rotating shaft; 303 first bearing; 304 support lug; 305 turntable; 306 sphere-passing through hole; 307 second bearing; 308 thinning groove; 309 limit groove; 310 support surface; 400 pressure-bearing casing; 401 end face flange; 402 first fastening assembly; 403 first sealing assembly; 404 rotor counter-bored hole; 405 sphere inlet adapter pipe; 406 tank body; 407 collimating counter-bored hole; 408a first sphere outlet adapter pipe; 408b second sphere outlet adapter pipe; 409 sphere inlet through hole; 410a first sphere outlet through hole; 410b second sphere outlet through hole; 500 internal member; 501 lining ring; 502 bearing press plate; 503 bearing seat; 504 positioning pin; 505 limit ring; 506 sphere inlet hole passage; 508a a first sphere outlet hole passage; 508b second sphere outlet hole passage; 509a first eccentric hole passage; 509b second eccentric hole passage; 510 sphere stop surface; 600 spherical element; 601 first spherical element; 602 second spherical element; 603 third spherical element. In order to make the objectives, technical solutions, and advantages of the embodiments of the present disclosure clearer, the technical solutions of the embodiments of the present disclosure will be clearly and completely described with reference to the accompanying drawings of the embodiments of the present disclosure. Obviously, the described embodiments are part but not all of the embodiments of the present disclosure. Based on the embodiments of the present disclosure, all other embodiments obtained by a person of ordinary skill in the art without creative efforts shall fall within the protection scope of the present disclosure. As shown in FIG. 1 to FIG. 8, the embodiments of the present disclosure provide a spherical element detecting and positioning device, including a power part 100, a transmission part 200, an execution part 300, a pressure-bearing casing 400, and an internal member 500. The power part 100 comprises an AC servo motor 101, a planetary gear reducer 102, a shield sleeve 103, and a metal coupling 104. Since the AC servo motor 101 has a good torque-frequency characteristic, and its equipped rotary transformer has high-precision resolution, the rotational speed and the rotational angle are precisely controlled by controlling the driver and the rotary transformer to perform rotational angle feedback. The reducer is configured to provide the output torque to ensure the smooth movement of the actuator. Therefore, the servo system can be ensured to meet the rotational angle control requirements of frequent start-stops, smooth operating, and accurate output shaft positioning. The shield sleeve 103 is a steel integrally machined piece, one end of which is positioned with a support 202 of the magnetic transmission part, and is rooted by being supported on the equipment steel frame or the steel platform. The AC servo motor 101 and the planetary gear reducer 102 are disposed in the shield sleeve 103, so as to limit the radial γ-ray cumulative dose of the spherical elements in the surrounding sphere flow pipelines to the electrodes and the reducer. The transmission part 200 is a cylindrical magnetic transmission with a lag angle of less than 0.2°, and includes a support 202, an outer magnetic assembly 201, an isolation hood 204, an inner magnetic component 203, and etc. The titanium alloy isolation hood 204 is limited and pressed by a flange 207 and the coaxially mounted support 202 flange, and is fastened to an end face flange 401 of the pressure-bearing casing 400 through a second fastening assembly 205 and a second sealing assembly 206, so as to form a complete pressure-bearing boundary together with a tank body 406. The outer magnetic assembly 201 is connected to the planetary gear reducer 102 through a metal coupling 104; the inner magnetic assembly 203 is connected to a rotating shaft 302 of the execution part 300 through a spline. Under the instructions from the nuclear power plant DCS main control system and the servo control driver, the reducer 102 directly connected to the AC servo motor 101 drives the outer magnetic assembly 201 to rotate synchronously. Under the effect of magnetic coupling, the magnetic field penetrates the isolation hood 204 and drives the inner magnetic assembly 203 and the execution part 300 directly connected thereto to rotate synchronously, so as to achieve the flexible mechanical transmission under a non-contact condition, and to transform the dynamic sealing into a static sealing, which not only achieves the sealing of radioactive hot helium, but also improves the operating environment of the power part 100. During the burnup measurement, both the spherical elements positioned in a through hole 306 of a turntable and on a sphere stop surface 510 of a lining ring 501 of the internal member 500, and the spherical elements 600 in strings stopped on a support surface 310 of the turntable have very strong radioactivity. The magnetic transmission adopts a slim and compact cylindrical structure, and the outer magnetic assembly 201 and the inner magnetic assembly 203 of the magnetic transmission have sufficient shielding thickness in the radial direction in addition to the sufficient shielding thickness in the longitudinal direction, so that the power part 100 can be protected from excessively y-ray cumulative radiation dose caused by short-time sphere stop. Since the power part 100 is subjected to relatively small oblique instantaneous radioactive radiation during the flow of the spherical elements, a shield sleeve 103 with a small thickness is only needed. The execution part 300 comprises a rotating shaft 302, a turntable 305, support lugs 304, and two bearings 303 and 307, as shown in FIG. 4. The rotating shaft 302 and the turntable 305 are an integrally machined piece; the turntable 305 includes a sphere-passing through hole 306; the support lugs 304 each have a shape of “Γ”, and have two pieces in total, which are made of high-strength and wear-resistant metal and mounted at both sides of the sphere-passing through hole 306 of the turntable 305 in a mirroring manner, for separating the spherical elements at the lowest end and supporting the spherical elements in strings. A support surface 310 of the sphere-passing through hole 306 and the support lugs 304 is a wear-resistant surface for supporting the spherical elements in strings. The turntable 305 is placed in the lining ring 501 of the internal member 500, and is supported in a bearing seat 503 of the internal member 500 and a rotor counter-bored hole 404 of the tank body 406 by a first bearing 303 and a second bearing 307, respectively. The pressure-bearing casing 400 includes the end face flange 401, the tank body 406, a sphere inlet adapter pipe 405 and a sphere outlet adapter pipe 408. The tank body 406 includes one rotor counter-bored hole 404, one sphere inlet through hole 409, a first sphere outlet through hole 410a, a second sphere outlet through hole 410b and one collimating counter-bored hole 407. The sphere inlet adapter pipe 405 coaxially communicates with the sphere inlet through hole 409, the first sphere outlet adapter pipe 408a coaxially communicates with the first sphere outlet through hole 410a, and the second sphere outlet adapter pipe 408b coaxially communicates with the second sphere outlet through hole 410b. The end face flange 401 is configured to support the magnetic transmission, and is tightly connected to the tank body 406 through a first fastening assembly 402 and a first sealing assembly 403. By disassembling the end face flange 401, the execution part 300 and the internal member 500 can be conveniently installed, disassembled, repaired and replaced. The internal member 500 comprises the lining ring 501, a bearing press plate 502, the bearing seat 503 and a positioning pin 504. As shown in FIG. 5, the lining ring 501 includes a limit ring 505, a sphere inlet hole passage 506, a first sphere outlet hole passage 508a and a second sphere outlet hole passage 508b. The bearing press plate 502 and the bearing seat 503 are configured to fix and support the first bearing 303 of the execution part 300. The positioning pin 504 is configured to limit and fix the bearing seat 503 together with fasteners. The internal member 500 is disposed in the rotor counter-bored hole 404 of the tank 406, and the sphere inlet hole passage 506, the sphere inlet through hole 409 and the sphere inlet adapter pipe 405 coaxially communicate. The first sphere outlet hole passage 508a, the first sphere outlet through hole 410a, and the first sphere outlet adapter pipe 408a coaxially communicate. The second sphere outlet hole passage 508b, the second sphere outlet through hole 410b and the second sphere outlet adapter pipe 408b coaxially communicate. An axis of the sphere inlet through hole 409 of the tank 406 and the collimating counter-bored hole 407 intersect perpendicularly at one point. When the spherical elements 600 stop steadily in the sphere stop surface 510 of the lining ring 501 and the sphere-passing through hole 306 of the turntable 305, the measurement precision is the highest when a spherical center of the spherical element 600 coincides with the intersection point. When the parts are being installed and the equipment is operating, the spherical center of the stopped sphere should be substantially coincident with the intersection point. During the burnup measurement, detecting rays with good directivity and a certain intensity are emitted through the external burnup measurement and reach the detecting and positioning device, coincide with the axis of the collimating counter-bored hole 307 and penetrate a wall of the collimating counter-bored hole until they steadily stop at the spherical center of the spherical element 600 on the sphere stop surface 510 of the lining ring 501. In order to ensure the measurement precision, the error between the position of the spherical center and the collimating detecting ray is required to be within 1 mm, and the effective diameter of the collimating counter-bored hole is required to be equal to a diameter of the spherical element, and the equivalent wall thickness of the structural steel in the collimating direction is required to be 15 mm or less. In addition, a distance h between adjacent spherical elements must be greater than 200 mm to eliminate the mutual influences between the spherical elements. As shown in FIG. 1, the diameter of the spherical element is φ61. In order to ensure a smooth sphere flow, an inner diameter of a sphere-passing pipe or a sphere hole passage that relies on gravity for flowing is usually φ65. In this embodiment, in order to ensure an accurate positioning of the spherical element and reduce the measurement errors, a diameter d1 of the sphere-passing through hole 306 of the turntable 305 is set to be φ61, and the sphere inlet through hole 409 of the tank body 406 and the sphere-passing through hole 306 have the same diameter. In addition, a tapered section is provided on the sphere inlet adapter pipe 405 in the pressure-bearing casing 400, and the small end thereof is connected to the sphere inlet through hole 409 of the tank body 406, and has a same diameter with the sphere inlet through hole 409, so as to guide the spherical elements to flow. In order to meet the requirements of the equivalent diameter and the equivalent wall thickness in the collimating direction, a diameter d4 of the collimating counter-bored hole 407 of the tank body 406 in this embodiment is 60 mm. A thinning groove 308 is provided on one side of the turntable 305 near the collimating counter-bored hole 407 of the tank body. When the turntable 305 is located at the burnup measurement position, a groove bottom surface of the thinning groove 308 is parallel to a bottom surface of the collimating counter-bored hole 407, and a projected circle of the collimating counter-bored hole 407 on the bottom surface of the thinning groove 308 is enveloped by the groove bottom surface of the thinning groove 308, and is in the direction of the axis of the collimating counter-bored hole 407. The effective collimating thicknesses d2 and d3 are 15 mm. When being in the measurement sphere stop position, the spherical elements in strings are separated by the support lugs 304 and located on a top surface of the support lugs 304, and a distance to the sphere stop surface 510 of the lining ring 501 is h which is about 250 mm in this embodiment. When h is too large, the detecting and positioning device is oversized. In order to ensure that the support lugs 304 can smoothly separate the spherical elements in strings, and do not damage the spherical elements, and to ensure the debris to smoothly pass, the structure, size and arrangement of the support lugs 304 need to be limited. In this embodiment, a height h2 of the support lugs 304 is equivalent to the diameter of the spherical element, so that transverse plates of the support lugs 304 can precisely pass through a gap of the brightest spherical elements. Since the support lug 304 is in the inverted L shape, if the transverse plates are too wide, it may touch the spherical elements instead of passing through the gap between two spheres; if the transverse plates are too narrow, the strength and rigidity are insufficient. Therefore, in this embodiment, a width d6 of the support lug 304 is slightly greater than a radius of the spherical element. In addition, in this embodiment, the minimum gap d5 between the two support lugs 304 is 20 mm, which is not only convenient for separating the spherical elements, but also can effectively ensure that the debris passes through the gap and enters the sphere-passing through hole 306. Since the support lugs 304 are distributed at both sides of the turntable 305 in a mirroring manner, in order to facilitate the installation of the turntable 305, a width d7 of the sphere inlet hole passage of the lining ring 501 must be smaller than the spherical elements to restrict the flow of the spherical elements, meanwhile d7 must be greater than the width d6 of the support lugs 304 so as to ensure the smooth assembly and disassembly of the turntable and the support lugs. In this embodiment, the width d6 of the support lug and the width d7 of the sphere inlet hole passage are 30 mm and 40 mm, respectively. In order to avoid possible dust and debris from depositing on the sphere stop surface 510 of the lining ring 501, the spherical elements to be detected are raised, without affecting the accuracy of the measurement result. A first eccentric hole passage 509a and a second eccentric hole passage 509b connected to each other can be respectively provided on the first sphere outlet hole passage 508a and the second sphere outlet hole passage 508b of the lining ring 501. The sphere stop surface 510 is polished from a concave cylindrical surface to a flat surface or a convex surface. When falling from the sphere-passing through hole 306 of the turntable, the dust or the debris will not be temporarily stored on the sphere stop surface 510 but will directly slip from the eccentric hole passages. In addition, the tank body 406 and the rotor of turntable 305 are respectively provided with a limit post and a limit groove 309 which are matched, and an angle of the limit points at both ends is 60°. On the one hand, the movement range of the rotation angle of the turntable 305 can be limited, and on the other hand, it is convenient for the AC servo system to use its torque mode to achieve the position calibration so as to ensure the positioning precision of the positioning distributor. The first bearing 303 and the second bearing 307 of the execution part 300, and the internal bearing of the magnetic transmission are heat-resistant and wear-resistant alloy bearings with polyimide cages. The polyimide cage having radiation resistance and self-lubrication properties provides a solid lubricating film, and the heat-resistant and wear-resistant alloy has better plasticity and toughness than ceramic bearings, thereby meeting the long-life operation requirements of bearing temperature resistance and radiation resistance. According to the burnup measurement results, the detecting and positioning device according to the present disclosure operates in a short-term continuous working mechanism under the DCS instruction, and its cyclic working process is: receiving spherical elements→rotating and separating the spherical elements→positioning measurement→directionally distributing→receiving the spherical elements, the working principle is shown in FIG. 6 to FIG. 8. In FIG. 6, the turntable 305 is in a static sphere receiving position. At this time, the sphere-passing through hole 306 and the support lugs 304 are located at a left limit point or a right limit point, and the spherical elements from the upstream will be temporarily stored in series in the sphere inlet adapter pipe 405 and the sphere inlet through hole 409 of the tank body, and be supported by the support surface 310 of the turntable. The turntable 305 starts to rotate after receiving the instruction. The support lugs 304 pass through the gap between the spherical elements 601 and 602. When the turntable reaches a middle position, the spherical elements 602 and 603 in series are lifted up, meanwhile the separated spherical element 601 enters the sphere-passing through hole 306 of the turntable under gravity, and stops on the sphere stop surface 510 of the lining ring 501, as shown in FIG. 7. After the spherical elements stop steadily, the burnup measurement can be performed. During the measurement, the spherical elements from the upstream will rest on the spherical element 603 and be supported by the support lugs 304. After the burnup measurement is completed, according to the measurement results and the DCS instructions, the turntable is turned to the left or to the right, and the measured spherical elements are directionally conveyed to the pipeline in the direction of the core or the spent fuel storage. At the same time, the turntable is returned to the sphere receiving position, and the spherical elements 602 and 603 in series drop onto the support surface 310 of the turntable, as shown in FIG. 8. In summary, the spherical element detecting and positioning device described in the embodiments of the present disclosure can achieve triple functions of performing automatic material separation, precise positioning and directional conveyance of spherical fuel elements, has compact structure and simple control, and can meet the operation reliability and maintainability requirements for long-term and intermittent operation under the strong radioactive environment. In the description of the present disclosure, it should be noted that, the terms “connected with” and “connected to” should be understood in a broad sense unless otherwise specified and limited, for example, they may be fixed connections, detachable connections, or integrated connections; they can be mechanical connections or electrical connections; they can be direct connections or indirect connections through intermediate mediums. For those of ordinary skill in the art, the specific meanings of the above terms in this disclosure can be understood according to specific situations. In the description of the present disclosure, unless otherwise stated, “several” means one or more; “multiple” means two or more. The orientation or position relations indicated by the terms “upper”, “lower”, “left”, “right”, “inner”, “outer” and etc. are based on the orientation or position relations shown in the drawings, and are only for the convenience of describing the present disclosure and simplifying the description, rather than indicating or implying that the referred device or element must have a specific orientation, be constructed and operated in a specific orientation, and therefore cannot be understood as limiting the present disclosure. Finally, it should be noted that the embodiments above are only used to illustrate rather than limit the technical solutions of the present disclosure. Although the present disclosure has been described in detail with reference to the foregoing embodiments, those of ordinary skills in the art should understand that they can still modify the technical solutions described in the various embodiments above, or equivalently replace some of the technical features thereof; and these modifications or replacements do not depart the essence of the corresponding solutions from the spirit and scope of the technical solutions of the various embodiments of the present disclosure.
054065950	description	DESCRIPTION OF THE PREFERRED EMBODIMENT A tubular lead-through in the form of a neutron detector housing arranged in the bottom of a reactor vessel in a nuclear power plant and with a seal designed according to the invention is shown in FIG. 1. A neutron detector housing 1 is, according to the invention, adapted to be closed and sealed off by means of a device comprising a cone 2 comprising a head 21 a rod-shaped part 22 and a sealing surface 23 arranged between the head 21 and the rod-shaped part 22, wherein the cone 2 is arranged with the head 21 inserted into the neutron detector housing 1, PA1 an annular flange 3 attached to the lead-through 1 and around the rod-shaped cone 2, inserted into the lead-through 1, for retaining the head 21 of the cone in the lead-through 1, whereby the annular flange 3 comprises a sealing surface 31, corresponding to the sealing surface 23 of the cone, in the form of a seat 31 with which the sealing surface 23 arranged on the cone is adapted to make contact to close and seal the lead-through 1, PA1 means for fixing and retaining the sealing surface 23, provided on the cone, to the seat-shaped sealing surface 31 in the form of a sealing washer 41 and a so-called neutron detector nut 42 comprising a teflon seal 43 and an intermediate drainage 44, PA1 the flush pipe 5 is connected to the cone 2, PA1 the flush pipe 5 is attached and a force is applied by means of the attachment member 55, whereby the cone 2 is retained in closed position with the sealing surface 23 of the cone sealingly making contact with the seat-shaped sealing surface 31, PA1 the means comprising a neumron detector nut 42 and a sealing washer 41, applied for fixing and retaining the cone, are detached and removed, the teflon seal 43 being already removed, PA1 temporarily during the mounting of the flush bottle 6, when the attachment 55 of the flush pipe has to be released, a nut divided into two parts is preferably mounted for fixing the cone 2, PA1 the attachment is detached such that the flush bottle 6 can be moved up over the flush pipe 5, PA1 the attachment 55 is again applied to the flush pipe 5 before the flush bottle 6 is moved up and is connected to the annular flange 3, PA1 the drainage connection 65 of the flush bottle 6 is connected, PA1 the attachment 55 is again detached and a member 56 for operation of the flush pipe 5 and the cone 2 is connected to the flush pipe 5; and PA1 flushing water is connected to the flushing water connection of the flush pipe 5. wherein the rod-shaped part 22 of the cone 2, in the end opposite to the head 21, comprises a member 24 for connecting the cone 2 to a flush pipe 5 arranged in the form of an extension of the rod-shaped part of the cone. The first end of the above-mentioned flush pipe 5, which end is fixed to the cone 2 by means of a connection member 24 arranged on the cone 2 and an attachment 51 arranged on the flush pipe, is provided with a plurality of holes 52, and the second end of the flush pipe is provided with means 54 for connection of flushing water and means 55 for connecting an attachment (not shown) by means of which a retaining force is applied to the flush pipe 5 and the cone 2 connected to the flush pipe. As shown in the figures, both the flushing water and the attachment can be connected by means of the same pin 54, 55 projecting from the flush pipe 5. During cleaning, the cone 2 and the connected flush pipe 5 are operated by means of an operating member 56. The second end of the flush pipe 5 is preferably made with a reduced diameter. In its free end, the above-mentioned annular flange 3 is provided with means 33 for connecting a flush bottle 6 arranged around the cone 2 and the flush pipe 5. In its first end the flush bottle 6 comprises means 62 for connection to the annular flange 3 and corresponding connection means 33 arranged on the annular flange 3. In the second end of the flush bottle, an internal sliding seal 64 is arranged for sealing against the flush pipe 5 and a drainage connection 65 is arranged for drainage of contaminated water. Before cleaning a neutron detector housing 1, which when no neutron detector is mounted is arranged with a seal according to the invention, the following steps are taken: While cleaning the detector housing 1, the flush pipe 5 and the cone 2 are operated by means of the connected operating member 56 which is capable of moving the flush pipe 5 up and down in the lead-through 1 and to rotate the flush pipe 5. In connection with the cone 2 being lifted by the operating member 56 and leaving the seat-shaped sealing surface 31, the supply of flushing water through the flush pipe 5 is opened immediately after the flush holes 52 have been maneuvered into the lead-through 1. The flushing proceeds while operating the flush pipe 5 with the cone 2 until it can be determined by activity measurement that the lead-through 1 has been cleaned from contaminated material. The cleaning can be made even more efficient by supplementing the equipment by means for mechanical cleaning by brushing, for example by means of a cleaning brush arranged between the flush pipe 5 and the cone 2. After completed cleaning, the supply of flushing water is closed while at the same time the sealing surface 23 arranged on the cone is again fixed to the seat-shaped sealing surface 31 and closes the seal 1. After that, the flush bottle 6 and the flush pipe 5 are removed while carrying out the above-mentioned operations in reverse order, the cone 2 again being fixed in the seat and retained by means of a sealing washer 41 and a neutron detector nut 42.
	description	The present application claims priority and the benefit of co-pending U.S. Provisional Patent Application Ser. No. 61/244,563 filed on Sep. 22, 2009, entitled “CABLE TENSIONING CYCLING SYSTEM”, which is incorporated herein in its entirety. The present embodiments generally relate to a hydraulically and/or electrically operated system for testing cable under variable tensions and speeds with lower input horsepower requirements. A need exists for a system that can cycle test long-length cable samples at variable cable tensions and speeds. A need exists for a system that can reduce the amount of horsepower required to cycle cable. A need exists for a closed loop tensioning system that can effectively close the loop and allow cable to be tensioned and cycled with less horsepower. The present embodiments meet these needs. The present embodiments are detailed below with reference to the listed Figures. Before explaining the present system in detail, it is to be understood that the system is not limited to the particular embodiments, and the system can be practiced or carried out in various ways. The present embodiments relate to a hydraulically and/or electrically operated system for testing cable under variable tensions and speeds with a lower input horsepower requirement. The present embodiments further relate to a hydraulic operated system that can include: a first storage reel, a second storage reel, a first moveable sheave, a second moveable sheave, a third moveable sheave, a fourth moveable sheave, a first clutch, a second clutch, a clutch controller, and a moveable tensioning moveable sheave. One or more embodiments relate to a long-length cable sample testing system. The system can utilize a parallel moveable sheave system and a hydraulically and/or electrically powered tensioning turning sheave assembly that allows for transfer of long-cable sample lengths at variable cable tensions and speeds with a low input horsepower. The system can be used for from about a few hundred feet of cable to about several miles of cable in a single setting. The system can require a lower amount of horsepower to move cable for testing as compared to normal systems known in the art. A first storage reel can be used for paying out cable to be tested. The first storage reel can be adapted to apply tension to the cable, and to allow the tension in the cable to be multiplied up to a test tension. The system can include a first moveable sheave in series with a second moveable sheave. The first moveable sheave can be rotated by a first hydraulic drive or a first electric drive. The second moveable sheave can be rotated by a second hydraulic drive or a second electric drive. The first moveable sheave can receive the cable and can pass the cable to the second moveable sheave. The third moveable sheave can be in series with a fourth moveable sheave. The third moveable sheave can be rotated by the second hydraulic drive or the second electric drive. In embodiments, the third moveable sheave can be in parallel with the second moveable sheave. The fourth moveable sheave can be rotated by the first hydraulic drive or the first electric drive, and can further be in parallel with the first moveable sheave. In embodiments, each moveable sheave can have grooves for receiving the cable and for containing the cable in each of the grooves. In one or more embodiments, each sheave can have at least six grooves. The grooves can be disposed in parallel, and can transfer the cable from one moveable sheave to another moveable sheave without otherwise touching or contacting additional cable. Both the second moveable sheave and the third moveable sheave can be tilted in part, thereby enabling at least two opposing grooves to be lined-up or aligned at bottoms of the sheaves, but to be offset at tops of the sheaves to facilitate cable transfer without sliding the cable on a face of the moveable sheaves. The second moveable sheave and the third moveable sheave can be connected and/or coupled with a first clutch. The first clutch can be operated by the second hydraulic drive. The first clutch can also disengage the second moveable sheave from the third moveable sheave. The first moveable sheave and a fourth moveable sheave can be connected and/or coupled with a second clutch. The second clutch can be operated by the first hydraulic drive. The second clutch can disengage the first moveable sheave from the second moveable sheave. The first clutch and the second clutch can be controlled by a clutch controller that can be in communication with a power source. Each clutch can be operable by one of the drives, a hydraulic power source, or combinations thereof. A first friction material can be disposed between the first moveable sheave and the fourth moveable sheave. A second friction material can be disposed between the second moveable sheave and the third moveable sheave. The friction material can provide coupling of each pair of moveable sheaves with the clutch. The first friction material and the second friction material can include a wearable brake material that can lock each pair of moveable sheaves together during testing of the cable. The hydraulic drives and/or electric drives can be connected to or coupled with a moveable tensioning moveable sheave, also referred to as a moveable tensioning sheave. In embodiments, the moveable tensioning sheave can include a load measuring sensor and a speed detector. In embodiments, each of the hydraulic drives can have at least one hydraulic pump connected to a hydraulic motor for rotating each moveable sheave. From about one hydraulic pump to about eight hydraulic pumps can be used in connection with each hydraulic drive. The hydraulic pump can have a fluid reservoir, and can be operated by an electric motor. The electric motor can be powered by an electric power source, such as a four hundred sixty volt three-phase power supply. The moveable tensioning sheave can receive the cable from the second moveable sheave and can pass the cable to the third moveable sheave, which can sequentially pass the cable to the fourth moveable sheave. In embodiments, a second storage reel can be used for receiving the cable and can be adapted to apply a second tension to the cable to be tested, which can allow the tension in the cable to be multiplied up to the test tension. In embodiments, the cable can be wrapped or reeved around the first moveable sheave and the second moveable sheave five times prior to passing the cable to the moveable tensioning sheave. The cable can move from the moveable tensioning sheave to the fourth moveable sheave, and can then be wrapped or reeved around the third moveable sheave and the fourth moveable sheave five times prior to passing the cable to the second storage device. The tensioning of the cable can occur at a speed from about one tenth of a foot per minute to about one thousand feet per minute. The tensioning of the cable can occur at a load from about one hundred pounds of force to about sixty thousand pounds of force. In embodiments, a first electric drive and a second electric drive can be used to rotate the moveable sheaves in addition to, or in replacement of, the first and second hydraulic drives. In embodiments, a hydraulic power source can be connected to the moveable tensioning sheave. The hydraulic power source can have at least one hydraulic pump connected to a hydraulic motor and/or a linear actuator. The hydraulic pump can have a fluid reservoir and can be operated by an electric motor, which can be powered by an electric power source. The system can have a processor for receiving signals from the load measuring sensor and the speed detector. The processor can be in communication with a network, at least one client device, and a data storage. The network can include the internet, an intranet, a local area network, a wide area network, a virtual private network, a satellite network, a cellular network, other similar networks, or combinations thereof. The client devices can be laptops, cell phones, pagers, or another network. In embodiments, the client device can have computer instructions for continuous remote monitoring of one or more compared signals from one or more processors simultaneously. The client devices can be in communication with the processor through the network for receiving load signals, speed signals, compared signals, notifications, or combinations thereof. Computer instructions can be located in the data storage and can be used for storing preset stress data for the cable to be tested. For example, data associated with loads that a cable can withstand can be stored in the data storage. Data associated with speeds that a cable can withstand can be stored in the data storage. Computer instructions can be stored in the data storage to instruct the processor to compare received signals from the load measuring sensor and the speed detector to the stored preset stress data, thereby forming compared signals. The processor and can determine if the received signals exceed or fall below the stored preset stress data. For example, if the stored preset stress data includes a maximum load amount of one thousand pounds, and the measured and received load signal is a load of two thousand pounds, then the processor can determine that the preset stress data has been exceeded. The system can have computer instructions in the data storage to instruct the processor to provide a notification when the compared signals exceed or fall below the stored preset stress data. For example, if the compared signals exceed or fall below the stored preset stress data, the processor can transmit the notification over the network to one or more client devices, thereby notifying users of the deviation from the stored preset stress data. The system can include computer instructions to instruct the processor to display the compared signals, the notification, or combinations thereof within client devices. In one or more embodiments, each drive of the system can be either a hydraulic drive or an electric drive. The first moveable sheave can be configured to receive the cable from the first storage reel. The first drive can be coupled with the first moveable sheave, and can be configured to rotate the first moveable sheave. The rotating first moveable sheave can be configured to pass the cable to the second moveable sheave in series with the first moveable sheave. The second moveable sheave can be configured to receive the cable from the first moveable sheave. The second drive can be coupled with the second moveable sheave, and can be configured to rotate the second moveable sheave. The moveable tensioning sheave can be coupled to at least one of the drives and can be disposed in series with the second moveable sheave. The second moveable sheave can be configured to pass the cable to the moveable tensioning sheave, which can be configured to receive the cable from the second moveable sheave. The third moveable sheave can be disposed in series with the moveable tensioning sheave, and can be configured to receive the cable from the moveable tensioning sheave. The second drive can be coupled with the third moveable sheave for rotating the third moveable sheave. The fourth moveable sheave can be disposed in series with the third moveable sheave and coupled with the first drive for rotating the fourth moveable sheave. The rotating fourth moveable sheave can be configured to receive the cable from the rotating third moveable sheave. The second storage reel can be configured to receive the cable from the fourth moveable sheave, and can be adapted to apply a second tension to the cable, thereby allowing tension in the cable to be multiplied up to the test tension. FIG. 1 depicts a schematic representation of an illustrative hydraulic cycle test system 100 according to one or more embodiments. The hydraulic cycle test system 100, which can also be referred to as a hydraulic operated system for testing cable under tension, can include one or more first storage reels 10, one or more first moveable sheaves 14, one or more first friction materials 80, one or more fourth moveable sheaves 24, one or more second clutches 28, one or more second moveable sheaves 16, one or more second friction materials 82, one or more third moveable sheaves 22, one or more first clutches 26, one or more first hydraulic drives 18, one or more second hydraulic drives 20, one or more clutch controllers 30, one or more power sources 32, one or more second storage reels 49, one or more moveable tensioning moveable sheaves 34, one or more hydraulic power sources 70, one or more client devices 52, and one or more processors 40 in communication with one or more data storages 42. Each of the moveable sheaves 14, 16, 22, and 24 can have six grooves for receiving the cable 12 to be tested. The cable 12 can be contained in each of the grooves in parallel, thereby allowing for the transfer of at least a portion of the cable 12 from one moveable sheave to another moveable sheave without contacting additional portions of the cable 12. For example, grooves of the first moveable sheave 14 can contain the cable 12 as the cable 12 is transferred from the first moveable sheave 14 to the second moveable sheave 16. The grooves of the moveable sheaves can be tilted in part, thereby enabling at least two opposing grooves to be aligned at the bottoms thereof but offset at the tops thereof. The tilt of the grooves can facilitate the transfer of a portion of the cable 12 from one moveable sheave to another moveable sheave, and can prevent the portion of the cable 12 from sliding about the face of the associated moveable sheaves. The first friction material 80 can be disposed between the first moveable sheave 14 and the fourth moveable sheave 24. The second friction material 82 can be disposed between the second moveable sheave 16 and the third moveable sheave 22. The first friction material 80 can couple together the first moveable sheave 14 and the fourth moveable sheave 24 with at least one of the clutches 26 and 28 utilizing a frictional force. The second friction material 82 can couple together the second moveable sheave 16 and the third moveable sheave 22 with at least one of the clutches 26 and 28 utilizing a frictional force. The friction materials 80 and 82 can include wearable brake material that can lock the pairs of moveable sheaves together during testing of the cable 12. The first clutch 26 can connect the second moveable sheave 16 to the third moveable sheave 22. Accordingly, the first clutch 26 can disengage the second moveable sheave 16 from the third moveable sheave 22. In one or more embodiments, the first clutch 26 can be operated by the second hydraulic drive 20. The second clutch 28 can connect the first moveable sheave 14 to the fourth moveable sheave 24. Accordingly, the second clutch 28 can disengage the first moveable sheave 14 from the fourth moveable sheave 24. In one or more embodiments, the second clutch 28 can be operated by the first hydraulic drive 18. In one or more embodiments, the clutch controller 30 can control the first clutch 26 and the second clutch 28. The clutch controller 30 can be in communication with the power source 32. The moveable tensioning moveable sheave 34 can be connected to and/or in communication with at least one of the hydraulic drives 18 and 20, the hydraulic power source 70, or combinations thereof. The moveable tensioning moveable sheave 34 can include a load measuring sensor 36 and a speed detector 38. The load measuring sensor 36 can be a stress gauge, a strain gauge, or a similar device for measuring load. The speed detector 38 can be tachometer, encoder, or similar device. In operation, the first moveable sheave 14 can receive the cable 12 from the first storage reel 10. The second moveable sheave 16 can receive the cable 12 from the first moveable sheave 14. The moveable tensioning moveable sheave 34 can receive the cable 12 from the second moveable sheave 16. In one or more embodiments, the processor 40 can be in communication with: the client device 52, the load measuring sensor 36, the speed detector 38, the data storage 42, or combinations thereof. Accordingly, the processor 40 can communicate with the client device 52, the load measuring sensor 36, and the speed detector 38. The processor 40 can receive signals from the load measuring sensor 36 and the speed detector 38 and can store the signals in the data storage 42. The processor 40 can monitor the tension loads of the cable 12, the speed of the cable 12, or combinations thereof. The data storage 42 can have: computer instructions 43 to instruct the processor to store preset stress data for the cable 12; computer instructions 44 to instruct the processor to compare received signals from the load measuring sensor 36 and the speed detector 38 to the stored preset stress data, and to form compared signals; computer instructions 45 to instruct the processor to provide a notification 46 when the compared signals exceed or fall below the stored preset stress data; and computer instructions 47 to instruct the processor to display the compared received signals, the notification, or combinations thereof within the client device 52. The data storage 42 is shown with preset stress data 48 stored therein. The processor 40 can be in communication with the client device 52 via a network 50. The network 50 can be the Internet, a local communication network, a satellite network, a cellular network, a wired network, a wireless network, or any other communication network. Data 53 is shown being transmitted from the processor 40 to the client device 52 over the network 50. The data 53 can include a notification, a load signal, a speed signal, a compared signal, other data associated with the cable, or combinations thereof. The client device 52 can have computer instructions 54 to allow for continuous remote monitoring of a plurality of compared signals from the processor and/or a plurality of processors. The processor 40 can be in communication with a plurality of client devices simultaneously. The client device 52 can be a laptop, a cell phone, a pager, or another electronic device. In operation, the cable 12 can be connected to the first storage reel 10 and to the first moveable sheave 14. Accordingly, the first storage reel 10 can be used to pay out the cable 12, and to apply a first tension 11 to the cable 12. Accordingly, the cable 12 can be tensioned up to a test tension. The first hydraulic drive 18 can rotate the first moveable sheave 14 and the fourth moveable sheave 24. The second hydraulic drive 20 can rotate the second moveable sheave 16 and the third moveable sheave 22. Accordingly, the cable 12 can be passed from the first moveable sheave 14 to the second moveable sheave 16. For example, the cable 12 can be configured to reeve around the first moveable sheave 14 and the second moveable sheave 16, such as five times, after which the cable 12 can pass from the second moveable sheave 16 to the moveable tensioning moveable sheave 34. Within the moveable tensioning moveable sheave 34, the load measuring sensor 36 can measure the load on the cable 12, and the speed detector 38 can measure the speed of the cable 12, forming signals and transmitting the signals to the processor 40 for storage in the data storage 42. The moveable tensioning moveable sheave 34 can pass the cable 12 to the third moveable sheave 22. The third moveable sheave 22 can be connected in series with the fourth moveable sheave 24, and in parallel with the second moveable sheave 16. The third moveable sheave 22 can be configured to be rotated by the second hydraulic drive 20. The fourth moveable sheave 24 can be in parallel with the first moveable sheave 14, and can be configured to be rotated by the first hydraulic drive 18. Accordingly, the cable 12 can pass from the third moveable sheave 22 to the fourth moveable sheave 24 as the moveable sheaves rotate. The cable 12 can then pass from the fourth moveable sheave 24 to the second storage reel 49. In one or more embodiments, the cable 12 can be configured to reeve around the third moveable sheave 22 and the fourth moveable sheave 24 five times prior to passing to the second storage reel 49. The second storage reel 49 can be configured to receive the cable 12, and to apply a second tension 51 to the cable 12, thereby allowing tension in the cable 12 to be multiplied up to the test tension. The tensioning of the cable 12 can occur at a speed from about one tenth of a foot per minute to about one thousand feet per minute. The tensioning of the cable 12 can occur at a load from about one hundred pounds of force to about sixty thousand pounds of force. A simplified schematic representation of the hydraulic cycle test system 100 shown in FIG. 1 is shown in FIG. 6. The cable 12 is released from the first storage reel 10. The cable 12 then winds between the first moveable sheave 14 and second moveable sheave 16 before coupling to the moveable tensioning sheave 34. The cable 12 then winds between the third moveable sheave 22 and fourth moveable sheave 24 prior to storage in the second storage reel 49. The moveable tensioning sheave 34 is shown coupled to the hydraulic power source 70. FIG. 2 depicts a schematic representation of an illustrative electrically operated cycle test system, according to one or more embodiments. The electrically operated system 200 can include a first electric drive 66 and a second electric drive 68 for driving the moveable sheaves 14, 16, 22, and 24. In addition, the hydraulic power source 70 can be in fluid communication with the first clutch 26 and the second clutch 28. The operation of the electrically operated system 200 can be substantially similar to the operation of the hydraulically operated system 100 in FIG. 1. The first electric drive 66 can drive the first moveable sheave 14 and the fourth moveable sheave 24. The second electric drive 68 can drive the second moveable sheave 16 and the third moveable sheave 22. The hydraulic power source 70 can operate the first clutch 26 and the second clutch 28. FIG. 3 depicts a schematic of the first hydraulic drive 18, according to one or more embodiments. The first hydraulic drive 18 can include a hydraulic fluid reservoir 62, a hydraulic motor 58, a hydraulic pump 56a, and an electric motor 60. The electric motor 60 can be in communication with an electric power source 64. The second hydraulic drive can be substantially similar to the first hydraulic drive 18. The hydraulic fluid reservoir 62 can be any fluid containment source, and can contain any hydraulic fluid. The hydraulic fluid reservoir 62 can be in fluid communication with the hydraulic pump 56a. The hydraulic pump 56a can be a centrifugal pump or another fluid pump. The hydraulic pump 56a can be in fluid communication with the hydraulic motor 58. The hydraulic pump 56a can be driven by the electric motor 60. The electric motor 60 can be a squirrel cage electric motor or another type of electric motor. The electric motor 60 can receive power from the electric power source 64, which can be an alternating current or direct current power source depending on the type of electric motor 60 used. As the electric motor 60 drives the hydraulic pump 56a, the hydraulic pump 56a can provide a pump head to the fluid in the hydraulic fluid reservoir 62 and can flow the fluid from the hydraulic fluid reservoir 62 to the hydraulic motor 58. As such, the hydraulic pump 56a can drive the hydraulic motor 58 by moving the fluid in the hydraulic fluid reservoir 62 to the hydraulic motor 58. The hydraulic motor 58 can be directly and/or indirectly coupled to one or more of the moveable sheaves and can drive the coupled moveable sheaves. FIG. 4 depicts a schematic of an illustrative first electric drive 66, according to one or more embodiments. The first electric drive 66 can include an electric motor 83, a gear reduction mechanism 84, and an electronic motor controller 88. The electric motor 83 can be in communication with an electric power source 90. The electric motor 83 can be an alternating current electric motor or a direct current motor. The electric motor 83 can be powered by the electric power source 90, and controlled by the electronic motor controller 88. The electronic motor controller 88 can be a variable speed controller, a digital speed controller, an on/of switch, or a combination thereof. The gear reduction mechanism 84 can directly and/or indirectly couple the electric motor 83 to one or more of the moveable sheaves and can drive one or more of the coupled moveable sheaves. The gear reduction mechanism 84 can be a speed reducer or a similar device, and can convert a portion of the speed of the electric motor to torque. The second electric drive can be substantially similar to the first electric drive. FIG. 5 a schematic of an illustrative hydraulic power source 70, according to one or more embodiments. The hydraulic power source 70 can include one or more hydraulic pumps 56a, a linear actuator 61, one or more electric motors 60, and one or more hydraulic fluid reservoirs 62. The electric motor 60 can engage an electric power source 64. The hydraulic power source 70 can include a plurality of hydraulic pumps. For example, the hydraulic power source 70 can have from about one hydraulic pump to about eight hydraulic pumps. The hydraulic pump 56a can be in fluid communication with the hydraulic fluid reservoir 62 and with the linear actuator 61. The electric motor 60 can be configured to drive the hydraulic pump 56a. Accordingly, the electric motor 60 can provide power to the hydraulic pump 56a to flow fluid from the hydraulic reservoir 62 to the linear actuator 61. The electric power source 64 can be a four hundred sixty volt three-phase power supply or another power supply depending on the type of electric motor 60 used. The linear actuator 61 can be coupled to the moveable tensioning moveable sheave through a mechanical linkage. While these embodiments have been described with emphasis on the embodiments, it should be understood that within the scope of the appended claims, the embodiments might be practiced other than as specifically described herein.
	summary
	description	By way of example an implementation of the present invention as a computer controlled process for determining a xe2x80x9cleast-costxe2x80x9d rehabilitation strategy for a water supply network will now be described. In this application the process requires for its operation a computer model of the network (or part of the network concerned) and other network analysis tools (including an hydraulic engine) necessary to perform calculations and predictions on the basis of the network model (network analysis). Since the present invention may be implemented as a discrete software module which can interface with proprietary network analysis software no detailed description of such features will be given here. Accordingly, it is to be understood that in a practical computer system for operating the present invention as described below, the rehabilitation method of the present invention will be one part of a system additionally comprising a computer model of the network under consideration, a hydraulic solving engine for performing hydraulic calculations and predicting the effect of changes to the network, and suitable interface and reporting facilities. The nature of the additional software analysis tools required will be readily apparent to the skilled reader by the references that are made to the required functionality. Such additional software tools may be entirely conventional and thus no description of appropriate tools will be made apart from references to the required functionality. In addition, the invention requires reference to a contractor cost table in which the various rehabilitation options open to the planner, and associated costs, are listed. The concept of a contractor cost table is discussed above. For ease of interface with the present invention it will be appreciated that the cost table should be represented in a database from which information can readily be extracted. If the network planner does not have an appropriate database one can be constructed and indeed the system according to the present invention may incorporate a database into which relevant information can be input by the planner. As such, the system could guide the planner as to the information required. From the appropriate cost table it would always be possible for the planner to determine the cheapest available option for rehabilitating selected pipes within the network. However, the user must also take account of a number of operating constraints which may not necessarily be satisfied by the cheapest rehabilitation strategy. The precise set of operating parameters which have minimum or maximum acceptable limits and which must therefore be considered in any particular instance may vary but some typical parameters are listed below (in no particular order). A maximum acceptable hydraulic gradient will normally be specified. That is, there will be a maximum permissible head loss per unit length of pipe within the network to ensure demand can be met. Minimum and maximum permissible pressures may be specified for each node, or selected nodes, within the network. For instance, it is often necessary to maintain particular nodes above a minimum pressure to avoid adverse effects on downstream pressures or flow rates and also meet levels of service criteria. It may be necessary to limit the maximum pressure at various points in the network for instance to address leakage problems or to ensure that pipe pressure ratings are not exceeded. Minimum and maximum flow rates through various parts of the network may be specified. For instance, it may be necessary to keep flow above a minimum rate to avoid sediment problems. Minimum tank levels may be specified for reservoirs etc. Conditions may be applied limiting the acceptable rehabilitation techniques which may be used in any particular instance and specifying a minimum or maximum permissible size for the pipe following rehabilitation. It will be appreciated that the above list is not exhaustive and that a variety of conditions may apply in any particular case. The parameters and associated limits which must be considered may be defined by the network model, the network planner or may be default parameters provided by the system according to the invention (or indeed a combination of the two). The predefined limits of operating parameters which apply in any particular case are referred to generally hereinafter as xe2x80x9coperating limitsxe2x80x9d. At the heart of the optimisation method of the present invention is an iterative routine which takes a xe2x80x9cstartxe2x80x9d rehabilitation strategy for a number of pipes and modifies the strategy to produce an optimum xe2x80x9cleast costxe2x80x9d strategy (by reference to the appropriate user provided cost table) whilst ensuring that operating limits are not violated. Thus, as a preliminary step to the iterative routine a list of the pipes to be rehabilitated must be provided together with a suggested rehabilitation option for each pipe. The selected pipes incorporating the proposed rehabilitation (which may for instance be pipe lining or replacement ) are referred to hereinafter xe2x80x9crehab.pipesxe2x80x9d. Thus, for instance, where reference is made to the size of a rehab.pipe this is a reference to the size of the respective pipe as would result from the rehabilitation method currently proposed for that pipe. Thus reference to the size of the rehab.pipe may be reference to a reduced size following lining etc of the original pipe, or an increased size following replacement of the original pipe with a new larger pipe. The planner may manually select the pipes to be rehabilitated from the network model, or use an appropriate filter (for instance selecting all cast iron pipes above a certain diameter), and may then select a xe2x80x9csafexe2x80x9d strategy from the available rehabilitation options as the start strategy for the iterative routine. For instance, such a xe2x80x9csafexe2x80x9d strategy may be to replace existing pipes with new pipes of similar size and flow characteristics, or a size larger than the existing pipes. Preferred methods for ordering the list of the pipes to be rehabilitated, and generating an appropriate start strategy for the iterative routine, will be described further below. Once the pipe list and start strategy has been generated , the iterative routine according to the present invention may be operated as follows. The first step is to select a first rehab.pipe from the pipe list. Having selected the first rehab.pipe from the pipe list, the next step is to consult the appropriate cost table and xe2x80x9cstep downxe2x80x9d the initially proposed rehabilitation method for the selected rehab.pipe. This is a step down in cost which can be determined from the appropriate cost table and will generally entail stepping down the size of the pipe to the next size down, but may also entail changing the material of the pipe or rehabilitation technique. Once the selected pipe has been stepped down in cost, a network analysis is performed to determine whether or not any of the predefined operating limits are violated as a result of the change to the selected pipe. This part of the routine requires calling upon network analysis tools (such as an hydraulic engine etc) to perform the necessary calculations on the network (modified by the rehabilitation strategy including the stepped down rehab.pipe) which are then compared with the predefined limits. As mentioned above, the network analysis methods and tools which may be used to perform the calculations and make the necessary determination may be entirely conventional and thus will not be described here. The above test can result in one of two outcomes: either that there are no operating limit violations or that there are operating violations. If there are no operating limit violations the iterative routine moves on to select the next rehab.pipe from the pipe list and repeats the process of stepping down the selected rehab.pipe and determining whether this results in any operating limit violations. If, however, stepping down the currently selected rehab.pipe results in any operating limit violations, the selected pipe is stepped back up to its previously proposed rehab.pipe size etc and xe2x80x9clockedxe2x80x9d against further change. The routine then moves on to select the next rehab.pipe from the pipe list. Once the iterative routine has completed its first iteration, and each rehab.pipe in the pipe list has been selected once, some rehab.pipes will have been stepped down whereas others will have been locked in their previous rehabilitation proposal (which after the first iteration will of course be the start proposal). The routine then returns to the start of the pipe list and selects the first un-locked rehab.pipe from the list. The selected pipe is then again stepped down and a determination is made as to whether or not any operating limit violations result. If there are no operating limit violations the routine moves on to the next unlocked pipe in the pipe list. If there are operating limit violations the selected pipe is stepped back up to its previous rehabilitation proposal and locked. The routine is continuously iterated, making as many passes as necessary through the rehab.pipe list, until all pipes in the pipe list have been locked. This results in a rehabilitation strategy which meets the predefined operating requirements but which is cheaper to implement than the start strategy. This optimised strategy may then be reported as the xe2x80x9cleast costxe2x80x9d acceptable rehabilitation strategy. The above is a simplified description of the basic operation of the iterative routine of the present invention which may be enhanced in a number of ways which will become apparent from the following description. It is important, however, to appreciate that the xe2x80x9cleast costxe2x80x9d option arrived at may not necessarily be the cheapest possible rehabilitation strategy if all possible strategies had been considered. For instance, changes to the initial starting strategy and order in which the rehab.pipes are considered during the iterative routine may result in different solutions (as mentioned above, preferred schemes for determining the ordering of the pipe list and start strategy will be described below). There may even be a number of alternative strategies which differ in detail but have substantially the same associated cost. However, the essence of the invention is the provision of a process which determines a low cost strategy at an acceptable overhead in terms of operating time and level of input required by the planner. The term xe2x80x9cleast costxe2x80x9d used above and hereinafter is to be interpreted accordingly. It will be appreciated that there may be a number of ways in which the iterative routine can actually be implemented by computer software. No effort will be made here to describe in detail such an implementation as the design of an appropriate software program to run the process according to the present invention can be made by an appropriately skilled person. However, a simplified flow diagram illustrating an overview of one preferred way in which a computer program for running the iterative routine may be designed is shown in FIG. 1. Referring to FIG. 1, block 1 represents the starting point of the routine which is the provision of a rehab pipe list in accordance with a start rehabilitation strategy. This is discussed in general terms above. Block 2 ensures that all rehab.pipes in the pipe list are un-locked (the significance of which will be apparent from the above description of the iterative routine). Block 3 sets the un-locked rehab.pipe count designated, i, to 0. Block 4 determines whether all of the pipes in the rehab.pipe list are locked. If all the rehab.pipes are locked the program exits the iterative routine and proceeds to a reporting stage. If there are any unlocked pipes the process proceeds to block 5. At block 5 the pipe count is moved on to the next un-locked pipe in the rehab.pipe list. On the first iterative this will be the first pipe in the pipe list. At block 6 a determination is made as to whether or not the pipe count is greater than the number of rehab.pipes remaining un-locked. If the answer to this determination is yes, the routine moves to block 7 at which the first unlocked pipe in the pipe list is selected before moving on to block 8. If the answer to the determination made in block 6 is no, the routine moves straight on to block 8. At block 8 the selected pipe i is stepped down as explained above by reference to the appropriate cost table. At block 9 a network analysis is instigated to calculate the effect of stepping down pipe i on the predefined operational parameters of the network. At block 10 a determination is made as to whether or not any of the predefined operating limits are violated (as a result of stepping down pipe i). There are two possible outcomes. If the answer to this determination is no the routine returns to block 4. If the answer is yes the routine moves on to block 11. At block 11 the selected pipe i is stepped back up to its previous rehabilitation condition, i.e. returned to the condition it was in prior to being stepped down at block 8. At block 12 pipe i (having been stepped up at block 11) is locked against further modification. The routine then returns to block 4. The program cycles through the iteration routine until the determination at block 4 finds that all pipes have been locked in a final rehabilitation strategy which is then passed on to a reporting routine, via any further analysis that may be deemed desirable (a preferred analysis is described further below). As mentioned above, the order in which the iterative routine passes through the list of pipes to be rehabilitated may have a bearing on the optimised rehabilitation strategy arrived at by the routine. In a preferred embodiment of the present invention the pipe ordering is a reverse of the hydraulic significance of each pipe. In other words, the least hydraulically significant pipes are considered before the most hydraulically significant pipes. There may be various different methods for determining the hydraulic significance of an individual pipe within the list of pipes to be rehabilitated. For instance, it would be possible to estimate the hydraulic significance of rehab.pipes on the basis of the size of the original pipes. However, the actual hydraulic significance of a pipe within a network may not be directly related to its size and one aspect of the present invention is to provide a novel method for determining the hydraulic significance of pipes in a network. This will now be described with reference to the flow chart of FIG. 2 which sets out the steps to be implemented by an appropriately designed computer program. The determination of the hydraulic significance in accordance with the present invention is essentially a flow path analysis performed on the network model determining how many times each pipe occurs in flow paths between the source node and boundaries of the network (or DMA etc). Thus, the routine for determining the hydraulic significance of the selected pipes must be made by reference to an appropriate network model which has the necessary information. Because water supply and/or distribution systems are dynamic and water demand patterns vary over time, a typical network model will comprise a number of xe2x80x9csnap shotsxe2x80x9d of the flow conditions at various time intervals over a given time period. For instance, the direction of water flow through some pipe elements may change over a 24 hour period as demand patterns change. Referring to FIG. 2, the first step in the procedure, as represented by block 13, is to build a pipe list. This may either be a list of every pipe within the network (or the portion of the network (DMA etc) under consideration) or only of those pipes selected for rehabilitation. The latter would streamline the process. At this stage, the pipes may be listed in any order. The preferred routine for determining the hydraulic significance of pipes illustrated in FIG. 2 considers the network flow at 30 minute intervals throughout a 24 hour period, although it will be appreciated that other time intervals/periods could be selected. Thus, at block 14 time is set to 0 and is an advanced to the first time interval at block 15. At block 16 the network model must be balanced. In other words, the hydraulic engine must determine the flow patterns through the network at the selected time interval. This is a conventional operation and is a basic facility provided by conventional network analysis tools. At block 17 the node count is set to 0. As mentioned above, the network nodes are identified by the network model. At block 18 the node count is incremented to the next node. The order in which the nodes are considered is not important. At block 19 the program operates to trace the flow path from the selected node back to the source. There may be a number of different flow paths between the selected node and the source. At block 20 an increment is made in an instance count for each pipe in the pipe list which appears in a flow path from the currently selected node to the source (for further details see the description of FIG. 3 given below). At block 21 a determination is made as to whether or not the node count equals the number of nodes in the network (or DMA etc) under consideration. If the answer is no the program returns to block 18 and the node count is incremented to the next node following which the steps of blocks 19 to 21 are repeated. If the answer is yes the routine proceeds to block 21. At block 21 a determination is made as to whether or not the time interval under consideration equals the end time. That is, whether or not every time interval over the total time period has been selected. If the answer is no the routine returns to block 15 and the time is incremented to the next time interval. The routine of blocks 15 to 21 is then repeated until the time equals the end time and the routine passes on to block 22. At block 22 the pipe list is sorted and ranked on the basis of the instance count for each pipe. Pipes with the highest instance count are considered to be the most hydraulically significant. The result is that each selected pipe is ordered in accordance with its hydraulic significance and this order can be used for the iterative routine described above. A simple example illustrating the manner in which the instance count is made is shown in FIGS. 3a and 3b. FIG. 3a is a schematic diagram of a simple pipe network and FIG. 3b is a table illustrating incrementation of the pipe count for each pipe in the network to arrive at a figure representative of each pipe""s hydraulic significance. Referring firstly to FIG. 3a, the illustrated network comprises a source S, eight pipes P1-P8, and six network nodes, N1-N6 respectively. In accordance with the routine described above, each node is considered in turn and the flow paths to that node via the pipe or pipes terminated or converging at that node are traced having regard to the flow directions determined by the network analysis performed to balance the network (as mentioned above). Flow directions are indicated in FIG. 3a by arrows associated with each pipe. Each pipe converging at the selected node is considered in turn and every flow path from the source to that pipe is traced. Any pipe occurring at least once in one or more of the flow paths to the pipe under consideration receives an instance count of 1. Thus, for instance, node N1 is fed directly by a single pipe P1. There are however three separate flow paths to node N1 via pipe P1, namely: P8/P6/P3/P1; P8/P7/P5/P3/P1; and P8/P7/P4/P1. Thus, when considering pipe P1 all pipes in the network baring pipe 2 receive an instance count of 1. Taking now node N3 for example, this is fed directly by two separate pipes, P3 and P4, each of which must be considered separately. There are two separate flow paths to node N3 via pipe P3, namely P8/P6/P3 and P8/P7/P5/P3. Thus when considering pipe P3 each of pipes P3, P5, P6, P7 and P8 receive an instance count of 1. When considering pipe P4 on the other hand, which also converges at node N3, there is a single flow path P8/P7/P4. Thus when considering pipe P4 only pipes P4, P7 and P8 receive an instance count. This operation is repeated for every node in the network, considering separately flow paths that either converge or terminate at the selected node via each pipe that converges or terminates directly at that node. The result of this operation is summarised in table 3b. The rows indicate the pipes which appear in a flow path to the respective fed pipe P1-P8. The columns are the cumulative instance counts for each of supplying pipes P1-P8. The final row at the bottom of the table is the hydraulic significance (HS) of each pipe by reference to the total of its instance counts. As would be expected, pipe element P8 clearly has the greatest hydraulic significance as all other pipes in the network must be fed from this pipe. Similarly, terminal pipes P1 and P2 are clearly the least significant. The existence of pipe element P5 however has an effect on the relative significance of other pipes in the network so that, for instance, element P7 has a greater hydraulic significance than element P6. It will be appreciated that although it is convenient to make the count by considering each node in turn, the same result would be achieved if each pipe was considered in a random order since the count is cumulative. That is, whatever order pipes P1-P8 are considered (as fed pipes), the supplying pipes would be the same and thus the calculated hydraulic significance would be unchanged. The hydraulic significance count represented by FIGS. 3a and 3b represents the process made at a given time. As mentioned above, the flow directions through the network can change over a period of time. For instance, should the flow direction through pipe element 5 reverse, the hydraulic significance of pipes 6 and 7 under that particular flow condition would also reverse. Thus to obtain a more representative indication of hydraulic significance the same process is repeated for each time period under consideration. Accordingly, the overall hydraulic significance for each pipe is taken as the sum of the counts made at each of the time intervals considered (in the example set out above this is every 30 mins over a 24 hour period). Thus, if at most times during the day flow through the pipe element P5 is in the direction shown, the total hydraulic significance count of pipe element P7 would be greater than for pipe P6. The overall result is that a hydraulic significance is attached to each pipe within the pipe list which can then be ordered accordingly. This ordering can be used to determine the order in which pipe elements are considered by the iterative routine of FIG. 1. Specifically, the invention has been found to give good results when the pipes are considered by the iterative routine in an order which is the reverse of the relative hydraulic significance of the pipe elements. As mentioned above, the iteration routine of FIG. 1 must take as its starting point a start rehabilitation strategy. The start strategy selected may have a bearing on the final outcome although it is expected that, whatever the starting strategy, the iterative routine will provide a good solution. Nevertheless, a preferred scheme for settling on a start strategy for the iterative routine will now be described. Before the process is run, the pipes to be rehabilitated must be selected by the network planner, i.e. a pipe list must be constructed as mentioned above. The network planner can then determine the least expensive option for rehabilitating each pipe by reference to an appropriate cost table. Once the least expensive option has been selected, a determination may be made as to whether any of the predefined operating limits are violated by the strategy proposed. If the answer is no, then this least expensive option may be taken as the solution and there is no need to run the iterative routine at all. Such a solution can be considered as a lower bound solution and is not likely to occur very often. If the initially proposed cheapest rehabilitation strategy does not meet the predefined conditions, i.e. there are operating limit violations, the present invention proposes a scheme for modifying the initial strategy to produce a start strategy for the iterative routine. Since the iterative routine will generally improve upon whatever start strategy is selected, the present invention contemplates a routine which represents a pragmatic approach to the selection of a start strategy. If the initial least cost option causes operating limit violations it will be necessary to increase the size of at least some of the rehab.pipes. In accordance with the preferred method of the present invention, this is done by again referring to the hydraulic significance of the selected pipes (preferably determined in accordance with the method described above). All the rehab.pipes are then increased in size but not all rehab.pipes are increased by the same amount. The amount by which each rehab.pipe or group of pipes is increased in size is determined by relation to the hydraulic significance of that rehab.pipe or group of pipes. Specifically, the invention proposes taking a select group of the most hydraulically significant rehab.pipes and increasing the size of these pipes by three sizes larger than that proposed in the initial solution and then increasing the size of the remaining pipes to one size larger than that proposed in the initial solution. The selection of the xe2x80x9cmost significantxe2x80x9d pipes can be made on a number of bases, for instance this could be the top few percent of pipes in the list, the top specified number of pipes in the hydraulic significance order, or pipes with a hydraulic significance above a lower limit. Whatever the method used to group pipes from the hydraulic significance order, the principle of the invention is to provide a simple approach which whilst being pragmatic has some reference to the relative importance of pipes in the network and thus the effect that changes of sizes of particular pipes or groups of pipes in the network may have on the network as a whole. Once the proposed rehab.sizes have been increased in accordance with the above scheme to produce a modified rehabilitation strategy, a second determination is made as to whether any of the operating limits are violated. If the answer is no, then the modified strategy is used as the start strategy for the iterative routine. If the answer is yes, i.e. some limits are violated, a further modification needs to be made. At this stage there is no point in effectively duplicating the work that would be done by the iterative routine and so the preferred step according to the present invention is to set all pipes to be rehabilitated to their maximum size and once more tested for operating limit violations. Hence it will be seen that this step of the preferred strategy for starting the optimisation process is to test out the suitability of an upper bound solution based on adoption of maximum possible rehab.pipe sizes throughout the scheme. For many cases the adoption of the maximum rehab.pipe sizes as a starting strategy will not produce operating limit violations and can therefore be used as the starting strategy for the iterative routine. However, if this proposed start strategy does result in operating limit violations (the large increases in mains rehab.pipe capacities leads to operating violations that arise as a result of the very low velocities and slack hydraulic gradients associated with the maximum rehab.pipe size option), then it is necessary to test one further set of starting conditions. The approach taken by the present invention is to test the existing network for operating limit violations. If these do not exist, then the final starting strategy option is to set all the rehab.pipes one size larger than the existing pipe sizes. However, if operating limit violations do exist for the existing network then the starting strategy option is, once again, to set all rehab pipes to the maximum possible size offered as an option from the associated contractor cost charts. This final modified strategy is then used as the start strategy for the iterative routine. It has also been found that the iterative solution finding stage of the current invention can be significantly shortened if a step is taken that presupposes that all the existing ferrous mains to be rehabilitated already exhibit hydraulic frictions normally associated with the much smoother plastic mains used for rehabilitation). As mentioned above, one of the important operating limits which will usually be specified for a network is that each rehab.pipe within the network is capable of meeting peak flow demands without unacceptable pressure losses per unit length of pipe, i.e. without the hydraulic gradient increasing above a predefined maximum limit. Conventional water supply network analysis will provide estimates of the flow rate expected through each pipe in the network. This conventional xe2x80x9cnetwork analysis flowxe2x80x9d can be used in determination of the limit violations. However, in accordance with a further aspect of the present invention there is provided a method of determining the peak flow requirement of each pipe in a pipe network which improves upon the results obtained by conventional network analysis by taking into account variations in the local water supply demand across the network and the effect that this may have on the total demand placed on individual pipes within the network. For instance, conventional network analysis will assume that at peak flow time the flow effectively increases by the same proportion throughout the network. This, however, is unlikely to be the case. It may well be that the peak flow condition is due to a sudden local demand in one particular area of the network where, for instance, industrial units or farmers etc. are supplied. However, it is more usual for local peak demand flow, such as that which might occur in a cul-de-sac, to be generated from such local domestic demands all taking place at the same time. The effect of the application on conventional network analysis would be to smooth the peak flow out across the network which may give an inaccurately low estimate of the peak flow expected at some points of the network. To avoid the potential problem of undersizing rehab.pipes from such incorrect water demand modelling, the present invention provides a method of estimating peak flow which combines both an estimate of local demand determined in a novel way together with peak flow through the network calculated by conventional network analysis processes (which will be referred to hereinafter as xe2x80x9cnetwork analysis peak flowxe2x80x9d). In accordance with the present invention, the local demand flow is calculated on the basis of flow procedures similar to those normally applied to determine flow rates to service pipes on a spur of a pipe network, but applied across the network as a whole. To do this, the invention introduces the concept of xe2x80x9cpseudo-spursxe2x80x9d. The preferred way for separating the network into pseudo-spurs is to first identify each source or pseudo source within the network and also each node which receives convergent inflows from two or more pipes of the network. Each of the nodes/sources identified in this way is then considered to be the origin of one or more downstream pseudo-spurs. Where two or more pseudo-spurs have a common origin, they may collectively be viewed as a xe2x80x9cpipe treexe2x80x9d. The pseudo-spurs (which are effectively branches of a pipe-tree) and pipe-trees are identified by reference to the network analysis flow patterns (i.e. flow directions) through the various pipe elements of the network. To determine local demands at the peak flow condition, this is done by reference to the network analysis peak flow pattern. An estimate of the local demand which must be met by each pseudo-spur is then calculated, and the local demand flow of each pipe in each pseudo-spur is added to a throughflow component determined on the basis of the network analysis peak flow to give a sum which is taken to be the peak flow which must be met by each individual pipe. Individual pseudo-spurs beginning at a given origin terminate at a downstream convergent node, or at a terminal demand node. The manner in which the network is divided into pseudo-spurs leads to an effective weighting of the effect of local demand versus network analysis throughflow. The network analysis flow component of the resultant peak flow determined can be calculated by any conventional network analysis technique. No particular technique will therefore be described for calculating the network analysis flow. The preferred manner in which the local demand is accounted for by the present invention will now be described with reference to FIGS. 4a and 4b which reproduce the simple network of FIG. 3. Referring to FIG. 4a, an indication is given at each node as to the properties supplied directly from service pipes (not shown) leading from the respective node. For simplification, the network is considered to be supplying domestic properties only, i.e. 50 houses are supplied by each of nodes N1 and N2, 200 houses are supplied by node N3, 150 houses are supplied by node N4 and 100 houses are supplied by node N5. There is no local demand at node N6. In accordance with the first stage of the process, the sources and convergent nodes are identified. The concept of sources and pseudo-soruces is discussed above and will be familiar to the skilled reader. A convergent node is a pipe junction at which flow converges from two or more separate pipes. It will be appreciated that any particular node may be a convergent node at some parts of the day but not at others. Since the object here is to determine peak flow demands, the convergent nodes are identified by reference to the network analysis peaks flow pattern. In this case (assuming the flow pattern illustrated to be the peak flow pattern as determined by network analysis) there is a single source S and two convergent nodes, i.e. nodes N3 and N4. A determination is then made of the pseudo-spurs originating at each of the convergent nodes and the source. Thus, the pipe tree which has its origin at the source S comprises three separate pseudo-spurs. A first pseudo-spur comprises pipes P8 and P6 and terminates at downstream conversion node N4. A second pseudo-spur comprises pipes P8, P7 and P5 and again terminates at downstream convergent node N4. The third pseudo-spur comprises pipe elements P8, P7 and P4 and terminates at downstream convergent node N3. Considering convergent node N4, the pipe tree which has its origin at this node comprises only a single pseudo-spur which terminates at downstream convergent node N3 and comprises the single pipe P3. Considering now convergent node N3, the pipe tree which has its origin at this node comprises two pseudo-spurs each of which consists of a single pipe P1 and P2 respectively. Thus, in the network as a whole there are three pipe trees and six pseudo-spurs. It will be seen that some pipes, namely pipes P7 and P8, occur in more than one pseudo-spur. Having first identified the pseudo-spurs, the next stage is to consider the number of users (in this case houses) supplied by each pipe to determine a local demand loading for each pipe. An assumption is made that the local domestic demand (houses) at a convergent node is supplied equally from the converging pipes. Thus, to arrive at the local demand weighting for any particular pipe the part that pipe plays in supplying downstream properties supplied by all pseudo-spurs of which that pipe is an element must be considered. Thus, taking pipe P1, this occurs in only a single pseudo-spur and moreover is the only pipe in that particular pseudo-spur. Thus, the local loading of pipe P1 is the 50 houses located at node N1. A similar calculation applies to pipe P2, which also has a local loading of 50 houses. At node N3, it is assumed that the 200 houses supplied from that node are supplied from each of the pipe elements converging at that node, i.e. pipes P3 and P4. Moreover, an assumption is made that each of the pipes P3 and P4 makes an equal contribution to the demand at node N3. Thus, the local demand loading for pipes P3 and P4 is 100 houses in each case. Similarly, of the 150 houses supplied at node N4, 75 are assumed to be supplied from pipe element P5 and 75 are assumed to be supplied from pipe element P6. Pipe P6 is part of a single pseudo-spur P8/P6 which has its origin at source S and its termination at convergent node N4. Therefore, the local loading applied to pipe element P6 comprises the 75 houses supplied at node N4. Taking now pipe element P7, this is part of two pseudo-spurs both of which have their origin at the source S but which have different terminations. The first of these is pseudo-spur P8/P7/P5 which terminates at node N4. The second is P8/P7/P4 which terminates at node N3. The total local loading applied to pipe P7 is considered to comprise a contribution from its function in both of these pseudo-spurs. Thus, pipe P7 is considered to supply all 100 houses at node N5, 75 of the houses at node N4 (via pipe P5), and 100 of the houses at node N3 (via pipe P4), giving a total loading for pipe P7 of 275 houses. It will therefore be seen that whereas every pipe within the network will have a direct local demand, i.e. the properties deemed to be supplied by that pipe at the node at which it terminates, some will also have an indirect local demand arising from each of the downstream pipes within the same pipe tree. Thus, the total local demand loading for pipe element P7 may be arrived at by summing the direct local demand loadings of pipe P7 with that of each of the downstream pipes in the same pipe tree, i.e. pipes P4 and P5 which have direct loadings of 100 and 75 houses respectively. This gives the total of 275 house for pipe P7. Finally, pipe P8 is part of three different pseudo-spurs all having their origin at source S. Two of these terminate at node N4, namely pseudo-spur P8/P6 and pseudospur P8/P7/P5. The third is pseudo-spur P8/P7/P4 which converges at node N3. The total loading for pipe P8 comprises a contribution from its function in each of its pseudo-spurs. Again, the total local loading for pipe P8 can be arrived at by summing the direct local loading of pipe P8 with the direct local loadings for each of the pipes downstream of pipe P8 within the same pipe tree (which will of course be all pipes downstream of pipe P8 within each pseudo-spur of which pipe P8 is an element). In other words, the total local loading for pipe P8 is the sum of the direct local loading for pipe P8 (which is 0), the direct local loading for pipe P7 (which is 100 houses), the direct local loading for pipe P5 (which is 75 houses), the direct local loading for pipe P6 (which is 75 houses) and the direct local loading for pipe P4 (which is 100 houses), which gives a total of 350 houses. An alternative way of arriving at the total local loading for pipe P8 is simply to sum the total local loadings for each of the pipes immediately downstream of pipe P8 within the same pipe tree. In other words totalling the previously calculated total local loadings of pipes P6 and P7. This same method can be applied throughout the network. Once the total local demand loading at the peak flow condition has been determined for each pipe within the network, the associated local demand must be determined. This may be done by estimating the local demand per house and then calculating the local demand for each pipe (as a simple multiple of the total local loading for that pipe and the estimated local demand per house). Alternatively an appropriate formula may be applied to the total house loading for each pipe. Local demand conditions are conventionally determined by an empirical formula. For instance, one such formula provided by the Foundation for Water Research applicable to domestic properties is as follows: F=kNA F=flow, liters per second k=a constant, based on the type of property N=number of houses A=a power term, taken to be 0.78 In this simple empirical formula, houses are categorised as one of two types each having a different value for k (0.067 and 0.107 respectively). This formula then provides an estimate of the local demand at different locations across a network by applying the formula to the two groups of properties. Applying the above formula to, for instance, pipe P7, and assuming in this example that 75% of the houses are type 1 and the others type 2, gives a total local demand flow for pipe P7 of 6.16 liters per second. This local demand flow calculation takes no account of the contribution any particular pipe may make to the water supplied downstream of the respective pipe tree. Thus, the next step is to calculate a throughflow component of the peak pipe flow for each pipe in the network. This is done by estimating the flow to be provided to the network downstream of the pipe tree on the basis of the conventional network analysis flow rates by determining the contribution made to the network downstream of each pseudo-spur containing the pipe in question. In other words, the throughflow for each pseudo-spur is determined and the throughflows for each individual pipe is taken to be the sum of the throughflow through each of the pipe spurs including that pipe. As mentioned above, the flow figures for the through flow calculation may be taken from a conventional network analysis, i.e. may be conventional network analysis peak flows. FIG. 4b shows the results of such a conventional network analysis on the basis of a normal (house) demand flow of 0.0045 liters per second and a peaking factor of 2. Thus, for the 550 houses supplied by the network this gives a total peak demand of 4.95 liters per second. The network analysis then apportions this to each pipe element in accordance with conventional methods and the relevant flows are listed. Thus, using conventional network analysis the peak flow through pipe element P7, for example, would be assumed to be 2.7 liters per second. Taking pipe P7 as an example, to determine the through flow to be added to the local demand flow calculated above, all pseudo-spurs containing pipe P7 must first be identified. These are spurs P8/P7/P5 and P8/P7/P4. Having identified the relevant pseudo-spurs, the through flow for each spur must be determined. This is done by reference to the network analysis flow immediately downstream of the node at which the respective pseudo-spur terminates. Consider first pseudo-spur P8/P7/P5 which terminates at node N4. Only a single pipe is immediately downstream of node N4, i.e. pipe P3. Pseudo-spur P8/P7/P5 does not however provide all the flow for pipe P3 since pseudo-spur P8/P6 also terminates at node N4. Thus, the contribution made by pseudo-spur P8/P7/P5 to the network analysis flow through pipe P3 is taken as the ratio of the flow through the downstream pipe of the spur, i.e. pipe P5, to the total network flow converging at node N4. Thus, the through flow through pseudo-spur P8/P7/P5 is determined by the calculation: [qp5/(qp6+qp5)]xc3x97qp3 where qn is the network analysis flow in pipe n which gives [0.3/(2.25+0.3)]xc3x971.2=0.14 liters per second Applying the same process to pseudo-spur P8/P7/P4, the calculation is [1.5/(1.5+1.2)]xc3x97(0.45+0.45), which gives 0.5 liters per second. The total through flow for pipe P7 is then the sum of the through flows through each of the pseudo-spurs P8/P7/P5 and P8/P7/P4, i.e. 0.14+0.5 liters per second, which gives 0.64 liters per second. The total peak design flow demand for pipe P7 is then the sum of the through flow component and the local demand component calculated above, i.e. 0.64+6.16 liters per second, giving a total of 6.8 liters per second. Thus, it can be seen that the peak design flow calculated in accordance with the present invention, which takes account of local demand, is much higher than the network analysis peak flow for pipe P7 of 2.7 liters per second. The same process can be applied to each pipe within the network. It is convenient to consider each pipe tree in turn, since any given pipe will occur in only one pipe tree. Once this process has been applied across the whole network it will be seen that at the extremities of the network, where network analysis throughflows have relatively low or null values, the local demand component of the peak flow calculated in accordance with the present invention will be more significant than for upstream mains pipes etc nearer the source which by their nature have higher network throughflows. It will be appreciated that the manner in which the network flows are calculated is not of primary significance. It will also be appreciated the local demand formula used above is only an example of a simple formula. The significant feature of this aspect of the invention is that whatever flow is calculated by the conventional network analysis is supplemented by a local demand loading calculated in accordance with the above procedure by breaking the network as a whole up into pipe trees comprising pseudo-spurs. Furthermore, whereas the proposal laid out above is one particularly efficient way of splitting the network into individual pipe spurs, other alternatives might be envisaged. It will be appreciated that the calculations made above are highly dependent on the pattern of flow through the network and thus to determine the peak flows the network flow pattern at the peak flow time is taken. However, it is also possible that local areas within the network may experience a localised peak which does not coincide with the peak for the network as a whole. Thus, as an enhancement to the basic method it would be possible to perform the above calculation for a number of different times over a given period (say, 30 min intervals over a twenty four hour period) and the maximum value obtained for any particular pipe from any of the times taken as the peak flow through that pipe. FIG. 5 is a flow diagram illustrating how determination of peak flow requirements in accordance with the above outlined procedure can be incorporated in a preferred routine for establishing a start rehabilitation strategy for the iterative routine of FIG. 1. Thus, referring to FIG. 5, block 23 represents the initial stage of selecting the least expensive rehabilitation option for all pipes selected for rehabilitation. This will be done by the network planner as mentioned above. Rather than advancing immediately to a determination of whether any operating limits are violated, the next stage at block 24 is to apply the peak flow analysis described above. If any proposed rehab pipe is found to be of an insufficient diameter etc to provide the calculated peak flow at the maximum acceptable hydraulic gradient (typically 1:100) the rehab proposal is automatically adjusted by upsizing the rehab.pipe in question to the minimum required size to accommodate the peak flow (or by changing the material of the pipe to a material which provides higher flow rates). Once any adjustments have been made in accordance with the peak flow analysis the process passes to block 25 at which the operating parameters are determined. This is done in the same way as described above in relation to the iterative routine. At block 26 a determination is made as to whether any of the operating limits are violated. If the answer is no then the least expensive option suggested by the user, modified as necessary by application of the peak flow analysis, can be taken as the final rehabilitation strategy. If the answer is yes as is almost certainly going to be the case in most applications, the process moves on to block 27. At block 27 the routine of FIGS. 3a and 3b described above is performed to determine the hydraulic significance of the pipes which are then ordered accordingly. This block can be omitted if the determination of hydraulic significance has been performed as a preliminary step to the start of this procedure. At block 28 a selection of the most hydraulically significant pipes are set to three size larger than initially proposed in the least expensive strategy. The selection of the most hydraulically significant pipes can be made on a number of basis as mentioned above. Making the pipes three sizes larger is to some extent arbitrary adjustment but one which has been found to provide satisfactory results. At block 29 all those pipes not increased in size to three sizes larger are increased in size to one size larger than the initially proposed least expensive option. At block 30 the peak flow analysis is applied once more. The peak flow analysis is provided at this stage in the routine on the assumption of resizing of pipes in blocks 28 and 29 such that hydraulically significant pipes are three times larger than the minimum rehab.pipes and all other rehab.pipes are one size larger than the smallest rehab.pipe option. The reason for doing this is that increasing the size of some pipes may mean that the flow pattern for the network is affected so that other pipes no longer need to have as large a minimum size as previously required when the peak flow analysis was conducted at block 24. It will be appreciated that each time the peak flow analysis is performed there must first be a conventional network analysis of the flow through the network based on the modified pipe sizes. Once the peak flow analysis has been performed, and the minimum size of any pipes adjusted accordingly, a further determination of operating limit violations is made at blocks 31 and 32. If there are no violations, the strategy as modified by the above routine is taken as the start strategy for the iterative routine of FIG. 1. If operating limit violations do exist further modification of the strategy is required before the iterative routine can begin. Thus the procedure passes on to block 33 at which all rehab.pipes are set to their maximum possible sizes in the network. A further limit violation assessment is made at blocks 34 and 35 and if no limit violations exist this strategy is used as the start strategy for the iterative routine. If operating limit violations still exist a further test is conducted at block 36 to determine whether or not the original network had operating limit violations. If it did not, the procedure passes on to block 37 at which all rehab.pipes are set to one size larger than the original size. This is then used as the start strategy. If, on the other hand, the original network did have operating limit violations the procedure moves on to block 38 at which all rehab.pipes are set to the maximum possible rehabilitation size available. This then is used as the start strategy for the iterative routine. The iterative routine has been described above at some length in relation to FIG. 1. It will be appreciated that an early step in the procedure is to unlock all of the pipes (i.e. block 2 of FIG. 1). This will include unlocking any pipes which have been resized by application of peak flow analysis at block 30. This is desirable because increasing the size of some pipes within the network may allow the minimum acceptable size of other pipes to be reduced. However, an effect of this may be that as a result of the iterative routine some pipes are reduced to below the minimum size that might be dictated by the peak flow analysis calculations. Thus, as a final procedure once the iterative routine has completed, and prior to reporting the final rehabilitation strategy, the peak flow analysis may be performed a further time and any pipes which are found to be below the minimum size suggested by the peak flow analysis can be increased in size accordingly. This is a relatively pragmatic post optimisation procedure. It is conceivable that as a result of such resizing, the maximum default pressure or some internal pipe pressure threshold may possibly be exceeded. However, it is considered that this will be negligible in practice. Thus, in summary, the above example of the present invention provides a method of optimising a pipe network rehabilitation strategy in a novel way and which further includes novel methods for determining the hydraulic significance of pipes within a pipe network and the required peak flow capacity of any particular pipe within the network. It will be appreciated by the skilled person that many modifications can be made within the framework outlined above and that the optimisation program could accommodate a variety of additional user specified conditions. For instance, the network planner may place a minimum permissible size for pipes within the network not withstanding that the optimisation process might suggest that smaller pipes would meet flow demands etc. Also, the planner may limit the reduction in size of the rehab.pipe compared with the original pipe to just one or maybe two sizes below the original pipe size. Similarly, the planner may require certain pipe rehabilitation techniques or pipe materials to be used in certain parts of the network. The manner in which these, and other conditions, could be included in the process will be clear to the skilled reader. It will also be appreciated that the invention is not limited to the optimisation of the networks during a rehabilitation process. For instance, this same procedure could be used as one step in the design process for a new network. In addition, it will be appreciated that optimisation may be performed by reference to factors other than costs simply by replacing the cost table with any appropriate xe2x80x9cpreferencexe2x80x9d list. It will also be appreciated that certain aspects of the invention, in particular the determination of hydraulic significance and the manner in which peak flow analysis may be made, may have applications outside the optimisation process of the present invention. That is to say, there may be other operations, or optimisation procedures, which could benefit from these particular novel aspects of the present invention independently from the iterative routine which lies at the core of the present optimisation process. Other possible modifications will be readily apparent to the appropriately skilled person, as will other possible applications of the methods of determining hydraulic significance and of dividing the network into xe2x80x9cpipe treesxe2x80x9d and xe2x80x9cpseudo spurs.
	claims	1. A fuel bundle assembly for a boiling water nuclear reactor comprising a plurality of fuel rods having respective fuel columns therein, and arranged in an ordered array, extending between upper and lower support structures, said plurality of fuel rods enclosed within a hollow, open-ended channel member; at least one water rod supported on the lower support and extending upwardly toward said upper support, said at least one water rod having an upward flow path including at least one inlet at a lower end of said upward flow path but no outlets in said upward flow path, and a downward flow path including at least one outlet located only at a lower end of said downward flow path, said outlet located in a range of 35% to 65% of the height of the fuel column; wherein said upward flow path is defined by at least first and second tube portions of relatively larger and smaller diameters, and said downward flow path is defined by an annular chamber surrounding the tube portion of relatively smaller diameter. 2. The assembly of claim 1 wherein said fuel rods are supported by a plurality of spacers, and wherein said at least one outlet in said downward path is located above a respective one of said spacers in said range. claim 1 3. A fuel bundle assembly for a boiling water nuclear reactor comprising a plurality of fuel rods having respective fuel columns therein, and arranged in an ordered array, extending between upper and lower support structures, said plurality of fuel rods enclosed within a hollow, open-ended channel member; at least one water rod supported on the lower support and extending upwardly toward said upper support, said at least one water rod having an upward flow path defined by upper and lower relatively narrow portions and a middle relatively wider portion; and a downward flow path surrounding the upper relatively narrow portion of said upward flow path, said downward flow path having at least one outlet located in a range of 35% to 65% of the height of the fuel columns. 4. The assembly of claim 3 wherein no additional outlets are provided in said water rod. claim 3
	summary
	summary
	abstract	A pressurized water nuclear reactor (PWNR) includes a core having a containment shield surrounding a reactor vessel having fuel assemblies that contain fuel rods filled with fuel pellets, and control rods, and a steam generator thermally coupled to the reactor vessel. A flow loop includes the steam generator, a turbine, and a condenser, and a pump for circulating a water-based heat transfer fluid in the loop. The heat transfer fluid includes a plurality of nanoparticles having at least one carbon allotrope or related carbon material dispersed therein, such as diamond nanoparticles.
046876286	claims	1. A flexible support structure for the upper ends of first and second pluralities of rod guides of respective first and second different types disposed as corresponding, interleaved first and second matrices thereof in parallel axial relationship within an inner barrel assembly of a pressurized water reactor vessel for receiving therein respective, corresponding first and second different types of rod clusters, the inner barrel assembly occupying a central portion of the vessel and being of a vertical height extending from a first plate of a lower elevation to a second plate of a higher elevation, each of said rod guides being of elongated configuration and of an axial length corresponding substantially to the vertical height of said inner barrel assembly and said first and second pluralities of rod guides being disposed in parallel axial relationship in an array of interleaved, respective first and second matrices with the bottom ends thereof affixed to said first plate and the top ends thereof disposed adjacent said second plate, comprising: a first matrix of plural top support plates of a first type disposed on and connected to the respective top ends of said first plurality of rod guides of said first type, each said top support plate of said first type comprising a unitary structure of plural arm segments in an annular configuration and having a periphery generally corresponding to the configuration of the respectively associated top end of said rod guide of said first type and an interior opening permitting axial passage therethrough of a corresponding rod cluster of said first type, said plural arm segments comprising a plurality of successive major arms having corresponding peripheries and the peripheries of successive pairs of adjacent major arms defining a plurality of corresponding exterior vertices; a second matrix of plural top support plates of a second type disposed on and connected to the respective top ends of said second plurality of rod guides of said second type, each said top support plate of said second type comprising a unitary structure of plural arm segments having a periphery generally corresponding to the configuration of the top end of said respectively associated rod guides of said second type and an interior opening permitting axial passage therethrough of a corresponding rod cluster of said second type, said plural arm segments comprising a plurality of successive major arms having corresponding peripheries and the peripheries of successive pairs of adjacent major arms defining a plurality of corresponding interior vertices, the interior vertices of each said top plate of said second type corresponding to respective, exterior vertices of each said top plate of said first type for receiving a respective, said exterior vertex therein in mating relationship; said first and second matrices of said top plates being assembled in interdigitated relationship with the interior vertices of said top plates of said second type within said array receiving, in mating relationship therein, respectively corresponding exterior vertices of respective, contiguous said top plates of said first type; a linkage connecting position at each vertex of one of said first and second top plates and a linkage connecting position on each of the adjacent major arms of the pair associated with the mating vertex of the other of said first and second top plates; and a flexible linkage interconnecting each said vertex linkage connecting position of said one of said first and second top plates with said linkage connecting positions on the respective adjacent major arms associated with the mating vertex, as received therein, of the other of said first and second top plates. a plurality of extensions depending from said second plate and respectively corresponding to said plurality of top plates of said second type; each said top plate of said second type defining a central receiving aperture for receiving a corresponding said depending extension therewithin, thereby to axially align each of said top plates of said second type and the associated said rod guides of said second type within said inner barrel assembly. each top plate of said second type includes at least a pair of aligned, first and second said major arms, said pairs of aligned major arms of said plurality of top plates of said second type being disposed in alternating transverse relative relationship in both the row and column directions of said matrix thereof; and said resilient means associated with each of said top support plates of said second type comprises a pair of first and second resilient means engaging the extremities of the respective first and second major arms of said aligned pair thereof. each said top plate of said first type further comprises a diagonal arm segment extending across each said exterior vertex thereof and integrally interconnecting each pair of major arms associated with the respective said vertex and an inward lateral extension at an intermediate position on each said major arm, associated respectively with and displaced from each vertex defined thereby; each said top plate of said second type further comprises a diagonal arm segment extending across each said interior vertex thereof and integrally connecting said adjacent major arms respectively associated with the respective said vertex, and transverse lateral extensions adjacent the extremity of each of said major arms, said transverse lateral extensions and said diagonal arm segment having an upper surface common with the upper surface of said major arms and being of reduced height relatively to the height of said major arms so as to define an undercut channel relatively thereto; said top plates of said first type being assembled with said top plates of said second type in said interdigitized relationship of said first and second matrices thereof, with said lateral extensions and diagonal arm segment associated with each said exterior vertex of each said top plate of said first type being received in said undercut channel associated with the respective said mating interior vertex of a contiguous said top plate of said second type, and thereby having superposed thereon the respective said transverse lateral extensions and diagonal arm segment associated with said respective mating interior vertex of said contiguous top plate of said second type. an alignment pin received in each of said aligned bores of the corresponding said superposed transverse extensions of said contiguous top plates of said second type and said lateral extensions of said major arms of said top plate of said first type as received in mating relationship therewith for limiting the extent of lateral displacement therebetween. each of said top plates of said first type includes a vertical extension on each of said major arms thereof at a position displaced from each associated exterior vertex defined thereby so as to be disposed adjacent the ends of the adjacent major arms of a top plate of said second type defining an interior vertex in which the said associated exterior vertex is received; and for each of said mating vertices, said vertex linkage connecting position comprises a threaded bore formed in the juncture of said adjacent major arms of said top plate of said second type, and each of said adjacent major arm linkage connecting positions comprises a threaded bore formed in the corresponding said vertical extensions on said major arms of said top plate of said first type. said vertical extensions formed on said major arms of said top plates of said first type have a top surface lower than the top surface of said major arms of said top plates of said second type when assembled in mating relationship therewith; and there is further provided: a groove in said transverse extensions and said diagonal arm segments of each of said top plates of said second type, the bottom of the groove lying in a common plane with the top surface of said vertical extensions when said top plates of said second type are assembled with said top plates of said first type with the respective vertices thereof in mating relationship; and each said flexible linkage is received within said grooves in said top plates of said second type which are contiguous to and assembled in mating relationship with a given said top plate of said first type. each said top plate of said first type is of generally square configuration and defines four exterior vertices; each said top plate of said second type is of generally cross-shaped configuration and defines four interior vertices; each given top plate of said first type has four top plates of said second type contiguous thereto, an interior vertex of each thereof receiving in mating relationship therein a corresponding exterior vertex of said given top plate of said first type; each said flexible linkage is of generally square configuration, corresponding substantially to the dimensions of said top plates of said first type, and comprises four continuously connected arms in a generally square configuration, each said flexible linkage being associated with a respective, given said top plate of said first type and rigidly connecting same in a plane transverse to the axis of said assembly and flexibly connecting same in a plane parallel to the axis of said assembly to said four contiguous top plates of said second type assembled in mating relationship therewith. each said connecting position comprises a threaded bore; and each said flexible linkage is connected to said connecting positions by bolts received therethrough and in the corresponding said threaded bores. each said top plate of said first type is of generally square configuration and defines four exterior vertices; each said top plate of said second type is of generally cross-shaped configuration and defines four interior vertices; each given top plate of said first type has four top plates of said second type contiguous thereto, an interior vertex of each thereof receiving in mating relationship therein a corresponding exterior vertex of said given top plate of said first type; each said flexible linkage is of generally star-shaped configuration, corresponding substantially to the configuration and dimensions of said top plates of said second type, and comprises four continuously connected V-shaped arms defining four exterior vertices and four corresponding, interior vertices each thereof intermediate an adjacent pair of said exterior vertices, each said flexible linkage being associated with a respective, given said top plate of said second type and flexibly connecting same to each exterior vertex of a contiguous top plate of said first type received in a corresponding interior vertex of said given top plate of said second type in mating relationship therewith. each said connecting position comprises a threaded bore; and each said flexible linkage is connected to said connecting positions by bolts received therethrough and in the corresponding said threaded bores. at least first and second matrices of plural top support plates of corresponding, at least first and second different types, disposed on and connected to the respective top ends of said corresponding pluralities of rod guides of said at least first and second types; said top support plates of said at least first and second different types having respective, mating interior and exterior vertices for assembling the respective said top support plates of said matrices thereof in interdigitated relationship with exterior vertices of one said type received in mating relationship by said interior vertices of another said type; a plurality of extensions depending from said second plate and respectively corresponding to the plurality of top plates of at least a selected one of said at least first and second different types, said top plates of said selected at least one type having central receiving apertures therein for receiving respectively corresponding ones of said depending extensions thereby to axially align same within said inner barrel assembly; and a plurality of resilient means respectively associated with said top plates of said at least one selected type, each said resilient means being secured to said second plate and contacting and exerting a vertically downward force on said respectively associated top plate to establish a frictional engaging force opposing lateral displacement of said plate from said axially aligned position thereof. a flexible linkage interconnecting a given top plate of one of said types with each contiguous top plate of said other of said types having the respective said vertices thereof in mating relationship, thereby to interconnect all of said top plates of all of said types in a concatenated relationship. at least first and second matrices of plural top support plates of corresponding, at least first and second different types, disposed on and connected to the respective top ends of said corresponding pluralities of rod guides of said at least first and second types; said top support plates of said at least first and second different types having respective, mating interior and exterior vertices for assembling the respective said top support plates of said matrices thereof in interdigitated relationship with exterior vertices of one said type received in mating relationship by said interior vertices of another said type; a plurality of extensions depending from said second plate and respectively corresponding to the plurality of top plates of at least a selected one of said at least first and second different types, said top plates of said selected at least one type having central receiving apertures therein for receiving respectively corresponding ones of said depending extensions thereby to axially align same within said inner barrel assembly; and a plurality of resilient means respectively associated with said top plates of said at least one selected type, each said resilient means being secured to said second plate and contacting and exerting a vertically downward force on said respectively associated top plate to establish a frictional engaging force opposing lateral displacement of said plate from said axially aligned position thereof. a flexible linkage interconnecting a given top plate of one of said types with each contiguous top plate of said other of said types having the respective said vertices thereof in mating relationship, thereby to interconnect all of said top plates of all of said types in a concatenated relationship. plural top support plates of at least first and second types, disposed on and connected to the respective top ends of said corresponding, at least first and second types of rod guides; said top support plates of said at least first and second types having respectively mating, exterior peripheral surfaces for assembly of each said top support plate of one said type in mating relationship with respective, contiguous and surrounding top support plates of another said type; means resiliently interconnecting each said top support plate of said one type with each of said respective, contiguous and surrounding top support plates; and each top support plate of at least said one type being adapted for connection to the upper support structure of a pressure vessel in which said elongated rod guides and respectively associated top support plates are disposed. said upper support structure of said vessel further comprises a plurality of spaced, downward extensions corresponding to and defining axes of alignment with respective said top support plates of at least a selected type; and each of said tip support plates of said selected type includes a central receiving aperture therein for receiving a respective, downward extension in the assembled relationship of said rod guides and respective top support plates with the upper support structure of said vessel. resilient means respectively associated with each of said top support plates of said selected type, connected to and extending downwardly from said upper support structure, each said resilient means selectively contacting and exerting a vertically downward force on the respective said top support plate in asid assembled relationship, to establish a frictional, engaging force opposing lateral displacement of the respective said top support plate from sai axially aligned position thereof. each said top plate of each said one type comprises plural major arms defining correspon ing, exterior vertices; each said top support plate of another said type comprises plural major arms defining corresponding, plural interior vertices and undercut channels in said major arms corresponding to said interior vertices; and each said exterior vertex defined by an adjacent pair of major arms of each said top support plate of said one type being received in the associated said undercut channel of a corresponding interio vertex of each contiguously surrounding top support plate of said another type, for assembling the respective said top support plates of s id at least first and second type in interdigitized and interlocked relationship. 2. A flexible support as recited in claim 1, further comprising: 3. A flexible support as recited in claim 2, wherein there is further provided a plurality of resilient means respectively associated with said top plates of said second type, each said resilient means being secured to said second plate and contacting and exerting a vertically downward force on a respectively associated top plate of said second type, thereby establishing a frictional engaging force opposing lateral displacement of each said top plate of said second type and the rod guide associated therewith from the said axially aligned position thereof. 4. A flexible support as recited in claim 3, wherein: 5. A flexible support as recited in claim 4, wherein each of said first and second resilient means of the pair thereof associated with each given, said top support plate of said second type is of elongated configuration and is disposed in alignment with the respectively associated aligned pair of first and second major arms of said given top plate of said second type, said respective first and second resilient means being connected at first ends thereof to said second plate at positions adjacent the correspondingly aligned said depending extensions next adjacent the said depending extension received in said given top plate of said second type. 6. A flexible support as recited in claim 5, wherein each said resilient means comprises a leaf spring. 7. A flexible support as recited in claim 3, wherein: 8. A flexible support as recited in claim 7, wherein there is further provided a vertical bore extending through each said superposed transverse lateral extension of said top plates of said second type and a corresponding, aligned bore extending partially through the corresponding lateral extension of said top plate of said first type; and 9. A flexible support as recited in claim 8, wherein: 10. A flexible support as recited in claim 9, wherein: 11. A flexible support as recited in claim 1, wherein: 12. A flexible support as recited in claim 11, wherein each of said flexible linkages is connected at the corners thereof to said connecting positions at the respective, mating interior vertices of said four contiguous top plates of said second type and is connected at intermediate positions on the respective arms thereof to respectively corresponding intermediate positions on said major arms of the respective given said top plate of said first type. 13. A flexible support as recited in claim 12, wherein: 14. A flexible support as recited in claim 1, wherein: 15. A flexible support as recited in claim 14, wherein each of said flexible linkages is connected at said four exterior vertices thereof to corresponding connecting positions at the ends of said major arms of said associated top plate of said second type and at each interior vertex thereof to the said exterior vertex of each said contiguous top plate of said first type received in mating relationship therewith. 16. A flexible support as recited in claim 15, wherein: 17. A support structure for the upper ends of at least first and second pluralities of rod guides of respective, at least first and second different types disposed as corresponding, at least first and second interleaved matrices thereof in parallel axial relationship within an inner barrel assembly of a pressurized water reactor vessel for receiving therein respective, at least first and second different types of rod clusters, the inner barrel assembly occupying a central portion of the vessel and being of a vertical height extending from a first plate of a lower elevation to a second plate of a higher elevation, each of said rod guides being of elongated configuration and of an axial length corresponding substantially to the vertical height of said inner barrel assembly, the bottom ends thereof being affixed to said first plate and the top ends thereof being disposed adjacent said second plate, comprising: 18. A support structure as recited in claim 17, wherein there are further provided stop pins interconnecting contiguous said top plates of said interdigitated matrices thereof for limiting the extent of relative, lateral displacement therebetween. 19. A support structure as recited in claim 18, further comprising: 20. A pressurized water reactor system having a vessel including an inner barrel assembly within which are disposed at least first and second pluralities of rod guides of respective, at least first and second different types in corresponding, at least first and second interleaved matrices thereof and in parallel axial relationship, said first and second pluralities of rod guides receiving therein respective, at least first and second different types of rod clusters, the inner barrel assembly occupying a central portion of the vessel and being of a vertical height extending from a first plate of a lower elevation to a second plate of a higher elevation, each of said rod guides being of elongated configuration and of an axial length corresponding substantially to the vertical height of said inner barrel assembly, the bottom ends thereof being affixed to said first plate and the top ends thereof being disposed adjacent said second plate, and a support structure for the upper ends of said rod guides comprising: 21. A reactor system as recited in claim 20, wherein there are further provided stop pins interconnecting contiguous said top plates of said interdigitated matrices thereof for limiting the extent of relative, lateral displacement therebetween. 22. A reactor system structure as recited in claim 21, further comprising: 23. A support for the top ends of a plurality of elongated rod guides of at least first and second types, generally vertically disposed within a pressurized water reactor vessel in corresponding, at least first and second interleaved matrices, said vessel having lower and upper support structures and said rod guides having lower ends fixedly supported on the lower support structure and upper ends disposed adjacent to and spaced vertically below the upper support structure, said support comprising: 24. A support as recited in claim 23, wherein said resislient interconnecting means laterally interlock said plural top support plates in a two-dimensional, concatenated relationship and resiliently restrain relative, vertical differential displacements of the individual, interconnected said top plates and associated rod guides. 25. A support as recited in claim 24, wherein said resilient conneccting means comprises a plurality of flexible linkages respectively connected to said plurality of top supoprt plates of said one type, each said flexible linkage further being connected to each of said respective, contiguous and surrounding top support plates. 26. A support as recited in claim 23, further comprising stop means interconnecting each said top support plate of said one type with each of said respective, contiguous and surrounding top support plates for limiting loads imposed on said respective, resilient interconnecting means resulting from forces tending to laterally, relatively displace the contiguous and interconnected said top support plates. 27. A support as recited in claim 26, wherein said stop means comprise pins extending between and received in respective, aligned bores provided therefor in each said top support plate of said one type and said respective, contiguous and surrounding top support plates. 28. A support as recited as recited in claim 23, wherein: 29. A support as recited in claim 28, wherein there is further provided: 30. A support as recited in claim 29, wherein said resilient means comprise leaf springs each said leaf spring having a central aperture for receiving the respectively corresponding downward extension of said top support plate, and laterally, downwardly extending arms, each said arm engaging the top surface of a respective top support plate. 31. A support as recited in claim 30, wherein each said selected top support plate is engaged by at least two said leaf springs at positions thereon so as to maintain a symmetrical force thereon relative to the axis thereof. 32. A support as recited in claim 23, wherein:
	claims	1. A multi-lens comprising: a substrate which is formed by stacking high-resistance substrates each having a plurality of lens apertures, an inner wall of which is formed by a resistance portion along a beam axis of a beam emitted by a beam source, and which has an electrode bonded around the plurality of lens apertures between the high-resistance substrates; and electrode substrates having apertures corresponding to the plurality of lens apertures, wherein the electrode substrates are bonded to two surfaces of said substrate, wherein a resistance of at least one of said electrode substrates is lower than a resistance of said resistance portion. 2. The lens according to claim 1 , wherein the resistance portion is made up of high-resistance layers formed on inner walls of apertures formed in insulating substrates, claim 1 said electrode substrates are formed by forming apertures corresponding to the lens apertures in a low-resistance substrate, and a wiring for the electrode is formed via the insulating substrates stacked on the two sides of the electrode. 3. The lens according to claim 1 , wherein the plurality of lens apertures are independently controlled. claim 1 4. The lens according to claim 1 , wherein the plurality of lens apertures are laid out to form a face-centered structure. claim 1 5. The lens according to claim 2 , wherein the low-resistance substrate is located on an outermost side to sandwich the insulating substrates, and a thickness T thereof and a diameter D of the aperture satisfy T greater than 0.3D. claim 2 6. The lens according to claim 1 , wherein the resistance of the resistance portion is not constant along a beam axis direction. claim 1 7. The lens according to claim 1 , wherein the resistance of the resistance portion has a positive differential coefficient along the beam axis. claim 1 8. The lens according to claim 1 , wherein a plurality of electrodes are present in a beam axis direction, and arbitrary potentials can be respectively applied to the plurality of electrodes. claim 1 9. The lens according to claim 8 , wherein a differential coefficient of a gradient of a voltage applied to the plurality of electrodes present in the beam axis direction is positive in an acceleration lens system and is negative in a deceleration lens system along the beam axis. claim 8 10. The lens according to claim 1 , further comprising temperature-controllable cooling means. claim 1 11. The lens according to claim 1 , wherein a resistivity of the resistance portion falls within a range from 10 6 xcexa9cm to 10 9 xcexa9cm. claim 1 12. The lens according to claim 1 , wherein the resistance portion consists of any one of silicon carbide, a nitrogen compound, and cladglass. claim 1 13. An electron beam lithography apparatus for directly writing a pattern on a substrate with an electron beam, comprising: a substrate which is formed by stacking high-resistance substrates each having a plurality of lens apertures, an inner wall of which is formed by a resistance portion along a beam axis of a beam emitted by an electron beam source, and which has an electrode bonded around the plurality of lens apertures between the high-resistance substrates; and electrode substrates having apertures corresponding to the plurality of lens apertures, wherein the electrode substrates are bonded to two surfaces of said, and wherein a resistance of at least one of said electrode substrates is lower than a resistance of said resistance portion. 14. A charged beam applied apparatus for processing using a charged beam, comprising: a substrate which is formed by stacking high-resistance substrates each having a plurality of lens apertures, an inner wall of which is formed by a resistance portion along a beam axis of a beam emitted by a charged beam source, and which has an electrode bonded around the plurality of lens apertures between the high-resistance substrates; and electrode substrates having apertures corresponding to the plurality of lens apertures, wherein the electrode substrates are bonded to two surfaces of said substrate, and wherein a resistance of at least one of said electrode substrates is lower than a resistance of said resistance portion. 15. A method of manufacturing a device, comprising: a step of applying a resist on a substrate; a step of directly writing a pattern on the substrate using an electron beam lithography apparatus; and a development step of developing the substrate, said electron beam lithography apparatus comprising: a substrate which is formed by stacking high-resistance substrates each having a plurality of lens apertures, an inner wall of which is formed by a resistance portion along a beam axis of a beam emitted by an electron beam source, and which has an electrode bonded around the plurality of lens apertures between the high-resistance substrates; and electrode substrates having apertures corresponding to the plurality of lens apertures, wherein the electrode substrates are bonded to two surfaces of said substrate, and wherein a resistance of at least one of said electrode substrates is lower than a resistance of said first resistance portion. 16. A method of manufacturing a device, comprising: a step of applying a resist on a substrate; a step of directly writing a pattern on the substrate using a charged beam applied apparatus; and a development step of developing the substrate, said charged beam applied apparatus comprising: a substrate which is formed by stacking high-resistance substrates each having a plurality of lens apertures, an inner wall of each of which is formed by a resistance portion along a beam axis of a beam emitted by an electron beam source, and which has an electrode bonded around the plurality of lens apertures between the high-resistance substrates; and electrode substrates having apertures corresponding to the plurality of lens apertures, wherein the electrode substrates are bonded to two surfaces of said substrate, wherein a resistance of at least one of said electrode substrates is lower than a resistance of said first resistance portion. 17. An electrostatic lens comprising: a substrate which is formed by stacking high-resistance substrates each having a lens aperture, an inner wall of which is formed by a resistance portion along a beam axis of a beam emitted by a beam source, and which has an electrode bonded around the lens aperture between the high-resistance substrates; and electrode substrates having an aperture corresponding to the lens aperture, wherein the electrode substrates are bonded to two surfaces of said substrate, and wherein a resistance of at least one of said electrode substrates is lower than a resistance of said resistance portion. 18. A multi-lens comprising: a plurality of electrode substrates, each of which is formed with a plurality of apertures; and substrates having apertures corresponding to the plurality of lens apertures, wherein the substrates are sandwiched by the plurality of electrode substrates, wherein the substrates have a relieve function of relieving a charge loaded to the substrates by striking an electron or charged particle to a side wall of the plurality of lens apertures.
041475895	summary	BACKGROUND OF THE INVENTION 1. Field of the Invention This invention pertains to control rods for nuclear reactors and more particularly to control rods having a coupling between the control rod and its associated drive shaft. 2. Description of the Prior Art A nuclear power plant generates electricity from heat produced by fissioning of a fissile material. The fissile material or nuclear fuel, is contained within fuel assemblies; a plurality of fuel assemblies comprise a nuclear core. In order to extract the nuclear heat produced by fissioning of the fuel, the core is placed within a reactor vessel and a coolant, such as water or liquid sodium, is made to flow through the core so as to transfer the nuclear heat to the reactor coolant. The heated fluid is then used to generate steam which is used to drive conventional steam turbine-electrical generator apparatus. Control of the reactor is usually achieved by control rods which are dispersed throughout the nuclear core and are mounted for movement into and out of the core. The control rods function by absorbing excess neutrons produced by the nuclear reaction; hence, proper radial distribution of the control rods produces a substantially uniform power distribution across the core. On the other hand, proper axial positioning of the control rods permits the nuclear reactor to achieve design power levels. Given the above nuclear, thermal, fluid flow, and mechanical functions, and the attendant constraints and requirements associated therewith, it is readily understandable that a complicated and sophosticated structure for supporting the core, a sufficiently rigid coolant flow channeling means, and a precise control rod guide means are necessary within the reactor vessel. Moreover, since most typical commercial nuclear power plants are required to be refueled on the order of once every year, the complete apparatus within the reactor vessel is required to be disassembled in order to allow replacement of the nuclear fuel elements in the core. Further, since the reactor must be positively shut down during the refueling operations to comply with reactor safety standards, the control rods and the control rod guide means are often designed so as to be capable of being left in the core throughout reactor refueling. This, of course, even further complicates the design of the apparatus within the reactor vessel. In the prior art, the requirement of leaving the control rods in the nuclear core during refueling is achieved by providing a manually operated disconnect joint between the control rod and the control rod drive shaft. However, in this art, the disconnect joints are such that the reactor vessel must be unsealed to allow installation of a special tool which is used to manually actuate the disconnect joint thereby uncoupling the control rod from the drive shaft. Manual actuation of the disconnect joint is also being required to recouple the control rod to the drive shaft. While this prior art type of joint provides for high reliability, there are a number of disadvantages inherently associated with it. For example: a relatively large amount of time is required to wait for the reactor to cool down, both thermally and nuclearly, before the reactor vessel may be unsealed and personnel can safely be present; a relatively long amount of time is necessary for manually disconnecting each of the joints; the long time required to manually disconnect the joints increases the radiation exposure of personnel working on refueling. SUMMARY OF THE INVENTION The aforementioned problems of the prior art are overcome by the present invention which provides a disconnect coupling between a control rod and its drive shaft which has a high degree of reliability while allowing for remote coupling and uncoupling of the control rod from the drive shaft by utilizing the actuating force of a control rod drive mechanism. In one embodiment of this invention, the coupling between the drive shaft and the control rod comprises the engagement of an expandable collet attached to the drive shaft, and axially movable with respect thereto, with one or more grooves formed within the control rod. A rod-like plunger forming the end of the drive shaft and extending through the collet is utilized to expand the collet into mating engagement with the grooves or to release the collet from mating engagement. Hence, the position of the plunger relative to the collet causes engagement or disengagement of the coupling. The plunger position relative to the collet is obtained by first lowering and then raising the control rod drive shaft. The lowering motion causes a pin which is attached to the collet to rotate a grooved cylinder attached to the drive shaft. The pin is thereby aligned with an axial groove in the cylinder such that the drive shaft is allowed to move in an upward direction relative to the collet. With the plunger in this position, that is, not expanding the collet, a biased resiliency of the collet causes the collet to move inward and out of engagement with the grooves in the control rod. In order to effectuate engagement of the coupling, the drive shaft is again lowered causing the pin to rotate the cylinder. However, this time the pin is aligned with a groove in the cylinder having a shouldered stop. Since the downward motion of the drive shaft causes the plunger to expand the collect and the stop maintains the axial position of the plunger relative to the collet, engagement of the coupling results. In another embodiment, a different type of coupling is used in conjunction with a rotating cylinder. In this embodiment, lugs attached to the control rod either interlock with or are free of coacting grooves formed in the cylinder and attached to the control rod to effectuate coupling or uncoupling, respectively. On lowering and then raising the control rod drive shaft, the lugs attached to the control rod cause the cylinder which is attached to the drive shaft to rotate. This results in the lugs attached to control rod being aligned either with a shouldered groove in the cylinder or with a non shouldered groove in the cylinder. The former position results in engagement of the coupling while the latter position results in disengagement of the coupling.
041486080	claims	1. A method of preparing isotope-containing samples for use in studies utilizing radioactive isotopes, said method comprising the steps of (a) combusting a sample of material containing .sup.3 H and .sup.14 C in a combustion chamber to produce combustion products containing .sup.3 H.sub.2 O and .sup.14 CO.sub.2 in gaseous form, (b) continuously exhausting the .sup.3 H.sub.2 O and .sup.14 CO.sub.2 gas from said combustion chamber during the combustion of said material, (c) continuously cooling the exhausted combustion products in a heat exchanger to convert the .sup.3 H.sub.2 O gas to a liquid during the combustion of said material, (d) continuously removing said liquid from said heat exchanger during the combustion of said material and transferring said liquid to a sample collection vessel to provide a liquid sample containing the recovered .sup.3 H.sub.2 O for use in studies utilizing radioactive isotopes, (e) maintaining the .sup.14 CO.sub.2 in gaseous form during recovery of the .sup.3 H.sub.2 O in liquid form, (f) continuously contacting the .sup.14 CO.sub.2 with a trapping agent in a trapping chamber to convert the .sup.14 CO.sub.2 to a liquid during the combustion of said material, (g) removing the resulting .sup.14 C-containing liquid from said trapping chamber to recover the .sup.14 C and transferring said liquid to a sample collection vessel to provide a liquid sample containing the recovered .sup.14 CO.sub.2 for use in studies utilizing radioactive isotopes, (h) and purging said combustion chamber, heat exchanger and trapping chamber between the combustion of successive isotope-containing samples. (a) combusting a sample of material containing .sup.14 C in a combustion chamber to produce combustion products containing .sup.14 CO.sub.2 in gaseous form, (b) continuously exhausting said .sup.14 CO.sub.2 -containing combustion products from said combustion chamber during the combustion of said material, (c) continuously contacting the exhausted combustion products with a trapping agent in a trapping column to convert the .sup.14 CO.sub.2 to a liquid during the combustion of said material, said trapping column comprising a series of smoothly contoured bulbous chambers each adjacent pair of which are interconnected by a smoothly contoured necked down portion with the interconnecting walls of said chambers and said necked down portions forming a smooth curvilinear configuration whereby said liquid is distributed along the length of said column in said chambers while gas is flowing therethrough and is effectively mixed with the gas flowing therethrough to effect a reaction therebetween, whereby fractional interaction between said liquid and said gas stream is effected along the length of said column, (d) removing said liquid from said trapping column to recover the .sup.14 C and transferring said liquid to a sample collection vessel to provide a liquid sample containing the recovered isotope for use in studies utilizing radioactive isotopes, (e) and purging said combustion chamber and trapping column between the combustion of successive isotope-containing samples. 2. A method of preparing samples as set forth in claim 1 wherein said combustion chamber is flushed with a fluid subsequent to the combustion step so as to sweep any residual combustion products out of said chamber and on through said heat exchanger and said trapping chamber to achieve substantially complete recovery of the .sup.3 H.sub.2 O and substantially complete trapping of the .sup.14 CO.sub.2 while purging the system prior to combustion of the next sample, and flushing said trapping chamber with a fluid subsequent to the removal of the .sup.14 C-containing liquid therefrom to achieve substantially complete recovery of the .sup.14 C while purging the trapping chamber prior to combustion of the next sample. 3. A method as set forth in claim 1 wherein said trapping chamber comprises a series of smoothly contoured bulbous chambers each adjacent pair of which are interconnected by a smoothly contoured necked down portion with the interconnecting walls of said bulbous chambers and said necked down portions forming a smooth curvilinear configuration whereby said liquid is distributed along the length of said column in said bulbous chambers while gas is flowing therethrough and is effectively mixed with the gas flowing therethrough to effect a reaction therebetween, whereby fractional interaction between said liquid and said gas stream is effected along the length of said trapping chamber. 4. A method of preparing isotope-containing samples for use in studies utilizing radioactive isotopes, said method comprising 5. A method of preparing samples as set forth in claim 4 wherein said exhausting and contacting steps are continued after completion of the combustion of the sample material until substantially all the .sup.14 CO.sub.2 is recovered from the combustion chamber. 6. A method of preparing samples as set forth in claim 4 wherein said combustion chamber is flushed with a fluid subsequent to the combustion step so as to sweep any residual combustion products out of said chamber and on through said trapping column to achieve substantially complete trapping of the .sup.14 CO.sub.2 while purging the system prior to combustion of the next sample, the flushing said trapping column with a fluid subsequent to the removal of the .sup.14 C-containing liquid therefrom to achieve substantially complete recovery of the .sup.14 C while purging the trapping column prior to combustion of the next sample. 7. A method of preparing samples as set forth in claim 6 wherein the flushing fluid for removing the liquid from said trapping column is an inert gas. 8. A method of preparing samples as set forth in claim 4 which includes the step of supplying oxygen to said combustion chamber at a controlled rate during the combustion of said material.
	abstract	A nuclear power plant (18) and its heat exhanger (26) are enclosed in an envelope (22) which is suspended above a bored shaft (14) from a support stem (30). When appropriate, the stem (30) can be melted by a furnace (34) to drop the envelope (22) to the bottom of the shaft (14). Sand (42) can then be dropped onto the envelope (22) through a drainage pipe (46). While the nuclear power plant (18) is operating and suspended in the shaft, spent fuel rods (70) are dropped into a sand blasting machine""s hopper (130), mixed with sand and dropped into a bag (134) containing a small explosive device. The bag (134) is then dropped to the bottom of the shaft (14) and the explosive detonated to scatter the contents of the bag (134). Optionally, more sand or earth is then added to reduce heat and radiation to acceptable levels.
048184691	summary	The present invention relates generally to a seal for turning valve bodies and more particularly to valves used in nuclear-engineering plants. From DE-OS No. 2,748,135 it is known to use a flexible graphite laminate as one of the materials for sealings and packings, whereby the laminate is applied to other materials for example a suitable metal. DE-OS No. 2,612,296 and DEP No. 2,039,355 also describe the use of flexible graphite material in the fabrication of seals. Flexible graphite materials are generally known according to the state of the art and are described, in addition to the aforecited publications, in DE-OS No. 2,855,408 and DE-OS No. 3,117,567. The essential advantages of flexible graphite materials may be found in the following properties: The materials are liquid- and gas-tight: they are highly temperature-resistant; they are resistant to radiation; They are resistant to most chemicals; and they have great flexibility and good elasticity and, in some applications, they also act as a self-lubricating seal The latter property, however, is coupled with the disadvantage that in a frequently actuated valve, the graphite material is relatively quickly worn off. In general terms, the useful life of such a seal is relatively short. In valves employed in radioactive plants, e.g., in plants for the reprocessing of nuclear fuel, the useful life of the valve is of special importance inasmuch as the replacement of worn-off parts in radioactive plants is very costly because the operation of the plant must be temporarily stopped, which naturally is extremely undesirable. Sealing materials of polytetrafluoroethylene plastics have not been found satisfactory since PTFE, even though chemically one of the most stable plastics, has very low radiation resistance and also has little resilience. In addition, various copolymers have been developed but their chemical stability, however, is small. For these reasons, it may be said that for the fluidized currents of the Purex process, no plastics are available for seals with a calculable useful life. It is the purpose of the invention to improve the seal of the type described in such a manner that its useful life is increased. This purpose is attained by the distinguishing features indicated in the appended claims. Advantageous embodiments and further refinements of the invention also become apparent from the appended claims. In short, in accordance with the present invention, the seal composed of flexible graphite materials is coated with a thin, flexible layer of tantalum. Tantalum has excellent ductility which is highly desirable for the intended purpose. Tantalum also has very good sliding or lowfriction properties so that a seizing or jamming of the valve body does not occur. In acccordance with the present invention, the tantalum coating layer is sufficiently thin to remain flexible so that the good flexibilty properties of the graphite covered by tantalum are preserved. It should also be stressed that the seal according to the present invention is likewise well suited for chemical plants in that tantalum is chemically very stable.
	claims	1. A method comprising:mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials, the powdered fissile material comprising grains having grain boundaries;pressing the mixed fissile and the additive into a pellet; and,sintering the pellet to a temperature greater than the melting point of the additive sufficient for melting of the additive into the grain boundaries of the fissile material and densifying the pellet,wherein the additive has a melting point greater than the sintering temperature of the fissile material, and has a median particle size less than that of the UN or U3Si2. 2. The method recited in claim 1 wherein the powdered fissile material is UN, and the additive is selected from the group consisting of tungsten and alloys containing at least 50 atomic % thereof, and UO2. 3. The method recited in claim 1 wherein the additive is present in amounts less than 20 weight percent of the fissile material. 4. The method recited in claim 1 wherein the sintering is selected from the group consisting of pressureless sintering, hot pressing, hot isostatic pressing, spark plasma sintering, field assisted sintering, and flash sintering. 5. The method recited in claim 1 wherein the median particle size of the additive is less than 10% of the median particle size of the UN or U3Si2. 6. The method recited in claim 1 wherein the median particle size of the additive is less than 1% of the median particle size of the UN or U3Si2. 7. The method recited in claim 1 wherein the vapor deposition is used to coat the outside of the unsintered pellet with the additive and to penetrate the additive into the pellet body of the UN or U3Si2. 8. The method recited in claim 1, wherein the powdered fissile material is U3Si2, and the additive is selected from the group consisting of molybdenum, titanium, chromium, thorium, tungsten, niobium, and zirconium, alloys containing at least 50 atomic % thereof, BeO, and UO2. 9. The method recited in claim 1 wherein the additive coats to the U3Si2 or UN powders to form protective layers through vapor deposition before pressing into pellets and sintering. 10. The method recited in claim 9 wherein the vapor deposition is selected from the group consisting of physical vapor deposition, chemical vapor deposition, and atomic layer deposition. 11. A method comprising:mixing a powdered fissile material UN with an additive, the powdered fissile material comprising grains having grain boundaries;pressing the mixed fissile and the additive into a pellet; andsintering the pellet to a temperature greater than the melting point of the additive sufficient for melting of the additive into the grain boundaries of the fissile material and densifying the pellet,wherein the additive has a melting point lower than the sintering temperature of the fissile material, and the additive is a borosilicate glass. 12. A method comprising:mixing a powdered fissile material U3Si2 with an additive, the powdered fissile material comprising grains having grain boundaries;pressing the mixed fissile material and the additive into a pellet; andsintering the pellet to a temperature greater than the melting point of the additive sufficient for melting of the additive into the grain boundaries of the fissile material and densifying the pellet, wherein the additive has a melting point lower than the sintering temperature of the fissile material, and the additive is a borosilicate glass.
	abstract	A measurement apparatus has a first detector for measuring an intensity such that a sheet-shaped beam of synchrotron radiation is integrated over the entire range of the beam in the thickness direction thereof; a second detector for measuring the intensity of the beam at two points where positions along the direction are different; and a calculating device for calculating the magnitude of the beam in the direction on the basis of the detections by the first and second detectors.
042235758	description	DESCRIPTION OF THE PREFERRED EMBODIMENT In order to refuel a typical light water nuclear reactor, it is first necessary to remove the reactor vessel closure head studs so that the closure head may be removed in order to access the fuel assemblies in the reactor core. The invention described herein provides apparatus for facilitating the removal or replacement of these studs. Referring to FIG. 1, a nuclear reactor referred to generally as 10 comprises a reactor vessel 12 with a closure head 14 attached to the top thereof. A core 16 comprises fuel assemblies (not shown) that produce heat in a conventional manner. A coolant such as water is circulated through reactor vessel 12 and in heat transfer relationship with core 16 thereby heating the coolant which is then circulated through heat exchange equipment for the production of steam and electricity. Apparatus for controlling the nuclear reaction in core 16 such as control rod drive mechanisms 18 are mounted on closure head 14 and extend therethrough and into contact with control rods 20. Closure head 14 is attached to reactor vessel 12 by means of studs 22. Studs 22 have an integral cap 24 on the top thereof and threads 26 on the bottom end. Studs 22 extend through first bores 28 in closure head 14 and into second bores 30 of reactor vessel 12. First bores 28 are not threaded while second bores 30 have threads therein that are complimentary to threads 26. Nuts 32 fit on studs 22 and engage studs 22 by means of threads not shown. Studs 22 extend into second bores 30 of reactor vessel 12 and are threaded therein. Once in this position, studs 22 are stretched into position by the use of stud tensioners well known in the art such as those manufactured by Biach Industries, Inc. of Cranford, N.J. When studs 22 are stretched and nuts 32 are tightened onto studs 22, studs 22 are in a preload tension state so that when reactor vessel 12 is internally pressurized the pressurized reactor coolant is retained. Referring now to FIGS. 2, 3, and 4 the stud turnout tool is referred to generally as 34 which is used to remove or insert studs 22 from first bore 20 and second bore 30. Tool 34 comprises an engagement mechanism 36 for engaging caps 24 of studs 22, rotation mechanism 38 for rotating engagement mechanism 36, and drive mechanism 40 for driving rotation mechanism 38. Tool 34 also comprises a carriage 42 and a support device 44 for supporting the carriage 42 and the weight of studs 22. Still referring to FIGS. 2, 3, and 4, carriage 42 comprises support members such as plate 46 and vertical member 48 for supporting the various components of tool 34. Drive mechanism 40 comprises a motor 50 which may be a one horsepower electric or air motor mounted vertically on vertical member 48 and a drive shaft 52 which is attached to motor 50 and rotatably disposed in plate 46. A first gear 54 is attached to drive shaft 52 and is capable of rotation when drive shaft 52 is rotated by motor 50. Rotation mechanism 38 comprises bearings 56 mounted on plate 46 which rotatably support gear segment 58 so that gear segment 58 may rotate relative to plate 46. Gear segment 58 is a metal member having an opening therein for accommodating cap 24 and is mounted in second gear 60 which engages first gear 54 so that when first gear 54 is rotated second gear 60 will also rotate. The rotation of second gear 60 causes gear segment 58 to also rotate. Gear segment 58 may be bolted to second gear 60 or merely inserted therein. When gear segment 58 is merely inserted in second gear 60, gear segment 58 is formed such that it is keyed into second gear 60 as shown in FIG. 4. Engagement mechanism 36 comprises inserts 62 and bar 64. Inserts 62 are mounted on gear segment 58 so as to coincide with the corners of cap 24 and extend down along the opening in gear segment 58 at least the length of cap 24. A lifting bolt 66 may be removably inserted into the top of cap 24 so that support device 44 may be easily attached to studs 22. Bar 64 may be bolted to at least two inserts 62 so as to extend along the side of lifting bolt 66. Bar 64 thus serves to prevent lifting bolt 66 from turning while studs 22 are rotated. Referring now to FIG. 5, when caps 24 of studs 22 are of hexagonal shape as shown in FIG. 5, then inserts 62 are formed in a shape to be complementary to the corners of caps 24. In this configuration, the flat sides of caps 24 may abut the flat sides of gear segment 58 such as at location 68. However, should the flat sides of caps 24 not extend to within close proximity of the flat sides of gear segment 58, spacers 70 may be bolted to second gear 60 as shown in FIG. 4. Spacers 70 extend down the inside of gear segment 58 the length of caps 24 so that caps 24 rotate when gear segment 58 rotates. Referring now to FIG. 6, when caps 24 have the shape as those shown in FIG. 6, no spacers 70 or jaws 62 are needed and bar 64 may be bolted to gear segment 58. Referring again to FIGS. 2, 3, and 4, support device 44 comprises a load equalizing device 72 which may be an air cylinder with self relieving regulator such as a Smoothie Model 10100 which may be purchased from Sierra Industrial Products, Inc. Load equalizing device 72 may be suspended from an overhead crane 74 or similar device and connected to lifting bolt 66 by connecting rod 76. Load equalizing device 72 serves to apply an upward force on stud 22 equal to the weight of stud 22 so that when stud 22 is rotated into or out of closure head 14 threads 26 will not be damaged. Generally studs 22 weigh approximately 750 pounds, so the load equalizing device can be set for that weight and will thus maintain a vertical force of approximately 750 pounds on stud 22. Connecting rod 76 has a substantially conical member 78 near its lower end. When connecting rod 76 is not attached to lifting bolt 66, crane 74 can cause support device 44 to be raised which by causing conical member 78 to contact ring 80. Since ring 80 is connected to carriage 42 by struts 82, contact of conical member 78 with ring 80 can be used to support carriage 42. Therefore, crane 74 may be used to transport and align tool 34. Carriage 42 is also equipped with handles 84 that have control triggers 86 mounted thereon. Control triggers 86 may be connected to drive mechanism 40 and to crane 74 so as to enable an operator to grasp handles 84 and to control tool 34 by manual manipulation. Wooden bumpers 88 may also be provided on carriage 42 to prevent damage to tool 34 should tool 34 be accidentally bumped against an adjacent stud 22 during removal or insertion of a stud 22. OPERATION When it is desired to remove closure head 14 from reactor vessel 12, a stud tensioner such as the one manufactured by Biach Industries, Inc. of Cranford, N.J., is used to loosen nut 32 and relieve the tension in stud 22. An operator then grasps handles 84 and trigger 86 while crane 74 supports the weight of tool 34 by contact of conical member 78 with ring 80. At this point the operator positions engagement mechanism 36 over cap 24 of studs 22 and crane 74 lowers the crane apparatus so that engagement mechanism 36 is in contact with cap 24 and conical member 78 is not in contact with ring 80. Lifting bolt 66 is then screwed into the top of cap 24 if it is not permanently installed therein and connecting rod 76 is attached to lifting bolt 66. The apparatus of crane 74 is caused to be raised so that an upward force is applied on lifting bolt 66 by support device 44. Support device 44 is then set to apply a constant vertical force on lifting bolt 66 that is approximately equal to the weight of stud 22 so that stud 22 and the associated threads are not damaged while stud 22 is removed. The operator then activates drive mechanism 40 by means of trigger 86 which causes motor 50 to rotate drive shaft 52 which in turn causes first gear 54 to rotate. The rotation of first gear 54 causes second gear 60 to rotate which causes gear segment 58 to rotate about bearing 56. Since inserts 62 are attached to gear segment 58 and in contact with cap 24, the rotation of gear segment 58 causes jaws 62 and cap 24 to rotate. The rotation of cap 24 which is an integral portion of stud 22 causes stud 22 to rotate out of second bore 30. As stud 22 is thus being unscrewed, support device 44 supports the weight of stud 22. When the lower end of stud 22 has been raised entirely out of second bore 30 and into first bore 28, a flat member 90 is slid into gap 92 between reactor vessel 12 and closure head 14 and stud 22 is lowered onto flat member 90 as shown in FIG. 7. Connecting rod 76 is then disconnected from lifting bolt 66 and tool 34 is removed from stud 22 and placed on another stud 22. Another crane such as crane 74 may then be attached to lifting bolt 66 to remove the stud 22 from first bore 28. As an alternative, tool 34 may also be used to lift stud 22 from first bore 28. This sequence may be continued until all studs 22 are removed from closure head 14 so that closure head 14 may be removed from reactor vessel 12. Of course, the reverse of this procedure may be utilized to insert a stud 22 into closure head 14. Therefore, the invention provides a device that is capable of inserting or removing reactor closure head studs without damaging the studs or associated apparatus.
056053614	summary	BACKGROUND OF THE INVENTION The invention disclosed herein relates to nozzles for vessels and piping that are installed either initially or as replacements without any welding, and to the installation of such nozzles without welding the nozzle to the vessel. (A "nozzle" may also be, or include as part thereof, a sleeve and/or piping. A "vessel" may also be large bore piping.) The invention more particularly relates to nozzles and procedures which replace nozzles that are attached to the vessel on the inside diameter of the vessel with a J groove structural weld, and has particular application to nozzles and procedures which replace or initially install nozzles in pressure vessels and large bore piping of pressurized water reactor nuclear power facilities which have failed due to phenomena known as Primary Water Stress Corrosion Cracking, PWSCC. The invention also particularly relates to nozzles and procedures for installing nozzles without welding as replacements or initial installations in large bore piping. A typical nuclear power generating facility includes in part a reactor vessel, steam generator, pressurizer vessel, and a reactor coolant piping system, all of which operate under high pressure. Nozzles are attached to the vessels and/or piping for a number of purposes, e.g., for connecting piping and instrumentation, vents, and to secure control element drive mechanisms and heater elements. A typical pressurizer vessel 20 is shown in FIG. 1 with nozzles 22 for vents, nozzles 24 for liquid level, nozzles 25 for pressure sensing, a nozzle 26 for temperature measuring, and a number of nozzles 27 for heating elements. All of those nozzles were heretofore welded to the pressurizer vessel at the time of original manufacture. As shown in FIG. 2, cladding 29 is welded to the interior of the pressurizer vessel which is made of carbon steel. The temperature nozzle 26 shown in cross section in FIG. 2, which is exemplary of the welded nozzles 22-27, passes through a hole or bore 30 in the pressurizer vessel 20 and is structurally welded at its interior end 32 to the vessel 20 with a J-weld 34 along the interior opening to the bore 30. The diameter of nozzle 32 is slightly less than the diameter of bore 30, so that there is a small annular space 36 between the nozzle exterior and the wall of bore 30. The J-weld 34 also functions as a seal weld to seal the annular space 36. A reactor vessel (not shown) similarly has nozzles represented by nozzle 26 in FIG. 2 welded thereto. The piping of the reactor coolant system (not shown) also includes similar nozzles welded thereto. Further details of pressurizer vessels, reactor vessels and coolant system piping, in particular, and nuclear power facilities, in general, are known to those of skill in the art. As mentioned, the invention has particular application to the prevention of nozzle failures in nuclear power facilities due to PWSCC phenomena, which occurs on components having a susceptible material, high tensile stresses, and which are in a corrosive environment, conditions which primarily exist on nozzle penetrations in the pressurizer vessel, reactor coolant piping, and the reactor vessel. Such failures are manifested by cracking, which the applicant recognized resulted from high tensile stresses introduced by welds which structurally attach and/or seal the nozzle to the vessel and the corrosive effect of the coolant within the vessel. Such cracking occurs at the grain boundaries on the inside diameter of the nozzle material (Alloy 600) at or near the heat affected zone of the weld and propagates radially outward through the thickness of the nozzle which eventually leads to small leakage of the reactor coolant supply. As indicated, nozzles of these types have failed over time and have had to be replaced, either because of a failure in the nozzle or the weld attaching and/or sealing the nozzle to the vessel. A typical replacement procedure in a nuclear power plant environment requires shutting down the nuclear power plant, removing the nozzle, which typically requires machining operations, and welding a replacement nozzle to the vessel or piping. The welded replacement nozzles currently in use closely duplicate the original welded nozzle they replace, except that they may be made of a different alloy, e.g., Alloy 690 (less susceptible to PWSCC) instead of Alloy 600, and may also be represented by the nozzle shown in FIG. 2. Other weld repair methods involve installing a thick weld pad on the outside of the vessel and structurally welding the nozzle to the pad, and seal welding the interior end of the nozzle to the vessel. Replacements employing the above-described procedures in a nuclear power plant currently require a minimum of approximately fourteen days for some types of nozzles and are extremely expensive. Including the lost revenue resulting from plant shut-down, which may be as high as $750,000 per day, the total cost of each repair is millions of dollars. The above-described nozzle replacement procedures and any other replacement procedure that requires welding the replacement nozzle to the vessel not only is time consuming and therefore expensive, but also exposes repair personnel to radiation hazards, particularly where the nozzle replacement method involves personnel entering inside the vessel to perform the replacement. Also, both the original welded nozzle and the welded replacement nozzle and method subject the nozzle to high residual stresses imposed by weld shrinkage. These high residual stresses increase the susceptibility to PWSCC. Thus, the welded replacement nozzle offers no improvement over the original nozzle in terms of expected life and reduction of failures, other than any improvement that may result from use of a superior nozzle material. Although, Alloy 690 material is less susceptible to PWSCC than Alloy 600, it is not known at this time whether the change in nozzle material alone will eliminate the possibility of nozzle failures. Furthermore, one utility that has replaced nozzles using the original design criteria and Alloy 690 material experienced failures in the weld material itself. Based on this information, an improved nozzle replacement method is needed. U.S. Pat. Nos. 5,149,490 and 5,202,082 (both of Brown et al.) describe methods and apparatus for replacing a nozzle for a pressurizer vessel in which the replacement nozzle is threaded to the bore. Although the replacement nozzle of the '490 patent is mechanically attached to the pressurizer vessel, according to the '490 patent, welding is still required to provide the seal between the nozzle and the pressurizer vessel. Therefore, the residual stresses discussed above are imposed on the nozzle by the weld whether it be a structural weld or a seal weld. In the replacement procedure and nozzle described in the '082 patent, the original welded nozzle is not fully removed, and a mechanical seal is made between the remaining cracked nozzle portion and the end of the replacement nozzle. Leaving part of the existing nozzle at the interior welded end of the nozzle may lead to a future failure because the existing failed portion of Alloy 600 nozzle which was not removed from the vessel has cracks near the existing J weld that may propagate out to the base material of the vessel and cause further cracking in the failed portion of the nozzle. Further cracking in the remaining portion of the failed nozzle would not likely result in reactor coolant leakage, and therefore might be justified for the life of the plant; however, a better design practice would be to remove the cracked nozzle to eliminate further degradation of the vessel. The procedure described in the '882 patent thus has the drawback that a portion of the failed nozzle remains structurally welded to the vessel and therefore continues to subject the vessel to the same stresses as the original nozzle. In any event, the remaining nozzle portion and the vessel portion surrounding the bore opening are subject to further degradation. As far as the applicant is aware, the nozzles and replacement procedures disclosed in the '490 and '882 patents have not been used in a nuclear power facility. The following U.S. patents disclose other procedures for replacing or repairing nozzles, sleeves or tubes which include welding: 4,255,840 (Loch et al.); 4,440,339 (Tamai et al.); 4,615,477 (Spada et al.); 5,091,140 (Dixon et al.); 5,094,801 (Dixon et al.); 5,196,160 (Porowski); 5,209,895 (Wivagg); 5,271,048 (Behake et al.); and 5,274,683 (Broda et al.). U.S. Pat. No. 4,826,217 (Guerrero) discloses a mechanical tube clamp for boiling water reactors. U.S. Pat. No. 5,278,878 (Porowski) discloses a method for reducing tensile stresses in the welded nozzles. Also a method previously used in steam generator tube repairs has been proposed with certain modifications to the Nuclear Regulatory Committee for repairing a leaking nozzle. According to the proposal, a sleeve is rolled into an existing nozzle and deformed against the ID of the existing nozzle such that a seal is created between the nozzle and vessel. A similar design was also proposed for a plug. However, the Nuclear Regulatory Committee declined the proposals because that rolling technique causes high tensile stresses at the rolled transition region which promotes PWSCC, and because that repair method was only leak limiting which could allow the boric acid in the reactor coolant to erode a portion of the carbon steel vessel. Nozzles are currently being replaced in pressurized water reactor (PWR) nuclear power facilities both because they have failed and as a preventive measure where a statistical analysis has indicated a high probability of a future failure. Nozzle failures and such statistically indicated failures have been occurring frequently enough to be a major concern for nuclear power plant operators (and owners) for a number of reasons including the high cost of repairs and the millions of dollars in lost revenue due to plant shut down. Therefore, there is a need for a replacement nozzle and a method for replacing nozzles that have failed or may fail in the future, that (a) reduce the time and expense required to make the replacement and (b) do not require confined entry into a pressure vessel, which reduce radiation exposure to the personnel performing the replacement, and (c) reduce the susceptibility to PWSCC and do not result in further degradation of the vessel, and accordingly reduce the risk of future failures. A similar need also exists for a nozzle for initial installation applications and a method of initially installing such a nozzle in a vessel. The invention disclosed herein addresses the above-described needs and avoids the problems discussed above, and provides nozzles and procedures for installing nozzles mechanically in pressure vessels in nuclear power facilities (and in other fields) that do not employ (a) a structural weld or a seal weld, and (b) any part of an existing nozzle which is being replaced. OBJECTS AND SUMMARY OF THE INVENTION It is an object of the invention disclosed herein to reduce the susceptibility to PWSCC of replacement nozzles and initial installation nozzles in nuclear power facilities as much as reasonably achievable, and thereby reduce the possibility of future nozzle failures. It is another object of the invention to reduce the time and expense involved with installing a replacement or initial installation nozzle in a vessel, particularly in a nuclear power facility. It is another object of the invention to not require confined entry into a vessel in order to install a replacement or initial installation nozzle in the vessel, particularly in a nuclear power facility. It is another object of the invention to reduce the exposure to radiation of repair personnel in a nuclear power facility while installing a replacement or initial installation nozzle in a vessel. It is another object of the invention to install a replacement or initial installation nozzle in a vessel without structurally welding the nozzle to the vessel, particularly in a nuclear power facility. It is another object of the invention to install a replacement or initial installation nozzle in a vessel without seal welding the nozzle to the vessel, particularly in a nuclear power facility. It is another object of the invention to install a replacement or initial installation nozzle in a vessel without structurally welding and without seal welding the nozzle to the vessel, particularly in a nuclear power facility. It is another object of the invention when replacing a nozzle in a vessel to remove the entire existing nozzle and to install a complete (whole) mechanical nozzle replacement, thereby removing the defective portion of the existing nozzle and avoiding further degradation to the vessel. It is another object of the invention to provide nozzles which may be installed in vessels while achieving the objects set forth above. The invention in achieving the above and other objects provides a full replacement or initial installation nozzle for vessels and a method for mechanically attaching the full nozzle to the vessel without any welding at all, i.e.,without using a structural or seal weld. The full nozzle is clamped or bolted to the vessel or attached to the vessel with an interference fit, and a seal is obtained using an interference fit between metal surfaces of the nozzle and the vessel (which may be polished), and/or by use of gasket materials. In the case of replacement, the entire existing nozzle is removed and the full nozzle is mechanically attached and mechanically sealed. The invention departs significantly from the prior art of nozzle replacement and initial installation by not utilizing a weld of any kind, which eliminates the stresses imposed by welding and significantly reduces the risk of a PWSCC type failure. The method for replacing a nozzle attached to and sealed against a vessel comprises removing the entire existing nozzle from the vessel, mechanically attaching the full replacement nozzle to the vessel with the replacement nozzle passing through the bore in the vessel from which the existing nozzle was removed, and mechanically sealing the replacement nozzle in or at the bore. Where a nozzle is initially installed (e.g., in a new vessel or as an additional nozzle on an existing vessel), a bore of the desired configuration is made in the vessel, and a new nozzle is installed generally as described for installing a replacement nozzle. In some embodiments of the invention, the existing bore is modified (e.g., configured to conform to the configuration of the nozzle). Depending upon the pressure to be encountered in the vessel, a mechanical seal is obtained by contacting the metal surfaces of the nozzle and the bore, which may or may not be polished, and/or by the use of gasket material. Polishing contacting metal to metal surfaces permits the surfaces to make intimate contact over a substantial area or areas thereof when forced together (e.g. in an interference fit or simply interfering parts forced together), and thereby create a seal of the contacting surfaces without in some applications requiring gasket material between the contacting surfaces. A gasket material employed for mechanically sealing the nozzle against the vessel may be a nickel alloy or other alloy plated or sprayed on the nozzle and/or possibly on the wall of the bore which upon compression forms a seal, or any suitable seal material which when positioned between two surfaces and compressed therebetween seals the two surfaces in the particular application of interest. As used herein, "positioning" or "placing" gasket material on or between the nozzle (and/or a flange thereof) and the vessel is meant to encompass plating or spraying the gasket material on a surface or surfaces of the nozzle and/or vessel as well as mechanically providing a material between two surfaces of the nozzle and vessel. As mentioned above, mechanically attaching the nozzle to the vessel may be accomplished by clamping, bolting or an interference fit of the replacement nozzle to the vessel. Some clamping embodiments comprise a nozzle which has a threaded portion projecting exteriorly of the vessel, means associated at least with the nozzle for engaging the vessel and preventing the nozzle from being withdrawn through the bore, and a nut threaded and tightened on the nozzle which bears against the exterior of the vessel and causes the engaging means to firmly engage the vessel. A spacer may be provided between the nut and the exterior of the vessel, in which case the nut bears against the exterior of the vessel through the spacer. The engaging means referred to above may comprise an interior flange attached to the nozzle surrounding the bore on the interior of the vessel, or interfering portions of the nozzle and the bore. Where the engaging means comprises interfering portions of the nozzle and bore, the nozzle and the bore may have circular cross sections, and a portion of the nozzle within the bore has a larger diameter than the largest diameter of the bore thereby providing the interfering portions. For example, the bore and nozzle may both be tapered. Gasket material is preferably positioned between the nozzle and the vessel to ensure a mechanical seal therebetween. In another clamping embodiment, the means for mechanically attaching the nozzle to the vessel comprises an exterior flange bolted to the vessel and means associated at least with the nozzle for engaging the vessel and preventing the nozzle from passing through the bore to the interior of the vessel. In still another clamping embodiment, the nozzle includes a separate sleeve and a nozzle body. The sleeve is externally threaded and the bore includes a threaded portion which receives the sleeve. The nozzle body and the bore are configured so that tightening the sleeve in the bore forces the nozzle body into engagement with the bore to clamp the nozzle body to the vessel. A mechanical seal is obtained from contacting metal surfaces of the nozzle body and the bore and/or gasket material as described above. Two specific embodiments of bolting the nozzle to the vessel include (1) threading the nozzle in the bore and (2) attaching an exterior flange (attached to or engaging the nozzle) to the vessel with bolts. In the first of those embodiments, the means for mechanically attaching the nozzle to the vessel comprises threads on a portion of the nozzle, a threaded portion of the bore, and means associated at least with the nozzle for engaging the vessel and preventing the nozzle from being withdrawn or pushed through the bore of the vessel. Where the engaging means comprises interfering portions of the nozzle and bore, the nozzle and the bore may have circular cross sections, and a portion of the nozzle within the bore has a larger diameter than the largest diameter of the bore thereby providing the interfering portions. For example, the bore and the nozzle may both be tapered. A tapered nozzle which is threaded in the vessel's bore may be inserted into the bore either from the interior or the exterior of the vessel depending upon the direction of the taper. In the clamping and bolting embodiments described herein, mechanically sealing the nozzle in or at the bore may comprise positioning gasket material between the nozzle (and/or a flange thereof) and the vessel and pressing that material against the vessel in the bore or at an end of the bore sufficiently to create a seal between the nozzle and the vessel, or mechanically attaching the nozzle to the vessel so as to force at least a part of the nozzle against the vessel to mechanically seal the nozzle to the vessel, or both. A mechanical seal may be obtained by pressing the flange against the vessel, or configuring the nozzle and bore to interfere and forcing the nozzle into engagement with the bore, e.g., by means of a tapered bore and nozzle as described above. Where a mechanical seal is created by forcing the nozzle against the vessel, to obtain a seal it may be necessary to machine polish the contacting surfaces as discussed above. However, it may be necessary to position gasket material between such contacting surfaces if high pressure and thermal transient conditions exist in the vessel. In such a case, the nozzle and vessel surfaces may not require polishing. For example, the gasket material may be positioned between the interior and exterior flanges referred to above and the interior and exterior, respectively, of the vessel, or along the tapered regions of the nozzle and bore. In another embodiment of mechanically sealing the nozzle to the vessel, the mechanically sealing means comprises at least one O-ring type gasket material between the nozzle and the interior of the bore. In yet another embodiment, a sleeve is mechanically attached in the bore by a shrink fit, rolling, etc., the nozzle is inserted into the sleeve, thereby providing a corrosion barrier for the vessel, and gasket material is positioned between a flange attached to the nozzle and the vessel. The bore, sleeve and nozzle may all be cylindrical or they may all be tapered. In one method of mechanically attaching the nozzle to the bore with an interference fit, the nozzle has a larger outer diameter than the inner diameter of the bore at a given temperature of the nozzle and the vessel adjacent the bore. A temperature gradient is provided between the vessel adjacent the bore and the nozzle sufficient to enlarge the diameter of the bore, reduce the diameter of the nozzle, or both to allow the nozzle to be inserted into the bore, and sufficient when the temperature gradient is substantially reduced to mechanically attach the nozzle in the bore in the temperature range of interest. After the nozzle has been inserted into the bore, the temperature gradient is reduced effective to produce the mechanical attachment. A nozzle attached as described above without an interior flange may be provided with an anti-ejection feature which prevents the nozzle from being ejected from the vessel should the mechanical attachment of the nozzle thereto fail. The anti-ejection feature may be embodied by at least one flange which is formed on the interior end of the nozzle and mechanically engages the interior of the vessel surrounding the opening to the bore. Inventive nozzles, and related attachment methods, have so far been described with respect to "vessels" in general, which term broadly encompasses piping. Specifically, all of the clamping, bolting and interference fit attachment embodiments described above are applicable to pressure vessels such as a pressurizer vessel or reactor vessel and to large bore piping. However, the invention also provides a method and apparatus specifically for attaching a nozzle to a large bore pipe in which the thickness of the pipe only allows minimum diameter changes in the bore or no installation of bolts in the pipe. A hole or bore through the circumference of the pipe is either made or an existing hole or bore in the pipe's circumference is used. A nozzle is provided having a first portion with a diameter therealong smaller than the diameter of the bore, a second portion with a diameter therealong larger than the diameter of the bore, and a flange therebetween. The nozzle portion with the smaller diameter is inserted into the bore with the flange bearing against the exterior circumference of the pipe. The flange is attached to the pipe with a suitable clamping device, and the exterior of the nozzle is mechanically sealed to the pipe. Sealing means for mechanically sealing the nozzle may comprise gasket material positioned between the flange and the outer circumference of the pipe and/or between the nozzle and the pipe which is compressed by the clamping device. The particular configurations of the smaller diameter portion of the nozzle and the ID of the bore may be conformed, for example as described above for certain vessel embodiments. Also, the mechanical sealing mechanism may be one described above for the vessel embodiments.
	claims	1. A flow management system for an extreme ultraviolet lithography apparatus, the system comprising:a first enclosing wall at least partially surrounding a first space;a system generating plasma in said first space, the plasma emitting extreme ultraviolet light;a second enclosing wall at least partially surrounding a second space;an elongated body at least partially surrounding a passageway and having a first open end allowing EUV light to enter the passageway from the first space and a second open end allowing EUV light to exit the passageway into the second space, the body having a shape establishing a location having a reduced cross-sectional area relative to the first and second ends, the passageway establishing fluid communication between said first and second spaces, said second space otherwise sealed from said first space; anda flow of gas exiting an aperture, the aperture positioned to introduce gas into the passageway at a position between the first end of the body and the location having a reduced cross-sectional area. 2. A system as recited in claim 1 further comprising a source for generating an electromagnetic field in said passageway to produce a plasma therein. 3. A system as recited in claim 2 further comprising a pair of electrodes for establishing an electric field in the second space to deflect charged particles. 4. A system as recited in claim 2 wherein said source comprises a radio-frequency coil for creating an inductively coupled discharge plasma in said passageway. 5. A system as recited in claim 2 wherein said source produces a direct current electrode discharge in said passageway. 6. A system as recited in claim 5 wherein said electrode discharge is a glow discharge. 7. A system as recited in claim 5 wherein said electrode discharge is a corona discharge. 8. A system as recited in claim 2 wherein said source produces a radio-frequency electrode discharge in said passageway. 9. A system as recited in claim 8 wherein said electrode discharge is a glow discharge. 10. A system as recited in claim 8 wherein said electrode discharge is a corona discharge. 11. A system as recited in claim 1 wherein the aperture comprises a hole formed in the elongated body. 12. A system as recited in claim 1 further comprising a temperature control system maintaining the temperature of the elongated body within a predetermined range. 13. A system as recited in claim 1 further comprising at least one vane disposed in the passageway of the elongated body. 14. A system as recited in claim 1 wherein the system comprises a plurality of apertures, each aperture positioned to introduce gas into the passageway at a respective position between the first end of the body and the location having reduced cross-sectional area. 15. A system as recited in claim 1 wherein the system comprises a nozzle directing flow from the aperture toward the first end of the elongated body. 16. An extreme ultraviolet lithography apparatus comprising:a first chamber having gas disposed therein;a second chamber having gas disposed therein;an intermediary chamber in fluid communication with the second chamber;an elongated body restricting flow from the first chamber to the intermediary chamber, the body at least partially surrounding a passageway and having a first open end allowing EUV light to enter the passageway and a second open end allowing EUV light to exit the passageway;a flow of gas exiting an aperture, the aperture positioned to introduce gas into the passageway at a location between the first end and the second end of the body; anda pump removing gas from the intermediary chamber. 17. An extreme ultraviolet lithography apparatus as recited in claim 16 wherein the pump cooperates with the flow of gas exiting the aperture and the operational pressures within the first and second chambers to establish a gas flow directed from the second chamber into the intermediary chamber and a gas flow from the aperture through the first open end of the elongated body and into the first chamber. 18. An apparatus comprising:a first enclosing structure surrounding a first volume;a system generating a plasma at a plasma site in the first volume, the plasma producing EUV radiation and ions exiting the plasma;an optic positioned in the first volume and distanced from the site by a distance, d;a gas disposed between the plasma site and optic, the gas establishing a gas number density sufficient to operate over the distance, d, to reduce ion energy below 100 eV before the ions reach the optic; anda second enclosing structure surrounding a second volume,a system coupling the second volume to the first volume to allow EUV radiation to pass from the first volume to the second volume and operable to establish a gas flow directed from the second volume into the system and a gas flow from the system into the first volume. 19. An apparatus as recited in claim 18 wherein a gas is disposed in the first volume at a pressure P1 and a gas is disposed in the second volume at a pressure P2, with P1>P2. 20. An apparatus as recited in claim 18 wherein the system comprises:an intermediary chamber in fluid communication with the second volume;an elongated body restricting flow from the first volume to the intermediary chamber, the body at least partially surrounding a passageway and having a first open end allowing EUV light to enter the passageway and a second open end allowing EUV light to exit the passageway;a flow of gas exiting an aperture, the aperture positioned to introduce gas into the passageway at a position between the first end and the second end of the body; anda pump removing gas from the intermediary chamber. 21. An apparatus as recited in claim 18 further comprising a multi-channel structure disposed in said first volume.
	abstract	A nuclear fuel according to one embodiment includes an assembly of nuclear fuel particles; and continuous open channels defined between at least some of the nuclear fuel particles, wherein the channels are characterized as allowing fission gasses produced in an interior of the assembly to escape from the interior of the assembly to an exterior thereof without causing significant swelling of the assembly. Additional embodiments, including methods, are also presented.
047568771	summary	FIELD OF THE INVENTION The present invention relates to a core barrel support system for a nuclear reactor, such as a pressurized water reactor, wherein the core support plate is engaged about the periphery thereof, and a method for installation of a core barrel in a pressure vessel of a reactor where alignment and securement of the core barrel are readily achieved. DESCRIPTION OF THE PRIOR ART In nuclear reactors, such as pressurized water reactors, the reactor has an upright cylindrical pressure vessel with a hemispherical lower head section and a removable hemispherical head bolted to the upper end of the vessel. A cylindrical core barrel is suspended inside the pressure vessel from a flange extending around the inside of the upper end of the pressure vessel. The barrel includes a bottom core support plate and is positioned within the pressure vessel spaced from the lower head section a substantial distance therefrom. The upper region of the core barrel contains reactor control rod guide tubes, while the core internals, such as the fuel element assemblies, the fuel element assemblies support grid structure, and the like are contained in the lower region of the core barrel. As described in the application of R. M. Blaushild and L. Veronesi, Ser. No. 547,294, filed Oct. 28, 1983, and assigned to the assignee of the present invention, the contents of which application are incorporated by reference herein, while the core barrel is primarily supported at its upper end by engagement with the upper end of the pressure vessel, the lower end of the core barrel is also restrained by engagement means so as to provide lateral stability thereof. As described therein, a preferred means for such lateral stability and auxiliary support is the provision of a plurality of engagement means which are secured to the lower end of the pressure vessel and extend radially inwardly from the upper portion of the walls of the hemispherical lower head section. Each of the engagement means have a recess in the upper surface thereof and keys, such as T-shaped keys are secured to the bottom of the core support plate, which keys are designed to fit into the recesses in the engagement means for lateral stability and to align the core barrel within the reactor vessel. In the conventional assembly of the core barrel within the reactor vessel, the engagement means with recesses are generally welded to the bottom portion of the pressure vessel and keys are bolted and/or welded to the bottom surface of the core support plate. A very precise alignment is required, between the keys and walls of the recesses or keyways, upon assembly of the core barrel into the pressure vessel. Because of the degree of precise alignment required, the core support plate is provided with a manway or access port, usually through the center of the core support plate, with a cover plate therefor, so that an assembler can be lowered through the manway into the area between the core support plate and the bottom wall of the pressure vessel. The assembler, while in that area, can then make measurements to determine the type and number of shims that are needed to be manufactured and then inserted into the keyways to provide the required alignment. At times, the needed shims can be inserted into the recesses only after removal of the core barrel from the pressure vessel, with the shims then placed into the recesses and the core barrel re-inserted into the pressure vessel. This system of alignment is expensive and time consuming and is possible only when the size of the reactor is such that an assembler can be physically lowered through the manway into the area between the core support plate and the bottom wall of the pressure vessel. In small reactors, for example, the pressure vessel may be of a size so small that an assembler cannot be physically located in the area between the core support plate and the bottom wall of the pressure vessel to perform the alignment operations above-described. It is an object of the present invention to provide a nuclear reactor which has an improved system for aligning the core barrel relative to engagement means for the core support plate. It is another object of the present invention to provide an improved method for aligning a core barrel of a nuclear reactor in a pressure vessel. BRIEF SUMMARY OF THE INVENTION An improved means for aligning and securing a core barrel within a pressure vessel of a nuclear reactor relative to engagement means disposed about the periphery of the core barrel and attached to the wall of the pressure vessel, wherein the core support plate has a plurality of apertures therethrough which communicate with recesses in the engagement means, and a key is inserted into the apertures, the lower section of which extends into the recess of the engagement means, the key being secured in said apertures of the core support plate. The keys preferably have an upper flanged portion which fits on a shoulder in the core support plate about the aperture, such that the key is secured in place with its upper surface flush with the upper surface of the core support plate and with the flange secured to the core support plate by welding or by bolted connections.
	summary

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