Abstract: A method of remote control of a mobile carriage including at least one transmit and receive antenna for movement into an underground gallery connected to the surface by a shaft provided with an elevator for effecting deep storage of radioactive wastes. The method involves fitting the site with a plurality of waveguides from a control station which includes a signal generator and a signal receiver and being situated on the surface. The plurality of waveguides are disposed with at least one first waveguide at the surface extending from the control station to the entrance to the shaft. At least one second waveguide is disposed along the shaft and connected at its top end to the first waveguide. At least one third waveguide is disposed along the gallery and connected to the second waveguide in the vicinity of the entrance to the gallery.

Abstract: A device for handling liquid radioactive waste includes a heater for heating and drying liquid radioactive waste being poured into a container. A pallet, which is preferably formed of metal, receives the container. A ground vehicle transports the pallet. A supplementary heater is part of the pallet.

Abstract: For transferring products from a contaminated enclosure (12) into a second enclosure (16) without contaminating the latter, it is proposed to engage on the contaminated enclosure a transportation container (20), in which is placed an empty transfer chamber (22). After removing the coupled doors (C,F,H) of the contaminated enclosure, the container and the transfer chamber, the products to be transferred are introduced into the latter, without the space surrounding the chamber within the container communicating with the enclosure. This is followed by the reclosing of the coupled doors (C,F,H) and the disconnection of the container (20), in order to transport it and engage it on the second enclosure (16). The coupled doors (B'C', F) of said second enclosure and the container (20) are then opened in order to introduce into said second enclosure the transfer chamber (22) containing the products.

Abstract: The swipe transfer assembly is a mechanical assembly which is used in conjunction with glove boxes and other sealed containments. It is used to pass small samples into or out of glove boxes without an open breach of the containment, and includes a rotational cylinder inside a fixed cylinder, the inside cylinder being rotatable through an arc of approximately 240.degree. relative to the outer cylinder. An offset of 120.degree. from end to end allows only one port to be opened at a time. The assembly is made of stainless steel or aluminum and clear acrylic plastic to enable visual observation. The assembly allows transfer of swipes and smears from radiological and other specially controlled environments.

Abstract: A transfer system moves fuel assemblies along a track extending through a transfer tube within a containment wall in a nuclear power plant between the auxiliary building side and the containment building side. A car carries a basket for the assemblies. Two winches are located on the auxiliary building side above the water level existing over the track during refueling operations. The winches operate respective pairs of cables, driving the car in either direction. Four sheaves respectively direct the cables to the horizontal direction along the track. One pair of cables is secured to a yoke on the car to drive the car away from the containment building. Two horizontal sheaves are located near the containment end of the transfer tube. The other two cables extend horizontally along the track from the vertical sheaves to the horizontal sheaves, redirecting them to extend horizontally in the reverse direction. These return cables are secured to the yoke to drive the car toward the containment building.

Abstract: The invention is directed to a centering arrangement for aligning two mutly adjacent openings of a lock and a container for receiving radioactive waste which is passed into the container through the lock. The container is provided with additional openings having a cross-sectional center point which is displaced from the cross-sectional point of the container per se. The centering arrangement includes a carrier which is pivotally journalled on a vehicle so as to be movable from a vertical plane into a horizontal plane and the vehicle is movable along rails in a horizontal direction. The longitudinal axis of the container is in a position aligned to a fixed point of the lock. The carrier includes a first container guide including an annular member having an inner conical surface and a second conical guide for positioning the container openings with respect to the rotational position of the container.

Abstract: The invention is directed to an arrangement for transferring irradiated f rods from a trough-shaped receptacle into a canister intended for terminal storage. The canister is docked at a pass-through opening formed in a partition wall of a nuclear facility. The arrangement includes a trough-shaped insert which is movable out of the terminal storage canister while empty and through the pass-through opening into the trough-shaped receptacle whereat it is filled with the irradiated fuel rods and then returned back through the opening and into the terminal storage canister. In this way, and with little effort, a transfer of fuel rods is achieved without components disposed between the receptacle and canister becoming contaminated by radioactive particles.

Abstract: A flask assembly for the transfer of objects, in particular objects contaminated by radioactivity, into and out of an enclosure. The assembly includes a levelling system to sit over a posting port in an enclosure for the objects and which supports a stool assembly. The stool assembly includes a lower gamma gate which cooperates with an upper gamma gate on a flask body which is removably mounted on the stool assembly. The flask body carries a winch system for flasking objects through the posting port. A shock absorber unit is housed within the stool assembly.

Abstract: The invention relates to a docking arrangement for docking a transport container to a lock opening of a radioactively charged work chamber for loading and unloading radioactive materials. In order to dock the heavy transport container precisely at the lock opening and to reliably remotely manipulate the closure cover of the container, the lock opening is covered from within the work chamber by a bell-shaped closure device which can be removed inwardly. This bell-shaped closure device is laterally displaceable in the lock opening and is resiliently journalled and therefore can align itself with respect to the docked transport container.

Abstract: The invention is directed to an apparatus for performing the remotely-manlated installation and removal of a pass-through conduit unit into and out of a channel formed in a partition wall. A feed assembly is part of the apparatus and includes a plurality of parts assembled to form an elongated body in the channel. An articulated coupling such as a ball joint couples the conduit unit to the elongated body. A drive is operatively connected to the elongated body for displacing the latter in the channel. A crane has a holder for holding and remotely manipulating the conduit unit as the latter is installed or removed from the channel.

Abstract: A nuclear fuel pellet unloading apparatus includes a transfer housing pivotally movable between an upright position remote from a pellet deposit site and an inverted position adjacent to the deposit site, and convertable between opened and closed conditions. In its upright position and closed condition, the housing receives a sintering boat loaded with nuclear fuel pellets and holds the boat while retaining the pellets within the boat as the boat is moved from upright to inverted orientations upon pivoting of the housing from its upright to inverted position. An actuator is operated for causing pivoting of the housing from its upright to inverted position and back to its upright position. A latch member latches the housing in its closed condition when the housing is disposed in its upright position and as the housing is pivoted from its upright position toward its inverted position.

Abstract: In order to place in sealed communication two reactor containments provided with openings capable of having a displacement between their axes, an assembly (12) is placed between the flanges (B.sub.1, B.sub.2) delimiting these openings, said assembly comprising two mobile linking parts (30a, 30b) according to a common axis, these parts bearing lip seals (36a, 36b) coming to take sealed support on the flanges under the action of a control (52) and springs (44) mechanism. Two double doors (14a, 14b) can be placed inside the openings and the linking parts in order to ensure separation of the containments. These double doors are formed of doors (16a, 18a, 16b, 18b) interconnected by means of magnets (62a, 64a, 62b, 64b) authorizing a certain relative sliding.

Abstract: An apparatus for aligning nuclear fuel pellets includes an endless belt for advancing nuclear fuel pellets along a generally linear path in a direction generally coincident with their axes and a stopper element disposed in the linear path for stopping advancement of the pellets therealong for assembling pellets in a row. A detector device senses when advancement of a prescribed number of the pellets in a row have been stopped by the stopper element. A feed mechanism is operable for successively feeding pellet holding trays one at a time to a pellet receiving position along the linear path. A panel defines an inclined path extending from the linear path downward to the one tray disposed at the receiving position. An ejector mechanism disposed along the linear path is responsive to the detector device for pushing the assembled row of pellets sidewise from the linear path along the inclined path of the panel to a groove defined in the one tray.

Abstract: A temporary hot cell and related method for handling high radiation level sources having wall, ceiling and floor structures comprised at least in part of temporary structures forming an enclosure to reduce to acceptable levels radiation of the surround from high level radiation sources handled within the enclosure. Preferably one or more manipulator arms extended through a wall structure of the enclosure to permit handling of the high level radiation sources within the enclosure by an operator located external to the enclosure. A window is positioned in the wall structure of the enclosure to allow an external operator to view handling of the radiation sources. The hot cell preferably also has a false floor, a filter and vent system sheeting to cover portions of the inner surface of the temporary structure forming the enclosure hot cell.

Abstract: The invention is directed to an apparatus for pulling a plurality of fuel ds out of a fuel element structure and has a gripping device which is capable of clamping the fuel rods. To reliably pull the fuel rods from an irradiated nuclear reactor fuel element, the apparatus includes an upper guide rod and a lower tension rod which lie horizontally and are arranged one above the other. The rods extend through a plurality of clamping plates in a direction perpendicular to the latter. The clamping plates are mounted so as to be parallel to each other and spacers are arranged between each two mutually adjacent ones of the clamping plates. The spacers are arranged on both rods with the width of the spacers on the lower rod beign slightly less than the diameter of a fuel rod. The clamping plates are pressable together by means of a tensioning device. The apparatus of the invention enables the gripping device to be placed on the fuel element in a simple manner.

Abstract: A pellet collating system includes a tray positioning station located adjacent a pellet collating line with a tray transfer robot located therebetween. The tray positioning station has mobile carts lodged thereat, some supporting pellet supply trays and others supporting pellet storage trays. Pellets on one supply tray and later placed on one storage tray are of the same enrichment. Pellet enrichments on some trays are different from on others. The collating line includes pellet input, work and output stations arranged in tandem. The robot is operable to transfer supply and storage trays one at a time to and from the positioning station and the respective input and output stations. An input sweep head is operable for sweeping pellets onto the work station from a supply tray on the input station. A gripping and measuring head is operable for measuring a desired length of pellets on the work station and then separating the measured desired length of pellets from the remaining pellets, if any.

Abstract: An inspection system for detecting leakage from for example the primary vessel (11) of a nuclear reactor includes a camera (29) carried by an umbilical cable (28) which can be fed through a duct assembly (22) comprising a series of tubular sections (23) connected endwise by flexible bellow (24). A guide track (18) extends around the top of the vessel (11) and each duct section (23) is provided with wheels (25) which engage the track (18). A curved guide tube (17) feeds the duct sections (23) from a vertical entry position (15) in the roof (13) into a horizontal track-engaging disposition. The track (18) includes spaced flanges (20b, 21b) through which the umbilical cable can extend and depend downwardly into the annular space between the primary vessel (11) and a surrounding guard vessel (12).

Abstract: In order to transfer a bundle of rods of or from a nuclear fuel assembly into a storage case, the bundle is placed in a waiting position above a cassette provided with recesses. The rods are then introduced into the recesses by lowering them by gravity. When the cassette is full, it is brought into the extension of the case by interposing a transformation member. By simultaneously exerting a thrust on all the rods, the latter are compactly transferred into the case.

Abstract: Bodies such as nuclear fuel pellets are formed into a stack in a stacking lane (34) and the length of the stack is measured at intervals by device (40) to determine if the partly-formed stack is drifting away from a target length. Pellets are issued into the stacking zone (34) by a selector mechanism (32), the input of which receives pellets from three lanes (24, 26, 28) containing oversize, undersize and intermediate size pellets and the pellets issued to the stacking lane (34) are selected under the control of microprocessor-based unit (18) according to the extent of any drift from the target value. The pellets in lanes (24, 26, 28) are derived from a common supply (12) following segregation by a diverter mechanism (22) controlled by unit (18) in accordance with length measurements made by measuring device (16).

Abstract: Apparatus for transferring components, particularly rod control cluster elements for a nuclear reactor, to and from containers, particularly fuel assemblies, with the aid of a movable carriage containing compartments for receiving at least one fuel assembly and at least one rod control cluster element. The carriage is mounted on tracks and carries an abutment member arranged to cooperate with stops which delimit respective positions of the carriage along the tracks. When the carriage is at least in some of its positions, a respective compartment is located directly below a vertically movable gripper which is operable for gripping a rod control cluster element. In order to allow the carriage to have more than two positions, there is provided a movable stop which can be lowered to permit the carriage abutment member to move therepast and raised to be contacted by the abutment member.

Abstract: The invention is directed to a remotely-operable positioning and carrier aratus for remote-handling equipment for use in large-area cells containing process components. The apparatus is mounted on a lifting device of an overhead bridge crane. The apparatus achieves good positioning of the particular remote-handling equipment even at locations which are poorly accessible. The apparatus includes a horizontal beam which is fixed at an eccentric position thereon to the bottom sheave unit of the lifting device so that the horizontal beam defines a long lever arm and a short lever arm. A receiving lever is pivotally connected to the end of the longer lever arm. The receiving lever has an equipment receiving device at its free end. A displaceable counterweight is arranged on the short lever arm for altering the position of the center of gravity of the apparatus. This apparatus makes it possible also to operate in spaces beneath components present in a rack.

Abstract: A method and an apparatus for loading containers with individual fuel rods or fuel-rod sections of irradiated nuclear reactor fuel elements are disclosed. In order to ensure maximum safety, cleanliness and close packing when loading the containers, the fuel rods or fuel-rod sections are horizontally front-loaded into the container which is horizontally positioned. The loading aperture is located as closely as possible to the upper inner periphery of the container. Following their insertion, the fuel rods or fuel-rod sections will drop onto the inner wall surface of the container or onto the already existing pile of previously loaded fuel rods or fuel-rod sections. The container for loading with such a method has a loading aperture in the end wall thereof arranged close to the inner periphery thereof for insertion of the fuel rods or fuel-rod sectons.

Abstract: Apparatus for remotely handling a device in an irradiated underwater environment includes a plurality of tubular sections interconnected end-to-end to form a handling structure, the bottom section being adapted for connection to the device. A support section is connected to the top tubular section and is adapted to be suspended from an overhead crane. Each section is flanged at its opposite ends. Axially retractable bolts in each bottom flange are threadedly engageable with holes in the top flange of an adjacent section, each bolt being biased to its retracted position and retained in place on the bottom flange. Guide pins on each top flange cooperate with mating holes on adjacent bottom flanges to guide movement of the parts to the proper interconnection orientation.

Abstract: A facility for posting irradiated fuel from a preparation chamber of a dry storage complex into storage canisters within a clean chamber and for posting contaminated canisters from a closed bucket in the clean chamber into the preparation chamber. The facility comprises two coaxial tubular port members extending from the preparation chamber into the clean chamber, the port members having masking means for the canister and bucket closures and means for withdrawing them into the preparation chamber.

Abstract: A position sensing mechanism, for use with a nuclear fuel transfer system which employs an underwater cart having a pivotable container to receive fuel assemblies, employs mechanical elements below water and a cable which carries movement of the mechanical elements to a switch assembly at a dry location. The mechanical elements include an anchor element which is affixed to an upender mechanism, which selectively moves the container between horizontal and upended positions when the cart is located at a fuel transfer station, and a feeler mechanism which is displaced by the cart. The feeler mechanism includes a pivotably mounted swing arm and one or more pulleys. The cable is attached to the anchor elements and is guided by the pulleys. The switch assembly includes a further pulley having cams to actuate microswitches when the cable is displaced by the anchor element and feeler mechanism. A temperature compensator is spliced into the cable to keep its length constant despite temperature variations.

Abstract: An apparatus for automatically loading one or more kinds of nuclear fuel pellets in fuel cladding tubes for producing nuclear fuel rods comprises at least one pellet transporting tray transferred from a tray stacking unit and provided with a plurality of grooves on which the fuel pellets are mounted, at least one pellet aligning tray provided with a groove selectively connected with one of the grooves of the pellet transporting tray at one end of the aligning tray, and a fuel cladding tube supporting device located in the vicinity of the other end of the aligning tray and adapted to support a number of fuel cladding tubes so that a selected one fuel cladding tube is operatively connected to the aligning tray. The fuel pellets are transferred from the transporting tray into the aligning tray by means of a pushing device and the row of the pellets transferred on the groove of the aligning tray is moved forwardly until it abuts against a stopping mechanism located in association with the aligning tray.

Abstract: This hooking device is fastened to the choke plug (8) for guide tube (2). comprises of catches (54) regularly arrayed along the periphery of the flange (9) of the choke plug (8) and hooks to the upper spacer (4S) of the guide tube (2). It is kept in the engaged position by a spring system (56-58), 63-65) and can disengage by means of a tool means comprising a roller (77) acting on each catch (54) and a rim (68) resting on a muff (56) acting as a rest also for the spring (57).

Abstract: A catalyst loading hopper suitable for positioning in vertical position above a reactor vessel, having an inlet at its upper end, a catalyst outlet at its lower end and a diagonally-disposed baffle extending downwardly across the hopper but terminating short of one of the walls of the hopper and a weir adjustably arranged so as to control the flow of catalysts through the hopper. There is a dust outlet at the top of the hopper, which may be connected to a conduit so as to draw dust away from the upper end of the hopper and a screen at the bottom of the hopper to separate the catalyst from any fines or undersized catalyst particles. The screen feeds into a catalyst outlet which, in turn, feeds into a conduit, which extends into the reactor vessel so as to allow arrangement of the cleaned catalyst pellets in layers in the vessel. A gas nozzle opens in the wall of the hopper and allows dust to be blown from the catalyst pellets and through the dust outlet to be collected in a suitable filter.

Abstract: A procedure for transferring an object along an axis, from a contaminated and radioactive zone to a clean zone without breaking the confinement when the zones are separated by a slab is disclosed. The slab contains a plug and the object can be secured to the plug with the use of a stationary pre-enclosure (43) equipped with two plugs (44 and 46) and of a movable transfer enclosure (47) equipped with one plug (48). The enclosure and pre-enclosure are placed in alignment with the transfer axis.

Abstract: A cable-driven arm-reciprocating system particularly useful for transferring nuclear fuel bundles from a nuclear reactor pool to a spent fuel storage pool, wherein an arm-retracting cable extends from a winch drum around fixed and movable-axis sheaves to a retracting anchor device and an arm-extending cable extends from the same winch drum also around fixed and movable-axis sheaves to an extending anchor device, each anchor device including spring means for maintaining and allowing for variations in cable tension.

Abstract: A system for remotely repairing nuclear fuel rod assemblies is disclosed herein. Generally, the system comprises a rod handler for gripping, lifting, lowering and ungripping a selected fuel rod, a work station for securing the nuclear fuel rod assembly to be repaired into a desired location, and a positioner device for laterally positioning the rod handler over a selected rod in the fuel assembly secured within the work station. The rod handler includes a contractable collet for gripping and ungripping a desired fuel rod, and a rod sensor concentrically disposed within the collet for sensing when a rod is in a grippable position. The positioner includes a movable carriage which is slidably mounted onto a frame assembly by means of a pair of rail and bearing mechanisms. The system also includes a microcomputer for controlling the manner in which the positioner positions the rod handler, as well as gripping, lifting, lowering and ungripping motions of the handler itself.

Abstract: A method and apparatus for withdrawing spent fuel rods from a nuclear fuel rod assembly into a different nuclear fuel rod container wherein the spent fuel rods have a higher fuel rod density, whereby a greater number of spent fuel rods can be stored in a water-storage pool. The individual rods are moved from a fuel assembly and through a transition funnel by movable grippers at opposite ends of the funnel. One movable gripper reciprocates between gripping and release positions in a gap between the fuel assembly and the transition funnel. A stationary gripper can be located in the gap at the entry side of the funnel to hold the fuel rods while the movable gripper returns from a release position to the gripping position. Both grippers include members which can be pressed into frictional engagement with the spaced apart array of fuel rods. All of the fuel rods are withdrawn concurrently and are merged toward one another into a tighter array within the transition funnel and emerge as a bundle.

Abstract: A handling tool for selectively removable cruciforms employed in ice baskets of the type employed with nuclear power generator systems. The tool includes clamping means for engaging a compressible central portion of the removable cruciform to retract same inwardly and permit moving same, in a horizontal orientation, throughout the axial height of the interior of the ice basket. When at a desired elevation, selective actuating means moves previously retracted guide means to an extended or projected position for engaging a retaining ring of the ice basket and supporting the tool on the ring. The clamping means is selectively actuated to the disengaged position for releasing the cruciform whereupon the same expands, projecting legs associated therewith radially outwardly and engaging the retaining ring, to support the cruciform on the ring. The tool may thereafter be removed.

Abstract: A method of and apparatus for melting radioactive waste contained in a metal transport vessel and in which the transport vessel is introduced into a container which is closed by a laterally retractable cover and then inverted by rotation through 180.degree. about a horizontal axis to lie above the mouth of a furnace. The mouth of the furnace is provided with a horizontally retractable slider and the cover and the slider are independently retracted to allow discharge of the transport vessel and the radioactive waste contents thereof into the furnace for melting therein. The container and its cover thus form part of the gate allowing transfer of the radioactive waste into the furnace without a hot or radioactive cell shielding the entire unit from vagabond or wayward radioactivity.

Abstract: A method of crimping a locking cap secured to the nut of a new split-pin assembly to the new split-pin to preclude turning of the nut and pin relative to each other. The method is practiced with apparatus including a crimping mechanism including crimping jaws having crimping pins face-to-face near one end. The jaws have external cam surfaces. The crimping pins are retracted and brought into crimping engagement with the cap to be crimped by cam followers which traverse the cam surfaces when actuated hydraulically through a C-frame connected to the cam followers. The crimping mechanism is mounted on a support which is moveable by a hydraulic cylinder between a retracted setting, where it is latched generally vertically, and an operating setting where it is positioned generally horizontally.

Abstract: An apparatus for transportation, positioning and sealing a container used for receiving irradiated fuel from beneath a loading and unloading pit of a nuclear installation including a cart which is successively brought through a hall underneath a loading preparation station, underneath a removal station for removing the plug from the container, and underneath a penetration shaft providing the connection between the loading and unloading pit and the hall where the cart travels. The cart includes a framework placed on a rolling platform with a sliding and rolling support therebetween, and guided between side rails on the walls of the hall.

Abstract: A method and an apparatus for loading containers with individual fuel rods r fuel-rod sections of irradiated nuclear reactor fuel elements are disclosed. In order to ensure maximum safety, cleanliness and close packing when loading the containers, the fuel rods or fuel-rod sections are horizontally front-loaded into the container which is horizontally positioned. The loading aperture is located as closely as possible to the upper inner periphery of the container. Following their insertion, the fuel rods or fuel-rod sections will drop onto the inner wall surface of the container or onto the already existing pile of previously loaded fuel rods or fuel-rod sections. The container for loading with such a method has a loading aperture in the end wall thereof arranged close to the inner periphery thereof for insertion of the fuel rods or fuel-rod sections.

Abstract: A positioning and locking apparatus including a fixture having a rotatable torque ring provided with a plurality of cam segments for automatically guiding a container into a desired location within the fixture. Rotation of the ring turns the container into a final position in pressure sealing relation against a hatch member.

Abstract: Apparatus for removing irradiated clips from an irradiated fuel assembly comprises a remotely operated tool including hydraulic or pneumatic jaws operable for withdrawing a clip from fuel rods, while supporting the portions of the fuel rods both above and below the clip to avoid damaging the rods during removal of a clip, and further including a support tube held captive in a carriage mechanism for moving the tool into positions for either clip removal, or for ejection of a removed clip from the tool into a clip disposal basket.

Abstract: Method intended to form a more or less compact bundle of flexible and oblong objects of reduced cross-section dimensions, such as fuel rods of a nuclear reactor, said objects forming, prior to compacting, an assembly wherein they occupy transversally spaced, parallel positions. According to the invention, this method is characterized in that there is arranged, in a generally vertical direction, a plurality of guiding tubes (2) of which the upper ends (2a) are arranged according to the initial disposition of said object assembly, and of which the lower ends (2b) are arranged according to the desired disposition, the dimension of said guiding tubes (2) being such that in each of them one of said objects may slide by means of gravity, and in that said assembly of objects is brought vertically on top of the plurality of guiding tubes, whereafter each object is introduced by its lower end in the upper end of one of said guiding tubes (2), allowing the assembly of said objects to slide downwardly.

Abstract: An apparatus for posting materials into and out of an enclosure through a port in a wall of the enclosure. A container for the materials has a lid engageable with a door for the port and the container is supported in a cradle. An interlock bar extends between the port and a clamp assembly for the container, the bar being axially displaceable between first and second positions. In the first position of the bar one end thereof arrests movement of a door release mechanism and the bar is locked against axial displacement in the absence of a container in the cradle. In the second position of the bar the opposite end thereof engages and locks the clamp assembly for maintaining the container at the port.

Abstract: A transfer system for controlling and initiating the flow of metered amounts of materials which may be radioactive ash, radioactive calcined salts, cement, flour, or pharmaceuticals comprising a vertical non-converging conduit which acts as a storage hopper; a stationary platform located at the downward end of the conduit to allow the radial outward flow of the material; a translatable hollow piston that acts externally but coaxially to the conduit and platform to interrupt the radial flow of material; a hopper located below the platform for accepting the material; and a housing that encloses and supports the hopper and platform and provides a dust tight seal around the apparatus of this invention.

Abstract: Device for disposing of elongated core instrumentation probes from nuclear reactors, the device having a guide for the probes to be disposed of, shears for cutting the elongated probes into sections and a shroud for receiving the sections, including a shielded storage container, the guide including a switch for bypassing the shroud, and means for controlling the switch together with the shears for directing relatively long probe sections having a relatively low radiation level into the shroud, and for cutting probe parts having a relatively high radiation level into manifold shorter sections and guiding the manifold shorter sections of the probes having the relatively high radiation level into the storage container.

Abstract: A method and an apparatus for loading containers with individual fuel rods r fuel-rod sections of irradiated nuclear reactor fuel elements are disclosed. In order to ensure maximum safety, cleanliness and close packing when loading the containers, the fuel rods or fuel-rod sections are horizontally front-loaded into the container which is horizontally positioned. The loading aperture is located as closely as possible to the upper inner periphery of the container. Following their insertion, the fuel rods or fuel-rod sections will drop onto the inner wall surface of the container or onto the already existing pile of previously loaded fuel rods or fuel-rod sections. The container for loading with such a method has a loading aperture in the end wall thereof arranged close to the inner periphery thereof for insertion of the fuel rods or fuel-rod sections.

Abstract: An apparatus is provided for the automatic assembly of nuclear fuel rod bundles in a predetermined coordinate array. Each fuel rod is identified during its travel and positioned according to an identifying code carried on its lower end plug which designates the fuel enrichment and additive level of the rod.

Abstract: A fuel transfer system for transferring fuel assemblies through a transfer tube between fuel exchange locations respectively in a fuel storage and handling building and a containment structure of a nuclear reactor includes a segmented track comprising first, second and third track segments and a segmented drive screw comprising first, second and third drive screw segments respectively associated with the fuel storage and handling building, the transfer tube, and the containment structure. Gaps between the successive, corresponding track segments and drive screw segments permit operation of valves for closing the ends of the transfer tube during normal operation of the reactor, which valves are then opened during fuel exchange operations. The adjacent but normally displaced ends of the first and second and of the second and third drive screw segments include respective, mating engagement means.

Abstract: A pushrod assembly including a carriage mounted on a shaft for movement therealong and carrying a pushrod engageable with a load to be moved. A magnet is mounted on a supporting bracket for movement along such shaft. Means are provided for adjustably spacing said magnet away from said carriage to obtain a selected magnetic attractive or coupling force therebetween. Movement of the supporting bracket and the magnet carried thereby pulls the carriage along with it until the selected magnetic force is exceeded by a resistance load acting on the carriage.

Abstract: A fuel rod-loading fixture for expediting the loading of fuel rods in an empty skeleton of a fuel rod assembly is disclosed herein. The fuel rod-loading fixture generally comprises a square array of non-radioactive "dummy" rods which are all connected at their top ends to a top guide plate. When the rods of the fixture are lowered through the rod-receiving apertures of the grids in the fuel assembly skeleton, they effectively obstruct every other set of mutually aligned, rod-receiving apertures in the grids of the skeleton. The top guide plate includes a plurality of apertures which will automatically register with the remaining sets of mutually aligned apertures in the grids, in order that fuel rods may be inserted through the top guide plate and into the remaining sets of apertures in the grids.

Abstract: An interactive system (10) for facilitating assembly of fuel rods into nuclear fuel assemblies having specific grid location requirements for the fuel rods, includes an operator work station (12) adapted for positioning between a supply of fuel rods and a fuel assembly loading magazine (22). Identifying data with each fuel rod is read by the operator with a manual scanner (24) for input and comparison by a computer (28) with the stored data for the particular fuel assembly to be assembled. The proper grid location for the fuel rod is then displayed on a screen (32) prompting the operator to insert the rod through a prompter/detector apparatus (36) mounted on one end of the magazine. In the preferred embodiment, the apparatus (36) includes a pair of motorized, slotted guide bars (54, 56) controlled by the computer (28) to intersect over the proper grid location for the particular fuel rod type.

Abstract: A tool for positioning a lower guide tube of a reactor for replacement of old split-pin assemblies by new split-pin assemblies. The lower guide tube has an upper and a lower flange and has a length typically between 124 and 150 inches. The split-pin assemblies are secured in counterbores in the lower flange. The tool includes an upper deck and a lower deck. The LGT is suspended from the upper deck from pins which engage holes in the upper flange. With the LGT so suspended the lower flange extends into the lower deck in position to be processed for the replacement. A rotary hydraulic cylinder is provided in the upper deck to rotate the LGT in positions to be processed by other tools involved in the replacement and also so that both of the old split-pin assemblies which are spaced 180.degree. around the periphery of the LGT may be replaced by a single set of robotic tools. A hydraulic lift cylinder is also provided at the upper level to raise the LGT so that it clears the pins when the LGT is to be rotated.