Abstract: An exemplary embodiment of the present invention provides an apparatus for dismantling for heavy water reactor facilities, including: a cutting device configured to divide a calandria of the heavy water reactor facilities into a main shell and a sub-shell; and a transfer device configured to draw the main shell cut by the cutting device to the outside, wherein the transfer device includes a fixing unit configured to fix the calandria; and a transfer unit configured to transfer the fixing unit.

Abstract: A system for manufacturing radionuclide generators includes an enclosure defining a radioactive environment. The enclosure includes radiation shielding to prevent radiation within the radioactive environment from moving to an exterior of the enclosure. The system also includes a conveyance system having a forward track and first carriages positioned on and movable along the forward track for conveying racks in a first direction. The conveyance system also includes a first walking beam mechanism magnetically coupled to the first carriages to move the first carriages. The conveyance system further includes a return track and second carriages positioned on and movable along the return track for conveying racks in a second direction opposite the first direction. The forward track and the return track form a loop.

Abstract: In one embodiment, a system and method for dry storage comprises removing spent fuel rods from their fuel rod assemblies and placing the freed fuel rods in a storage cell of a dry storage canister with a high packing density and without a neutron absorber material present.

Abstract: A method for loading fuel pellets for manufacturing a nuclear fuel rod is provided. The method includes arranging fuel pellets in a row on a tray, aligning the fuel pellets in the row on the tray such that the fuel pellets are closely in contact with one another, obtaining a total length of the pellets in the row by measuring the fuel pellets in the row on the tray, and comparing the total length with a predetermined length. When the total length is smaller than the predetermined length by a difference greater than an average unit length of the pellet, one or more fuel pellets are added in the row until to increase the total length until the difference becomes smaller than the average unit length of the fuel pellet.

Abstract: In one embodiment, a system and method for dry storage comprises removing spent fuel rods from their fuel rod assemblies and placing the freed fuel rods in a storage cell of a dry storage canister with a high packing density and without a neutron absorber material present.

Abstract: A method of reducing the volume of a blade section of a boiling water reactor control rod for transport or storage that cuts the control rod spline into four substantially equal longitudinal sections, with each longitudinal section including one control rod blade. Each longitudinal section is radiologically characterized and the locations of desired lateral segmentation are identified. A band of malleable metal is wrapped around each longitudinal section at each of the locations and the bands are sheared to separate segments of the longitudinal section and the ends of the bands are crimped at the point of shearing to seal the interior of the segments.

Abstract: A reactor installation tool and method for installing a reactor unit in a reactor tube. A reactor installation tool including a movable assembly and a fixed assembly linked together such that the movable assembly can be adjusted relative to the fixed assembly. The movable assembly including a reactor sleeve attachment means for releasably securing a reactor sleeve loaded with a reactor unit to the tool. The fixed assembly including an expandable clamping unit for releasably securing the tool to a reactor tube. A reactor unit can be installed in the reactor tube by adjusting the movable assembly to extract the reactor unit from the reactor sleeve as the fixed assembly is rigidly secured to the reactor tube. The fixed assembly can be released from the reactor tube and the reactor installation tool can be removed from the reactor tube.

Abstract: A jet pump diffuser weld repair device includes a lower ring section and an upper ring section respectively sized to fit around a circumference of the diffuser on opposite sides of the weld to be repaired. The lower and upper ring sections are provided with a plurality of aligned gripper slots. A corresponding plurality of grippers are fit into the gripper slots, where at least one of the gripper slots and the grippers defines cam surfaces shaped to drive the grippers radially inward as lower and upper ring sections are drawn toward each other. A plurality of connector bolts are secured between the lower ring section and the upper ring section. Tightening of the connector bolts draws the lower and upper ring sections toward each other.

Abstract: A pressure-loss adjusting-member installation tool having pressure-loss adjusting-member grippers that are configured to freely grip or release a pressure-loss adjusting member which is arranged at a position between a lower nozzle arranged at one end of a fuel assembly having a relatively small pressure-loss when a primary coolant flows and a lower core support plate, and which can cause the primary coolant to pass therethrough in a state with a pressure-loss being increased more than that of when the primary coolant passes through only core support plate flow holes formed on the lower core support plate; and a holding unit that holds the pressure-loss adjusting-member grippers in a same positional relationship as a relative positional relationship between the fuel assemblies arranged in plural on the lower core support plate.

Abstract: An apparatus for removing a dry tube assembly includes a mounting structure configured to mount the apparatus to a top guide of a reactor vessel, a clamping assembly configured to engage the dry tube assembly, and a positioning assembly that is configured to position and rotate the clamping assembly relative to the dry tube assembly. The dry tube assembly is buckled and removed without exercising a joint.

Abstract: A tool for use in servicing an LPRM assembly of a nuclear reactor vessel includes a structural member having a first bore that is structured to receive an LPRM device associated with the LPRM assembly, a headpiece provided at a first end of the structural member, and a nut engaging assembly slideably mounted on the structural member. The headpiece has a plurality of projections structured to mate with a plurality of bores provided in a seal of the LPRM assembly to enable the seal to be removed, and the nut engaging assembly has a housing that defines a second bore and that has first and second nut engaging portions. The nut engaging assembly is free to slide along the structural member and over the headpiece to a position wherein the engaging portions extend beyond the headpiece so that they may be used to remove the assembly nut.

Abstract: A reactor installation tool and method for installing a reactor unit in a reactor tube. A reactor installation tool including a movable assembly and a fixed assembly linked together such that the movable assembly can be adjusted relative to the fixed assembly. The movable assembly including a reactor sleeve attachment means for releasably securing a reactor sleeve loaded with a reactor unit to the tool. The fixed assembly including an expandable clamping unit for releasably securing the tool to a reactor tube. A reactor unit can be installed in the reactor tube by adjusting the movable assembly to extract the reactor unit from the reactor sleeve as the fixed assembly is rigidly secured to the reactor tube. The fixed assembly can be released from the reactor tube and the reactor installation tool can be removed from the reactor tube.

Abstract: The inventive tool is designed to ensure proper plant operation position of the core shroud head bolt assemblies of a boiling water nuclear reactor. The tool exerts an upward pulling force on stuck retainers to return them to the locking position around the nut. The tool includes a frame, an engagement member, and a collar. The engagement member is lowered toward and end of the bolt until it comes into contact therewith. Further movement of the engagement member causes the frame and collar to move upward, lifting the retainer and extending the spring.

Abstract: A device is provided for repairing a damaged location in an underwater region of a wall of a vessel or pool, in particular in the region of a wall of a pool of a nuclear reactor plant. The device includes a guiding system, which can be attached along a side wall at a distance therefrom and can be fixed thereto, for guiding a carriage which can be made to move in a longitudinal direction of the guiding system. Arranged on the carriage is a displaceably mounted holder for a repair support, which can be placed with an adhesive surface against the wall region containing the damaged location. With such a device, wall regions that are at a great depth and can only be accessed through narrow gaps can be repaired quickly and reliably.

Abstract: A method of manufacturing an optimized sheet metal (1) of a zirconium based alloy is described, which optimized sheet metal (1) defines a sheet plane (BA). The method comprises the steps of providing a sheet metal (2) of a zirconium based. alloy, subjecting the sheet metal (2) to at least a preparing cold rolling and a final cold rolling, wherein the preparing cold rolling and the final cold rolling are both performed in a common rolling direction, and heat treating the sheet metal (1) between the preparing cold rolling and the final cold rolling so that the zirconium based alloy is partially re-crystallized. A method of manufacturing a spacer grid using an optimized sheet metal (1) according to the invention is also described.

Abstract: An assembly adapted to access a weld extending circumferentially around a core shroud of a nuclear reactor, wherein the core shroud is contained in a pressure vessel reactor, the assembly including: a baffle plate rail having a lower surface adapted to abut a baffle plate in a gap between the core shroud and the pressure vessel reactor; a telescoping rail slidably coupled to an upper region of the baffle plate rail, and a reciprocating rail slidably coupled to an upper region of the telescoping rail, wherein the reciprocating rail includes at least one of a weld conditioning tool, a weld inspection sensor and a weld repair device.

Abstract: A joint tong apparatus for a radiation shielding facility. A spherical ball has a through-hole. An inner spherical socket and an outer spherical socket are installed in a hole formed in a partition between a radiation-shielded room and a control room so as to enclose the spherical ball on inner and outer sides. A bar is inserted and coupled into and to the through-hole of the spherical ball. An inner joint assembly has a first housing coupled to a shielded room-side end of the bar and a first pivot member pivotably mounted on a free end of the first housing. An outer joint assembly having a second housing coupled to a control room-side end of the bar and a second pivot member pivotably mounted on a free end of the second housing. The apparatus further includes a tong assembly, a handle assembly, a tong manipulation cable, and a pair of pivot manipulation cables.

Abstract: An F-18 production target system having an internal support produces F-18 by means of a nuclear reaction of protons and H218O, and reduces the deformation of thin sheets to thus increase the durability of the thin sheets. The F-18 production target system includes a frame, which has the shape of a cylinder the central portion of which is bored, holds H218O in the central portion, and includes through-holes bored from the central portion to the outer circumference thereof, thin sheets, which are installed on opposite sides of the frame so as to seal the central portion, and a support, which is installed in the central portion so as to prevent the thin sheets from being deformed.

Abstract: A tool for use in servicing an LPRM assembly of a nuclear reactor vessel includes a structural member having a first bore that is structured to receive an LPRM device associated with the LPRM assembly, a headpiece provided at a first end of the structural member, and a nut engaging assembly slideably mounted on the structural member. The headpiece has a plurality of projections structured to mate with a plurality of bores provided in a seal of the LPRM assembly to enable the seal to be removed, and the nut engaging assembly has a housing that defines a second bore and that has first and second nut engaging portions. The nut engaging assembly is free to slide along the structural member and over the headpiece to a position wherein the engaging portions extend beyond the headpiece so that they may be used to remove the assembly nut.

Abstract: A method for production of spacers to hold at least a number of elongated fuel rods (5) in a fuel unit (20) for placement in a re-actor (1) is described. The method comprises the steps of providing at least two spacers (30), to provide a set of mandrels (40) comprising a number of mandrels (42), to arrange at least two spacers (30) with one on top of the other on the set of mandrels (40), and to heat treat the spacers (30) when they are arranged on the set of mandrels (40) so that the cells (31) in the spacers (30) adapts to the mandrels (42).

Abstract: The invention concerns a method for repairing guide rails (27) of an assembly (10) radially maintaining a core supporting plate (5), which consists in measuring the spacing between the spans of the lateral branches of the guide rail (27) to be repaired, cutting and removing at least one lateral branch of said guide rail (27) to be repaired, measuring the dimensions of said lateral branch and machining with identical dimensions at least one substitution lateral branch, mounting and fixing said substitution lateral branch and measuring the spacing between the spans of the lateral branches of the repaired guide rail.

Abstract: An underwater cutting device for the handle of MTR plate-type fuel has a housing that has an accommodation space for a feed pneumatic cylinder to drive a slidable base for lateral movement. And in front of the accommodation space there is a cutting chamber. A primary motor is located on the slidable base to drive the saw blade inside the cutting chamber to move and cut laterally with the slidable base that is driven by the feed pneumatic cylinder. A positioning block is located on the side with the housing and in the moving path of the saw blade. In the positioning block there is an accommodation space to hold the MTR plate-type fuel. Above the positioning block there is at least a pressing pneumatic cylinder to immobilize the MTR plate-type fuel and facilitate the saw blade to cut and remove the handle of MTR plate-type fuel.

Abstract: An apparatus for removing a dry tube assembly includes a mounting structure configured to mount the apparatus to a top guide of a reactor vessel, a clamping assembly configured to engage the dry tube assembly, and a positioning assembly that is configured to position and rotate the clamping assembly relative to the dry tube assembly. The dry tube assembly is buckled and removed without exercising a joint.

Abstract: A method for production of spacers to hold at least a number of elongated fuel rods (5) in a fuel unit (20) for placement in a re-actor (1) is described. The method comprises the steps of providing at least two spacers (30), to provide a set of mandrels (40) comprising a number of mandrels (42), to arrange at least two spacers (30) with one on top of the other on the set of mandrels (40), and to heat treat the spacers (30) when they are arranged on the set of mandrels (40) so that the cells (31) in the spacers (30) adapts to the mandrels (42).

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: A method of manufacturing a radiation source in one example comprises selecting at least one of a target, a collimator, and target shielding consisting essentially of at least one isotope having a neutron production threshold less than a peak acceleration energy of the source, and assembling the source including the selected material.

Abstract: A method for installing a locking retainer in a tube to maintain internal components within the tube under compression comprising the steps of: a) providing an elongated retainer spring having large and small diameter sections with the large diameter section of a size for an interference fit with the interior diameter of the tube and the smaller diameter section of a size having a clearance with the interior diameter of the tube; b) inserting a smaller diameter section of an elongated tool into the larger diameter section of the elongated retainer spring; c) engaging a transition between the smaller and larger diameter sections of the tool against a transition between the larger and smaller diameter sections of the elongated retainer spring; d) inserting the combined tool and retainer spring into an open end of the tube containing internal components with an end of the smaller diameter section of the retainer spring entering the tube first; e) advancing the combined tool and retainer spring within the tube to

Abstract: A modular submersible repairing system includes a working unit having a tool module capable of repairing structures in a reactor. A scanning/pitching module is capable of being selectively connected to or disconnected from the tool module, and is provided with a scanning/pitching shaft for scanning or pitching the tool module. A submersible fan module is capable of being selectively connected to or disconnected from the scanning/pitching module. A first buoyant module keeps an orientation of the tool module. A base unit includes a manipulator module internally provided with an actuator driving mechanism. An adsorbing module is capable of being detachably mounted on the manipulator module and a wall. A second buoyant module keeps the orientation of the manipulator module. The scanning/pitching module and the manipulator module are provided with a submersible connecting device capable of being operated in water for engagement and disengagement.

Abstract: A basket assembly fixture is useful in the construction of a basket assembly for interring spent nuclear fuel rods. The basket assembly fixture has an elongate base and a pair of lifting beams disposed above the base. Lifting beam raising means are provided at both ends of the base to raise the pair of lifting beams. A transverse beam is provided below the two lifting beams and above the base. Transverse beam raising means are provided for raising the transverse beam.

Abstract: A pressure vessel having a removable closure head in a high radiation environment is closed by placing the closure head having a flange over and spaced from the flange of a pressure vessel body containing fissile material. The closure studs are installed in closure stud holes of the pressure vessel body flange. Transition nut members of hydraulic nut assemblies are threaded onto the closure studs. Hydraulic hoses are connected between the hydraulic nut assemblies and a pressure source. The pressure source simultaneously pressurizes the hydraulic nut assemblies to simultaneously apply a uniform force to the closure studs sufficient to seat the spaced apart closure head flange on the pressure vessel body flange and to elongate the closure studs. The hydraulic nut assemblies are locked in place over the closure head flange while the force is applied to the closure studs and the closure studs are elongated.

Abstract: The method of protectively coating metallic uranium which comprises dipping the metallic uranium in a molten alloy comprising about 20-75% of copper and about 80-25% of tin, dipping the coated uranium promptly into molten tin, withdrawing it from the molten tin and removing excess molten metal, thereupon dipping it into a molten metal bath comprising aluminum until it is coated with this metal, then promptly withdrawing it from the bath.

Abstract: A modular submersible repairing system includes a working unit having a tool module capable of repairing structures in a reactor. A scanning/pitching module is capable of being selectively connected to or disconnected from the tool module, and is provided with a scanning/pitching shaft for scanning or pitching the tool module. A submersible fan module is capable of being selectively connected to or disconnected from the scanning/pitching module. A first buoyant module keeps an orientation of the tool module. A base unit includes a manipulator module internally provided with an actuator driving mechanism. An adsorbing module is capable of being detachably mounted on the manipulator module and a wall. A second buoyant module keeps the orientation of the manipulator module. The scanning/pitching module and the manipulator module are provided with a submersible connecting device capable of being operated in water for engagement and disengagement.

Abstract: A basket assembly fixture is useful in the construction of a basket assembly for interring spent nuclear fuel rods. The basket assembly fixture has an elongate base and a pair of lifting beams disposed above the base. Lifting beam raising means are provided at both ends of the base to raise the pair of lifting beams. A transverse beam is provided below the two lifting beams and above the base. Transverse beam raising means are provided for raising the transverse beam.

Abstract: A modular submersible repairing system is capable of dealing with various tasks somewhat inefficiently, though, and of being inserted and installed in a reactor instantly, and highly maneuverable. A repairing method is carried out by the modular submersible repairing system.

Abstract: The present invention relates to a method for refurbishing an atomic fuel assembly storage rack the partitions (10) of which include a layer (14) of neutron-absorbing material between a wall (16) and a more or less rectangular piece of sheet metal (18) welded onto said wall. In this method the sheet metal is cut along each of the four sides. Once the short sides of sheet metal (18) have been cut by cutting the welding spots or by cutting it into sections the long sides are cut using a cutting head (20) that includes one to four blade-blade support assemblies (22) or one to four blades. Each blade (24) and blade support (26) is either fixed or movable.

Abstract: A heat pipe shaping device comprises a rectangular table, and each lateral surface of the table has a work station. The top plate of the table is elevated by a plurality of supporting rods at a periphery of the table. A vacuum manifold is connected to the top plate. Thereby, the vacuum manifold is connected to a vacuum pump. A welding gun is positioned at the top plate so that the welding gun is connected to a welding machine. Each work station is connected to a surface of the rotary disk on the table and the rotary disk is driven by a motor in the table. Each work station on the rotary disk has an supporter. A top of each supporter is installed with a pressing unit and a cutting unit. One end of the vacuum manifold is installed with a clamping unit for clamping a heat pipe to pump into a vacuum condition,. The heat pipe is then pressed to seal the opening, and the distal end is cut by the cutting unit, and finally, the opening is spot-welded.

Abstract: A method for removing a plug from engagement with a nuclear reactor steam generator tube within a tube bundle, which plug has a shell, an expander, and a plug top, by providing a drill bit having a pilot portion and a drill portion, where the pilot portion diameter is smaller than the drill portion diameter. Further, removing a portion of the plug shell and expander using the drill bit and leaving the plug top in the tube. The plug top may be removed by providing a gripper tool, inserting the gripper tool into the tube, urging the gripper against the plug top and removing the plug top by removing the gripper from the tube.

Abstract: A mechanical tube expander for expanding tubes into interlocked relationship with fins. Structure is provided for in situ storage of the expander rods and facilitating use of selected expander rods during a cycle of operation.

Abstract: A tool fixture device for positioning tools to repair defects adjacent to the sealing grooves in a pressure vessel head. The device includes a two pair of parallel, spaced apart, arcuate segments adapted to fit into one of the sealing grooves. A support plate is attached to the first and the second pair of parallel, spaced apart, arcuate segments. The fixture includes a plurality of threaded rods for expanding the ends of the parallel arcuate segments to engage the inside walls of one of the grooves to hold the fixture in place. In the preferred embodiment, a tool positioner is adapted to be attached to the support plate for positioning a repair tool to permit the repair tool to be used to repair defects adjacent to the sealing grooves. The tool positioner includes a planar table and a tool jig attached to the planar table for receiving the repair tool.

Abstract: An apparatus for repairing cracked core spray supply piping in a boiling water reactor vessel includes a pair of clamps extending circumferentially around the piping on opposite sides of a crack and a preloading mechanism urging the clamps toward one another to apply and maintain an axially compressive load on the piping tending to close the crack. For vertical sections of core spray supply piping, the clamps are secured at vertically spaced locations with each of the clamps including a first jaw extending circumferentially around a first portion of the piping and including a first opening oriented substantially parallel to a longitudinal axis of the piping and an elongate passage or channel oriented substantially perpendicular to and in communication with the first opening.

Abstract: An apparatus for repairing cracked core spray supply piping in a boiling water reactor vessel includes a pair of clamps extending circumferentially around the piping on opposite sides of a crack and a preloading mechanism urging the clamps toward one another to apply and maintain an axially compressive load on the piping tending to close the crack. For vertical sections of core spray supply piping, the clamps are secured at vertically spaced locations with each of the clamps including a first jaw extending circumferentially around a first portion of the piping and including a first opening oriented substantially parallel to a longitudinal axis of the piping and an elongate passage or channel oriented substantially perpendicular to and in communication with the first opening.

Abstract: Method for expanding tubular members, such as U-shaped heat transfer tubes having ends thereof located in the confined space adjacent the curved sides of the bowl-shaped lower plenum of a typical nuclear steam generator. The apparatus includes an elongate mandrel having a flow channel therethrough in communication with a resilient tubular bladder surrounding the mandrel. The bladder is flexible about its longitudinal axis due to the ribbed construction of the wall thereof. The mandrel includes a plurality of segments, adjacent ones of the segments interconnected by a ball-and-socket joint therebetween, so that the segments swivel about respective ones of the ball-and-socket joints. Thus, the mandrel and the expandable bladder connected thereto are flexible rather than rigid in order to be easily inserted into the tube ends located adjacent the curved sides of the bowl-shaped plenum and in order to easily traverse the upper U-bend portion of the tube.

Abstract: Method of restricting transverse displacement of a nuclear heat exchanger tube support plate during a transient event, the support plate having a plurality of holes therethrough for passage of respective ones of a plurality of heat transfer tubes. The method includes radially expanding the tube adjacent the first side of the support plate to define a first expanded region thereat, the tube being expanded to a diameter greater than the diameter of the hole formed through the support plate. The method further includes radially expanding the tube adjacent the second side of the support plate to define a second expanded region thereat, the tube being expanded to a diameter greater than the diameter of the hole formed through the support plate. The first expanded region and the second expanded region coact to restrict transverse displacement of the support plate because the support plate is firmly captured between the first expanded region and the second expanded region.

Abstract: Method and joint for sealing a bare hole in a nuclear heat exchanger tubesheet. The tubesheet has a plurality of holes formed therethrough, wherein at least one of the holes has been left vacant by a heat transfer tube removed from the hole. Such a hole is defined as a bare hole. One embodiment of the method of the invention comprises disposing a sleeve in the bare hole to protect the tubesheet material from the corrosive attack of the heat exchanger primary coolant and sealingly disposing a sleeve plug in the sleeve in order to seal the sleeve. A leak-tight joint is defined as the sleeve plug is sealingly disposed in the sleeve.

Abstract: An apparatus for tensioning a hold down beam of a nuclear reactor jet pump inlet mixer is configured to be inserted in a confined annulus between a core shroud and a reactor vessel of a nuclear reactor. The hold down beam includes a beam body, a pair of opposed beam tabs and a pair of opposed beam trunnions extending outwardly from the beam body, and a threaded beam bolt received within a threaded channel extending through the beam body. The tensioning apparatus includes a housing having a lower base plate and an upper support plate positionable over the body of the hold down beam, rotatable trunnion engaging members for engaging the beam trunnions, reciprocating members coupled to the upper support plate and lower base plate for engaging the inlet mixer adjacent to the beam trunnions, and an actuator mounted between the upper support plate and lower base plate and extending through the lower base plate for selectively actuating the trunnion engaging members.

Abstract: A tube expanding assembly expands a plurality of tubes used in combination with a plurality of fins and end sheets to form a heat exchanger, the tube expanding assembly includes a nest plate secured to the base wherein the nest plate holds the tubes thereon, a bolster cylinder extendable between the base and the nest plate for moving the nest plate relative to the base, a ram support disposed above the base, a ram plate secured to the ram support, a ram cylinder depending from the ram support and secured to the ram plate wherein the ram cylinder moves the ram plate relative to ram support, a plurality of expansion rods depending from the ram plate wherein each of expansion rods is extendable through each of the tubes such that the tubes engage the fins and end sheets, and a plurality of transducers, each of the transducers are associated with each of the bolster cylinder and the ram cylinder such that the transducers create signals identifying position of each of the ram plate and the nest plate.

Abstract: Apparatus for localized radial expansion of a ductile metal tube into tight engagement with a tube support sheet, e.g., for deformable member which is axially compressed by hydraulic pressure to effect radial expansion of the deformable member and the tube. The hydraulic pressure is multiplied to provide a relatively high force in a small diameter by connecting a plurality of pistons in series by rigid connecting rods having axial and radial bores for flow of pressurized fluid. The apparatus carries a probe for locating the position of the tube support sheet and a support member carrying an eccentric cam. Rotation by an operator of the support member, by rotation of a rod passing therethrough, causes the cam to frictionally engage the tube wall and wedge the support member in position to provide an abutment surface for contact by a stop member on the rod, thereby positioning the deformable member at the desired axial location to effect radial expansion of the tube.

Abstract: A weld fixture for receiving and aligning the fuel rod contact points of a nuclear fuel bundle spacer grid. Two plates are provided with intersecting unequally spaced slots that define polygons on one side of each plate. Both plates have bores therethrough substantially at the slot intersections and in the slots adjacent the outer edges of the plates. Bores are provided through both plates in polygons that correspond to fuel assembly guide tube and instrument tube locations. These positions receive guide cell pins during use, some of which are hollow and are used to bolt the plates together over the spacer grid strips. Bores in each plate through the defined polygons receive alignment pins. Guide rods receive and align the plates through corner bores in each plate. The slots and pins in the facing plates align the critical fuel rod contact points in the spacer grid during the intersection welding process.

Abstract: An apparatus is presented for removing the keys smoothly and reliably from support grids of a fuel assembly. The apparatus performs the task of removing the keys, which had been inserted into the grid through the opening sections of the grid, and enables mechanization and automation of the key removal operation. The apparatus has a robotic arm including a pair of parallel grid support members freely movably disposed at the end of the robotic arm for clamping onto the side edges of the grid. The apparatus further includes a key rotation device disposed on the support arm for engaging with and rotating the keys; a key moving device disposed on the grid support members so as to hold the keys and move the keys in the direction of the key axis.

Abstract: A tool for removal of the internal bushings from a piston coupling of a CRD. The tool incorporates a spring-loaded and hardened collet supported on one end of a ram. The collet has a pair of arms with shoulders or projections which latch inside the internal bushing ring to be removed. The tool is inserted into the piston coupling from either end, depending on which internal bushing is to be removed. The tool is inserted until the latching shoulders or projections snap behind the radially inwardly projecting internal bushing, with the contact surfaces of the shoulders or projections in contact with a radial end surface of the bushing. The bushing can then be dislodged, from the inside out, by impacting the other end of the ram with a hammer.