Abstract: A tool to slide a channel on a nuclear reactor fuel bundle assembly, the tool includes: a plate having a slot to receive a handle of the fuel bundle and a lower surface that engages an upper edge of the channel; at least one post extends up from the plate, and an arm is attached to a pivot on the post and includes a first end to receive a downward force and a second end adapted to engage the handle of the fuel bundle to apply an upward force to the handle and push down on the channel.

Abstract: A plurality of capsules are made available, each for receiving a fuel rod, and each comprising a tubular sheath that is closed at its ends by plugs. A loading structure is placed in a pool to receive at least one capsule with its axis vertical. A device for loading fuel rods into the capsule is secured onto an open top end of the structure. Defective rods are taken one by one and inserted one by one into empty capsules in the loading structure. For each capsule that is to receive a defective rod, a top plug of the capsule is unscrewed, a defective rod is inserted into the capsule through a guide device of the loading device, the top plug is screwed back onto the capsule, and the capsule containing the rod is put into a location in the support structure.

Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

Abstract: A method of aligning a nuclear fuel bundle and handling selected fuel rods within the fuel bundle located in a spent fuel pool of a nuclear power plant. The bundle includes water rods, full-length and part-length fuel rods extending through a plurality of fuel spacers provided between top and bottom ends of the bundle, each spacer having a plurality of cells accommodating corresponding fuel and water rods. The method includes insertion of a rod grapple tool into a top end of a fuel bundle and down to a desired location within the bundle. A guide pin retrieval tool inserts into a side of the fuel bundle to remove a guide pin from a distal end of a gripper of the rod grapple tool, allowing the guide pin retrieval tool to grip a part-length fuel rod within the fuel bundle.

Abstract: The nuclear reactor comprises a lower stopper sealingly fixed to a lower end of a tubular casing of the pencil that comprises a part which is internal to the casing successively comprising a first cylindrical section having a diameter which is substantially equal to the inner diameter of the tubular casing; a second cylindrical section whose diameter is smaller than the inner diameter of the tubular casing and a third cylindrical section whose inner diameter is smaller than the inner diameter of the tubular casing and greater than the diameter of the second cylindrical section such that 1-2 tenths of a millimetre radial play is created in the gas passable between the outer surface of the third section and the inner surface of the casing.

Abstract: A system, apparatus and method of processing and/or removing radioactive materials from a body of water that utilizes the buoyancy of the water itself to minimize the load experienced by a crane and/or other lifting equipment. In one aspect, the invention is a method comprising: a) submerging a container having a top, a bottom, and a cavity in a body of water having a surface level, the cavity filling with water; b) positioning radioactive material within the cavity of the submerged container; c) raising the submerged container until the top of the containment apparatus is above the surface level of the body of water while a major portion of the container remains below the surface level of the body of water; and d) removing bulk water from the cavity while the top of the container remains above the surface level of the body of water and a portion of the container remains submerged.

Abstract: In a spent fuel pool of a nuclear power plant, there is provided a system for aligning a nuclear fuel bundle and handling selected fuel rods within the fuel bundle. The bundle includes water rods, full-length and part-length fuel rods extending through a plurality of fuel spacers provided between top and bottom ends of the bundle, each spacer having a plurality of cells accommodating corresponding fuel and water rods. The system includes a bundle alignment system for aligning the fuel rods and water rods, a rod grapple tool to extract selected part-length rods from the bundle, and a fuel rod guide block slidable onto the top end of the bundle for protecting an uppermost fuel spacer of the bundle, and for aligning fuel rods within individual cells of all the fuel spacers in the fuel bundle.

Abstract: A lifting tool is used for lifting a channel on and off of a nuclear fuel bundle. The lifting tool includes a lifting bail and a leg assembly secured to the lifting bail. The leg assembly has an adjustable width, adjustable between a narrower pre-lifting position and a wider lifting position. The lifting legs are engageable with the channel clips in the lifting position.

Abstract: The invention relates to a monitoring device (20) of the position of an assembly containing nuclear fuel (4) in a housing of a storage basket (2). According to the invention, it comprises at least one mobile stop device (24, 26, 28) and a position indicator (30) suitable for being held at a stop by the mobile stop device in a first position indicating that the assembly occupies a first position, said mobile stop device being arranged so as to be able to be placed, by means of contact with the assembly located in a second position in its housing, in a position enabling it to release the position indicator devised to move automatically from the first position to a second position indicating that the assembly occupies the second position.

Abstract: Disclosed embodiments include nuclear fission reactor cores, nuclear fission reactors, methods of operating a nuclear fission reactor, and methods of managing excess reactivity in a nuclear fission reactor.

Abstract: A tool to slide a channel on a nuclear reactor fuel bundle assembly, the tool includes: a plate having a slot to receive a handle of the fuel bundle and a lower surface that engages an upper edge of the channel; at least one post extends up from the plate, and an arm is attached to a pivot on the post and includes a first end to receive a downward force and a second end adapted to engage the handle of the fuel bundle to apply an upward force to the handle and push down on the channel.

Abstract: A method of repairing a nuclear fuel cell wall and tools useful for performing that repair are described. A repair tool may be used to align a jack near a region of a bent or distorted structural component of nuclear fuel cell and that jack may be used to apply a force to that structural component. Application of such a force may serve to bend the structural component of a nuclear fuel cell in a way to restore the structural component to its position before damage occurred. The repair tool includes a way of mounting that tool to a fuel cell, positioning elements to align the tool near a structural deformation or bent element and a jack that may be use to apply a force to at least one structural component in a fuel cell.

Abstract: The present invention relates to a fuel rod of a nuclear fuel assembly having a vase-like compression spring adapted to increase the internal volume thereof wherein when the vase-like compression spring is inserted into a cladding tube, it has a relatively smaller volume occupied inside the fuel rod when compared with the existing coil type compression spring, such that the vase-like compression spring can ensure a sufficient space portion receiving the fission gases generated during the operation of the fuel rod, thereby increasing the burn-up performance of the fuel rod and the mechanical integrity thereof.

Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

Abstract: Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include assemblies for retention and producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more retention assemblies that contain one or more irradiation targets and are useable with example delivery systems that permit delivery of irradiation targets. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while containing irradiation targets and desired isotopes produced therefrom.

Abstract: A fast reactor including a reactivity control assembly including a reactor shutdown rod and neutron absorbers, a reactor shutdown rod drive mechanism, and units of neutron absorber drive mechanism. The reactor shutdown rod drive mechanism causes an inner extension tube to fall and release the reactor shutdown rod by a gripper section by turning off the power supply to a holding magnet at the time of scram. When grasping the neutron absorbers, an outer extension shaft is pulled up to allow both of the extension shafts to be inserted. After the outer extension tube gets to a handling head section of the neutron absorber, the outer extension shaft is pushed down to grasp the neutron absorber externally by latch fingers of the gripper section so that the neutron absorber can be moved up and down.

Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

Abstract: A tool to slide a channel on a nuclear reactor fuel bundle assembly, the tool includes: a plate having a slot to receive a handle of the fuel bundle and a lower surface that engages an upper edge of the channel; at least one post extends up from the plate, and an arm is attached to a pivot on the post and includes a first end to receive a downward force and a second end adapted to engage the handle of the fuel bundle to apply an upward force to the handle and push down on the channel.

Abstract: A fuel transfer system is used for transporting spent fuel from a first room to a second room. The system includes a carriage configured for travel between the first room and the second room, and a boom assembly that extends and retracts between the first room and the second room, wherein the boom assembly facilitates travel of the carriage. The system also includes a hoist system positioned in the first room. The hoist system includes at least one boom cable interconnected with the boom assembly to extend and retract the boom assembly. The hoist system also includes at least one carriage cable interconnected with the carriage to move the carriage.

Abstract: A nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same. The fuel assembly comprises an enclosure adapted to enclose a porous nuclear fuel body having the volatile fission product therein. A fluid control subassembly is coupled to the enclosure and adapted to control removal of at least a portion of the volatile fission product from the porous nuclear fuel body. In addition, the fluid control subassembly is capable of circulating a heat removal fluid through the porous nuclear fuel body in order to remove heat generated by the nuclear fuel body.

Abstract: A method for applying a burnable poison onto the cladding of a nuclear fuel rod (2) which comprises, providing a nuclear fuel rod (2) and at least one application device (8), rotating the nuclear fuel rod, optionally removing one or more oxides and/or surface deposits on the outer surface of the nuclear fuel rod (2) by spraying an abrasive material onto the nuclear fuel rod via the application device (8) while adjusting the position of the application device in relation to the nuclear fuel rod (2), and applying burnable poison particles (33) onto the outer surface (6) of the nuclear fuel rod (2) by spraying the burnable poison onto the nuclear fuel rod via the application device while adjusting the position of the application device (8) in relation to the nuclear fuel rod, where the burnable poison particles are applied at a velocity sufficient to cause adhesion to the outer surface (6) of the cladding.

Abstract: 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 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.

Abstract: A method of loading nuclear fuel assemblies into a fuel rack in an underwater (or other submerged) environment that reduces the depth required for the pool to effectuate the fuel rack loading procedure. In one embodiment, the method comprises submerging a nuclear fuel assembly having an axis and a horizontal cross-section in a pool; providing a fuel rack in the pool, the fuel rack comprising a body structure comprising at least one elongated cell, a top, a bottom, a first lateral side, at least one elongated slot in the first lateral side that forms a lateral passageway into the cell; positioning the fuel assembly laterally adjacent to the elongated slot of the fuel rack so that the axis of the fuel assembly is substantially aligned with the elongated slot; and translating the fuel assembly in a lateral direction through the elongated slot and into the cell.

Abstract: Disclosed are a replaceable fusion core that can be inserted and removed from the core of a nuclear fission reactor, thereby enabling the replacement of materials exposed to neutron flux and reducing outage times and “hybrid reactor, method, and device for improved nuclear fusion reactors to provide sufficient flux of fast neutrons with sufficient energy to transmutate transuranic wastes from nuclear fission and to be used in improved nuclear fuel cycles so as to effectively reduce the amount radio-toxicity, and the risks and costs of the disposal of nuclear waste, thereby reducing the cost of nuclear energy and increasing its acceptability as an energy source. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

Abstract: The core of a pressurized water reactor is assembled in such a way that if the fuel elements on the edge of the core are bent, these fuel elements are oriented such that the bending of the fuel elements points outwards in a convex manner. When the reactor is in operation, forces arise which increase the size of small gaps between the fuel elements at the expense of greater gaps and counteract the bending effect of the fuel elements.

Abstract: A tie rod for reinforcing a nuclear fuel assembly. The tie rod includes an outer, hollow tubular member that extends from above the top nozzle through the bottom nozzle of the fuel assembly and has an axially split lower tip with an enlarged end and an upper portion having a circumferential threaded region. An inner rod extends axially through the hollow of the outer tube and has a slightly enlarged tip which spreads the split tip of the outer tube to lock the split tip below the lower nozzle of the fuel assembly. A nut is turned down on the upper threaded portion of the outer hollow tube and staked in position to lock the tie rod in position.

Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

Abstract: A method to insert nuclear fuel pellets into a fuel rod cladding tube, having the steps of providing a cladding tube, providing at least one nuclear fuel pellet to be incorporated into the cladding tube, measuring a length of the at least one nuclear fuel pellet with a camera, comparing the length of the at least one nuclear fuel pellet to an expected length, and incorporating the at least one nuclear fuel pellet into the cladding tube when the compared length of the at least one nuclear fuel pellet is within a threshold value of the expected length.

Abstract: The geometric dimensions and shape of a device for removing solid particles from the cooling medium that is circulated in the primary circuit of a nuclear reactor, in particular a boiling water nuclear reactor, are such that the device can be inserted in lieu of a fuel element or fuel assembly into an empty fuel element or assembly position of the reactor core of the nuclear reactor.

Abstract: To permit the particularly safe, easy handling of fuel elements, the fuel element loading machine with a lifting apparatus has a guide mast and a fuel element gripper which can be extended telescopically from the guide mast. A video camera is for this purpose arranged on the lifting apparatus, is connected on the data side to a control station and has its viewing direction pointed downwards.

Abstract: A two-part integrated head assembly (100) is disclosed wherein the lower portion (110) attaches to, and is supported by, the reactor vessel closure head (90), and the upper portion (160) is fluidly connected to the lower portion, but is supported externally from the reactor vessel closure head. In the disclosed embodiment, the upper portion includes transverse support beams (170) that engage containment walls (92), for example steam generator walls, to support the upper portion. A duct (150) releasably connects a fan plenum (165) in the upper portion with an annular plenum in the lower portion, such that fans (166) can draw heated air from around the CEDMs (95). In one embodiment, a chiller (168) is provided in the fan plenum to cool the air prior to expelling it in containment. A missile shield (169) is also provided in the upper portion.

Abstract: A method and device to repair nuclear fuel assembly structural defects in the top nozzle to guide thimble connection, wherein the device includes a repair sleeve comprising tendons configured to deflect to allow establishment of a structural connection between a projection on each tendon and a dimple area of a guide thimble.

Abstract: A method to load a nuclear fuel rod, comprising, providing nuclear fuel pellets in a fuel plate transfer unit; transferring the nuclear fuel pellets from the fuel plate transfer unit to a fuel pellet column through the use of a belt, indexing the nuclear fuel pellets in the fuel pellet column to a nuclear fuel pellet loading machine; and pushing the fuel pellet column into a fuel rod cladding.

Abstract: The invention relates to a method and device for production of non-contaminated rods from MOX tablets in columns, within a confinement chamber divided into compartments, by means of a centering and aligning element for the tablets and a long pushrod with a sensitive drive.

Abstract: Illustrative embodiments provide nuclear fission igniters for nuclear fission reactors and methods for their operation. Illustrative embodiments and aspects include, without limitation, a nuclear fission igniter configured to ignite a nuclear fission deflagration wave in nuclear fission fuel material, a nuclear fission deflagration wave reactor with a nuclear fission igniter, a method of igniting a nuclear fission deflagration wave, and the like.

Abstract: Illustrative embodiments provide nuclear fission igniters for nuclear fission reactors and methods for their operation. Illustrative embodiments and aspects include, without limitation, a nuclear fission igniter configured to ignite a nuclear fission deflagration wave in nuclear fission fuel material, a nuclear fission deflagration wave reactor with a nuclear fission igniter, a method of igniting a nuclear fission deflagration wave, and the like.

Abstract: A method of producing a cladding tube for nuclear fuel for a nuclear pressure water reactor includes forming a tube which at least principally consists of a cylindrical tube component of a zirconium-based alloy, where the alloying element, except for zirconium, which has the highest content in the alloy is niobium, wherein the niobium content in weight percent is between about 0.5 and about 2.4 and wherein no alloying element, except for zirconium and niobum, in the alloy, has a content which exceeds about 0.2 weight percent. The cladding tube is then annealed such that the tube component is partly but not completely recrystallized. The degree of recrystallization in the tube component is higher than about 40% and lower than about 95%. A fuel assembly for a nuclear pressure water reactor also has a plurality of such cladding tubes.

Abstract: A method of fuel bundle consideration in a reactor. The method includes creating or editing bundle groups including fuel bundles.

Abstract: A method for applying a burnable poison onto the cladding of a nuclear fuel rod (2) which comprises, providing a nuclear fuel rod (2) and at least one application device (8), rotating the nuclear fuel rod, optionally removing one or more oxides and/or surface deposits on the outer surface of the nuclear fuel rod (2) by spraying an abrasive material onto the nuclear fuel rod via the application device (8) while adjusting the position of the application device in relation to the nuclear fuel rod (2), and applying burnable poison particles (33) onto the outer surface (6) of the nuclear fuel rod (2) by spraying the burnable poison onto the nuclear fuel rod via the application device while adjusting the position of the application device (8) in relation to the nuclear fuel rod, where the burnable poison particles are applied at a velocity sufficient to cause adhesion to the outer surface (6) of the cladding.

Abstract: A device and method to move a fuel assembly of a nuclear reactor, wherein the device eliminates the potential for dropping the fuel assembly due to stress corrosion cracking of the upper guide thimble sleeves that attach the top nozzle to guide thimbles.

Abstract: An aligning device for fuel elements allows fuel elements of a pressurized water reactor to be aligned in a comparatively easy and quick manner. To this end, the aligning device for fuel elements includes an aligning body, which extends in a longitudinal direction and whose lateral faces formed from side metal sheets can be displaced out of a position of rest in a direction that is perpendicular to the longitudinal direction. The cross-sectional dimensions of the lateral faces of the aligning body in the position of rest are selected so that they are less than the corresponding cross-sectional dimension of a reference fuel element by a predetermined nominal value.

Abstract: The invention relates to a method and a device for loading a fuel assembly into the core of a nuclear reactor. The inventive method consists in: inserting a dummy assembly (4) into the loading location (3) of the fuel assembly (5), said dummy assembly essentially having the same shape and dimensions as the loading location (3) and comprising smooth side walls; fixing the position of at least one fuel assembly (5) that is adjacent to the loading location (3), in the presence of the aforementioned dummy assembly (4), in relation to at least one second assembly (5) of the core, using at least one fuel assembly support tool (11); removing the dummy assembly (4) from the loading location (3); introducing the fuel assembly (5) which is being loaded into the loading location (3); and removing the fuel assembly support tool(s) (11).

Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

Abstract: A fuel assembly for a light water reactor contains a fuel rod cluster and a spacer that has a number of cells, bounded by webs for laterally holding fuel rods. A damaged region including at least one damaged cell is present in an edge region of a spacer. There being fastened above or below the damaged region on the spacer with the aid of at least one connecting part is a replacement assembly that contains at least a number of cells that corresponds to the number of the damaged cells, at least a portion of the cells being traversed by fuel rods. A method for repairing the light water reactor fuel assembly in the case of which fixed above or below the damaged region on the spacer is a replacement assembly that takes over the holding function at least of one defective cell.

Abstract: A method and device for blocking a fuel assembly in a housing of a transport basket. An attachment system is placed between an upper end piece of a fresh fuel assembly that it is to be transported and the open end of a housing in which the assembly is placed, to make a rigid connection between them. The attachment system holds the lower end piece of the assembly far from the bottom of the housing and puts the upper end piece in contact laterally with the corner of the housing designed to face downwards during subsequent transport of the assembly in the horizontal position. Furthermore, the lower end piece of the assembly is maintained laterally by a part of the housing with a smaller section.

Abstract: A device and method to move a fuel assembly of a nuclear reactor, wherein the device eliminates the potential for dropping the fuel assembly due to stress corrosion cracking of the upper guide thimble sleeves that attach the top nozzle to guide thimbles.

Abstract: A method is for establishing a nuclear reactor core loading pattern (LP) for fuel assemblies and burnable absorbers (BAs). The method establishes an optimum LP through the steps of: a) providing nuclear data representing fuel assemblies and BAs in a nuclear reactor core; b) depleting the nuclear data to form a reference core depletion; c) incorporating the nuclear data into a system of linear equations of a nuclear design quality flux solution method; d) defining the system of linear equations to include constraints which accurately represent the neutron physics of the reactor; employing the equations as a constraint matrix for a MIP solver to find an optimum core pattern solution; f) repeating steps b) through e) updating the constraints and objective functions to satisfy specified engineering requirements and establish an optimum core loading pattern. An algorithm for deriving the system of equations is also disclosed.

Abstract: A method for controlling a robot wherein a procedure is carried out with the robot while maintaining the robot immobile in axes that are not required to carry out the procedure.

Abstract: A method for providing a nuclear fuel includes forming a uranium-molybdenum alloy that provides an enhanced reactivity in research, test and radioisotope production nuclear reactors. In this uranium-molybdenum alloy, the uranium is enriched in the isotope 235-U, while the molybdenum is depleted in the isotope 95-Mo. The thus obtained enhanced reactivity can have at least two advantages, depending on the exact use of the fuel element: a requirement for less uranium in the fuel and the use of the fuel elements during a longer period in the reactor.

Abstract: A process and product produced thereby which involves subjecting an egg white product to turbulent flow at an elevated temperature not to exceed 162.degree. F. for a period of time not to exceed one minute followed by immediate rapid cooling to a temperature of from 25.degree. F. to 40.degree. F. to improve refrigerated shelf life. The chilled product is then filled and sealed in sterilized containers under aseptic or near sterile conditions. The refrigerated shelf life may be enhanced by freezing the packaged product for a finite period of time prior to placing it in refrigerated storage.