Abstract: An article transporting apparatus for inserting an article into a port of a vessel and removing the article from the vessel through the port and for transporting the article in a direction transverse to the inserting and removing direction within the vessel. The apparatus includes a frame movable into and out from the vessel through the port, a parallel link mechanism mounted on the frame for transporting the article in a direction transverse to a direction of movement of the frame, a device for driving the parallel link mechanism, and a device for connecting the end of the parallel link mechanism to the article.

Abstract: A crane for use in a nuclear waste handling facility is disclosed. The crane includes a bridge of sufficient transverse dimension to span the width of the area being serviced, a bridge drive for moving the bridge along spaced rails extending longitudinally along opposite sides of the area being serviced, and a crane control cabinet depending from a cantilevered support extending from one end of the bridge. The nuclear waste handling facility includes a stationary radiation barrier extending longitudinally in spaced relationship to one of the rails supporting the crane. The barrier is positioned between the bridge and the crane control cabinet.

Abstract: A remote control apparatus for removing from one of a number of filter pits, and loading for protective storage in a disposal drum, radioactive filters used in nuclear power generating stations, and for replacing spent filters. The apparatus includes a transportable base adapted to be placed adjacent the respective filter pit and a hoist mechanism mounted on the base. The hoist mechanism includes a vertical tower or mast mounted on the base, a generally horizontal boom mounted on and extending outwardly from the top of the mast, a grab mechanism for engaging various specially adapted articles, including spent filters to be removed and new filters for replacement, means for operating the grab mechanism from a remote location, a lift mechanism for supporting the grab mechanism from the outer end of the boom and for raising and lowering it in a vertical path, and means for operating the lift mechanism from the remote location.

Abstract: An automated loading system for nuclear reactor fuel elements utilizes a gravity feed conveyor which permits individual fuel pins to roll along a constrained path perpendicular to their respective lengths. The individual lengths of fuel cladding are directed onto movable transports, where they are aligned coaxially with the axes of associated handling equipment at appropriate production stations. Each fuel pin can be reciprocated axially and/or rotated about its axis as required during handling steps. The fuel pins are inserted as a batch prior to welding of end caps by one of two disclosed welding systems.

Abstract: A system and method for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Abstract: A nuclear reactor containing assemblies having two caps and a framework inside which fuel rods are disposed vertically is reloaded by first inverting the assembly to be removed into a vertical position permitting the then lower cap to be demounted. The spent fuel rods are then identified and removed in sets and deposited in a suitable storage area, and replacement rods are placed in sets in the framework of the fuel assembly. Finally, the lower cap is replaced and the assembly is conveyed into the reactor vessel at its new location.

Abstract: A typical embodiment of the invention provides a nuclear fuel assembly lock structure for control rod guide tubes. Illustratively, a sleeve telescopes over an end portion of a control rod guide tube which bears against an internal shoulder of the tube. The upper end of the sleeve protudes beyond the control rod guide tube spider and is locked in place by means of a resilient cellular lattice or lock that is seated in a mating groove in the outer surface of the sleeve. A special tool is provided for disengaging the entire lock structure, washer, spider, spring and grill from the end of the fuel assembly in order to enable these components to be removed in an assembled state and subsequently replaced on the fuel assembly after inspection and repair.

Abstract: A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

Abstract: A reactor refueling method utilizing a vibrating fuel grapple for removing spent fuel assemblies from a reactor core which incorporates a pneumatic vibrator in the grapple head, enabling additional withdrawal capability without exceeding the allowable axial force limit. The only moving part in the vibrator is a steel ball, pneumatically driven by a gas, such as argon, around a track, with centrifugal force created by the ball being transmitted through the grapple to the assembly handling socket.

Abstract: A cable handling system for use in an installation such as a nuclear reactor is disclosed herein along with relevant portions of the reactor which, in a preferred embodiment, is a liquid metal fast breeder reactor. The cable handling system provides a specific way of interconnecting certain internal reactor components with certain external components, through an assembly of rotatable plugs. Moreover, this is done without having to disconnect these components from one another during rotation of the plugs and yet without interfering with other reactor components in the vicinity of the rotating plugs and cable handling system.

Abstract: A reusable thermally actuated linkage arrangement includes a first link member having a longitudinal bore therein adapted to receive at least a portion of a second link member therein, the first and second members being sized to effect an interference fit preventing relative movement therebetween at a temperature below a predetermined temperature. The link members have different coefficients of thermal expansion so that when the linkage is selectively heated to a temperature above the predetermined temperature, relative longitudinal and/or rotational movement between the first and second link members is enabled. Two embodiments of a thermally activated linkage are disclosed which find particular application as actuators for a grapple head positioning arm in a nuclear reactor fuel handling mechanism to facilitate back-up safety retraction of the grapple head independently from the primary fuel handling mechanism drive system.

Abstract: Tubes or cables designated as ducts and extending through a movable component which is capable of rotational motion about a vertical axis are supported between a fixed point located externally of the movable component and a second point which is located on the vertical axis of rotation of the component and constitutes the extremity of the supporting means. The portions of ducts located between the extremity of the supporting means and the center of rotation of the movable component are guided and maintained in uniformly spaced relation on a ruled surface of revolution about the axis of said movable component so that the duct portions thus form a bundle-type assembly. Means are further provided for securing the lower extremity of the guiding means to the movable component at the center of rotation of this latter.

Abstract: A method and arrangement for utilizing mixed oxide fuel in the core of a nuclear reactor controlled by rectilinearly movable control rod elements which decreases the maximum single control rod element worth in the core. Fuel elements containing the mixed oxide fuel are positioned at discrete core locations, particularly at those locations receiving high worth control rod elements, thereby decreasing the worth of those control elements.

Abstract: A detachable and leaktight device for closing an orifice of a nuclear reactor vessel during hydraulic pressure testing comprises a body which bears, inside the vessel, on an internal part of the vessel which is resistant to the thrust stresses during the application of pressure, sealing means for producing a seal between the interior and the exterior of the vessel and being mounted on the body, and operating means for fixing and/or demounting the device, the operating means being accessible and operable from outside the vessel.

Abstract: A refueling machine for inserting and removing fuel assemblies from a nuclear reactor including a pair of concentrically disposed stationary masts mounted on a movable bridge which spans the containment walls of the reactor. The bridge supports a trolley movable transversely to bridge movement thus providing an arrangement wherein the masts can be precisely positioned over a fuel assembly in the reactor core. A hoist mounted on the outer of the masts supports a vertically movable inner mast of a size sufficient to enclose a fuel assembly. An actuator tube inside the inner mast moves gripper fingers on the bottom thereof into engagement with the top nozzle of a fuel assembly prior to lifting it upwardly out of the reactor core.

Abstract: Apparatus for charging a nuclear reactor disposed at the bottom of a pool. The reactor is constituted by a plurality of tiers of combustible assemblies having different stages of enrichment, each assembly having combustible rods and an auxiliary cluster associated with the particular tier of the assembly. The apparatus comprises a rolling bridge supported for movement in a plane above the pool, and carrying a turnable platform which supports a plurality of vertical telescopic manipulation arms arranged in angular spaced relation thereon. Each arm carries a respective grappling unit for respectively engaging a complete combustible assembly or at least one type of auxiliary cluster. The auxiliary clusters may include control clusters, sealing clusters and poison consumable clusters.

Abstract: A head equipment support structure system (HESS) (10) particularly adapted to be cooperatively associated with a nuclear reactor vessel (12) for purposes of effecting a separation of the electrical cables (30) that are utilized in the head area of such a vessel (12), as well as for purposes of providing support for these cables (30). The subject HESS (10) which is in the form of an integral structure that is removably supported relative to the vessel (12) combines the features of cable support structure, missile shield, and cooling ductwork support structure. The HESS (10) embodies horizontally disposed multiple decks (14) to which the cables (30) are vertically routed from the reactor vessel head. The decks (14), which are located in vertically spaced relation directly above the reactor vessel head, support and separate the cables (30).

Abstract: Remotely assemblable and disassemblable fuel assembly comprising a mechanical structure constituted by an upper plate, a lower plate and a plurality of brace rods extending between the said plates, and a plurality of elongated fuel elements fixed to the brace rods by gratings, one of the ends of each brace rod being irremovably fixed in the upper plate, the other end of each brace rod being fixed to the lower plate by a system of remotely assemblable and disassemblable assemblies, wherein the said system of assemblies comprises a thread made at the end of each brace rod, a screwing member having a thread able to cooperate with the thread on the brace rod and a head having a plug hole and on its periphery at least one chamfer, as well as machining in the lower plate, constituted by a bore having a larger diameter portion issuing into the outer face of said plate, said larger diameter portion being surrounded by a flange shaped by cutting in the plate and which is separated from the remainder of the plate by an

Abstract: A contaminating product is packaged within a leak-tight sheath and transferred through a lock-chamber which is rigidly fixed to a leak-tight partition-wall. The device comprises a sleeve having a central cavity for establishing a communication between the lock-chamber and the sheath while ensuring tightness against outleakage to the environment. A seal plug having a double wall is placed within the cavity for preventing said communication. The seal plug and the sleeve are cut simultaneously in order to close-off the lock-chamber and the sheath separately by means of each wall of the seal plug.

Abstract: A device for use in handling nuclear elements, such as control rods, fuel elements and blind rods in a nuclear energy plant, comprises, a hoist having a gripper rod assembly, which includes a tubular column structure into which is engaged a top movable part which is adapted to be connected to a lifting cable. The top movable part carries a crossbar which is engaged by engaging members which are pivotally mounted within the tubular column structure of the gripper rod assembly and which have pin elements thereon which, when the engaging members are positioned inwardly, engage in recesses between teeth defined on the crossbar.

Abstract: Handling device for a fast neutron reactor cooled by a liquid metal such as sodium and of the type comprising a container with a vertical axis containing the core and a given volume of sodium contained in said container, defining above the core a free level surmounted by an inert gas cushion, a thick horizontal slab placed above the gas cushion and constituting the upper closure of a protective caisson surrounding the container, an inclined ramp which passes into the container up to a loading and unloading station located in the vicinity of the core and extending at its opposite end into a handling chamber supported by the slab, a second inclined ramp connecting the inside of the handling chamber to a second loading and unloading station positioned externally of the caisson in a storage container, a carriage carrying a handling pot able to move along the said ramps and moving the pot from a position where it is submerged below the sodium level to a position where it is introduced into the inert gas atmosphere

Abstract: Apparatus for introducing a fuel element into a fuel assembly is constituted by a plurality of vertical fuel elements and a structure for fixing said fuel elements, whereby the fuel elements have a positioning given by the fuel assembly and has an introduction plate fixed to the upper face of the fuel assembly. The plate has a plurality of orifices for the passage of a fuel element, the orifices positioning the fuel elements in the fuel assembly. A tool grips a fuel element for introduction thereof into a fuel assembly. Lifting means moves the tool in horizontal displacements between a storage rack for the fuel elements and one of the orifices of the introduction plate.

Abstract: Device for transporting radioactive material having a lifting mechanism displaceable along a travel path, includes an operator's cab shielded against radiation and displaceable with the lifting mechanism along the travel path, a control console for actuating the lifting mechanism, the control console being disposed in and displaceable with the cab, filter means through which the cab is ventilated with filtered air, and means for testing the ventilating air for freedom thereof from radiation.

Abstract: Paraseismic device for a handling hood of a nuclear reactor, comprising an enclosure with a vertical axis connected to a lock communicating with a passage provided in a slab located in the upper part of the reactor.According to the invention the device comprises, mounted between enclosure and lock, an elastic joint permitting the enclosure to perform a gimballing movement around a center located on the vertical axis of the lock, and regulatable tension tie attachment means disposed between the hood and the slab and distributed regularly about the vertical axis, each of said means having an attachment point on the hood disposed in the vicinity of a horizontal plane passing through the center of the ball and socket joint.Application to any power or experimental reactor.

Abstract: The proposed device for the removal of fuel assemblies and control and safety system cans from the core of a nuclear reactor comprises a hollow bar, wherein there is installed a main grip adapted for axial movement relative to the bar. At the end of the hollow bar, which faces an element to be withdrawn, there is mounted an auxiliary grip. The internal diameter of the hollow bar is selected so that the latter can envelop the elements being removed from the reactor's core. The length of the bar is selected so that the auxiliary grip can reach the jammed end of an element being withdrawn from the core, while the main grip holds the head of the element.

Abstract: The proposed gripping means for fuel assemblies of a nuclear reactor comprises a housing, whereupon there is movably mounted a slider provided with longitudinally extending slots to receive gripping jaws whose tails are pivotably secured to the housing of the gripping means. On one side, the end faces of the longitudinally extending slots are slanted with respect to the longitudinal axis of the gripping means and come in contact with the teeth of the gripping jaws provided on the end which is opposite to the tail, whereby the jaws open as the slider and housing of the gripping means moves relative to each other so that the teeth are received in an internal groove provided in the head of the fuel assembly.

Abstract: The proposed nuclear reactor comprises fuel assemblies whose heads are shaped as prisms and provided with an internal hollow for the working member of the gripping means to grip and handle the fuel assembly. The gripping means is accommodated in a guide member of a refuelling device having an end face shaped as a truncated cone whose vertex is directed towards the head of a fuel assembly being handled. Recesses are provided in the end faces of the fuel assembly heads. The number of recesses is equal to that of fuel assemblies adjacent to the fuel assembly being handled. The recesses are arranged symmetrically with respect to the face edges of the fuel assembly heads. The sides of the recesses next to the recess which is adjacent to the recess of the fuel assembly being handled and facing the fuel assembly being handled all form parts of the surface of a truncated cone whose axis is matched with the longitudinal axis of the fuel assembly being handled.

Abstract: A fuel bundle positioning and ejecting apparatus comprising two piston members, one slidable along a stem on the other piston member, and a compression spring urging the pistons apart, is secured in a horizontally extending fuel channel upstream of the coolant flow therealong. The downstream one of the piston members has a shield plug attached thereto and the piston members are urged together in a fuel channel with he compression spring compressed, by a series of fuel element bundles along the fuel channel. When the downstream end of the fuel channel is opened using a fuelling machine, with pressurized coolant therein and continued circulation of coolant along the fuel channel, the compression spring expands causing the piston members to become entrained in the coolant and urge the fuel element bundles out of the fuel channel and into the fuelling machine.

Abstract: The proposed gripping means of a refuelling machine for a nuclear reactor is arranged in a manipulator tube of the machine. Longitudinally extending grooves are provided on the internal surface of the manipulator tube. The gripping means comprises a housing which accommodates a slider with thrust pins which are in contact with the longitudinally extending grooves of the manipulator tube. A working member is secured at one end of the slider. At the opposite end of the slider there is provided a hole to receive a spherical lug provided on a rod. The latter is mounted on the housing of the gripping means and is driven by the machine's drive. The spherical lug of the rod is in contact with the surface of the slider, thus forming an articulated joint, whereby the slider is mechanically coupled to the rod.

Abstract: Disclosure is made of a gripping mechanism which comprises a casing mounted on the housing of the gripping mechanism and displaceable with respect to the housing. One end face of the casing interacts with a spring arranged on the housing, whereas the other end face of the casing carries a cap whose shape corresponds to that of the contact surface of a fuel assembly's head. The length of the casing is selected so that when the head of a fuel assembly is gripped by gripping jaws pivotably mounted on a slider accommodated in the housing, the end face of the cap comes into contact, under the action of the spring, with the contact surface of the fuel assembly's head, thus forming a closed circuit for passage of the cooling medium through the cavity of the slider and casing and through the head of the fuel assembly into the fuel assembly.

Abstract: Two guide ramps for the transfer of fuel assemblies in sliding motion between the reactor core and an external storage container are surmounted by a lock-chamber in which two pivotally suspended rectilinear rail sections carried by a revolving unit form guide ramp extensions. Each rail section has a lever extension in cooperating relation with a rocking system for displaying the rail section in swinging motion from an inclined position in the line of extenson of one of the guide ramps to the vertical position and conversely.

Abstract: Two carriages which can be displaced independently of each other in vertical translational motion are guided by means of slideways secured to a rotatable vertical body, the upper end of which passes through the rotating shield plug of the reactor. Each carriage has a horizontal arm and grab for handling fuel assemblies, the arms being maintained parallel to each other.

Abstract: The proposed system for handling fuel assemblies of a nuclear reactor comprises a sealed chamber housing a recharging machine comprising a carrier tube, wherein there is arranged a manipulator tube interacting with a reduction gear. Inside the manipulator tube there is a grip suspended on a chain interacting with another reduction gear. Extending through an opening in the cover of the sealed chamber is a vertical rotary tube with a bracket mounted thereon. The carrier tube is suspended on the bracket. Installed in the wall of the sealed chamber are inductive transmitters of the manipulator tube position. The system further includes three drives located outside the sealed chamber, of which two are kinematically coupled to the reduction gears, respectively. The third drive is kinematically coupled to the vertical rotary tube and turns the tube through a prescribed angle.

Abstract: The proposed manipulating means comprises a sealed housing, wherein a gripping means is arranged to grip a fuel assembly being transferred. The gripping means is coupled to a drive having a chain which is in contact with a sprocket mounted on an axle arranged in the sealed housing. The driving force of the drive is transmitted to the gripping means. The driving force is controlled by a force regulator mounted on the gripping means. The force regulator comprises two force transducers mounted on the sealed housing, and a spring suspension member installed in the gripping means. Some clearance is allowed where the drive sprocket axle is secured in the walls of the sealed housing. The ends of the axle extend outside the sealed housing and are coupled to sensitive elements of the force transducers.

Abstract: A system for recharging fuel assemblies of a nuclear reactor, comprising a hermetically sealed chamber on whose bottom there is placed a movable platform of a recharging machine which charges the reactor with new fuel assemblies, removes spent fuel assemblies from the reactor, and transports spent fuel assemblies from the reactor to a place of storage, as well as new fuel assemblies from the place of storage to the reactor. In the bottom of the hermetically sealed chamber there are provided channels through which it communicates with an intermediary distribution chamber arranged in the reactor vessel and the places for storing spent and new fuel assemblies. Between the channels of the reactor vessel and the channel of the container for storing spent fuel assemblies, i.e.

Abstract: Automatic apparatus for loading a predetermined amount of nuclear fuel pellets into a nuclear fuel element to be used in a nuclear reactor. The apparatus consists of a vibratory bed capable of supporting corrugated trays containing rows of nuclear fuel pellets and arranged in alignment with the open ends of several nuclear fuel elements. A sweep mechanism is arranged above the trays and serves to sweep the rows of fuel pellets onto the vibratory bed and into the fuel element. A length detecting system, in conjunction with a pellet stopping mechanism, is also provided to assure that a predetermined amount of nuclear fuel pellets are loaded into each fuel element.

Abstract: Disclosure is made of a device for recharging a fast-neutron reactor, intended for the transfer of fuel assemblies and rods of the control and safety system, having profiled heads to be gripped on the outside. The device comprises storage drums whose compartments for rods of the control and safety system are identical to compartments for fuel assemblies. In order to store and transport rods of the control and safety system from the storage drums to the recharging mechanism provision is made for sleeve-type holders. When placed in such a holder, the dimensions of a rod of the control and safety system are equal to those of a fuel assembly. To join a holder to a rod of the control and safety system, on the open end of each holder there is mounted a collet, whereas on the surface of each rod of the control and safety system, close to its head, there is provided an encircling groove to interact with the collet.