Abstract: Spent nuclear fuel storage casks, particularly a protective and venting cover for such storage casks which are stored above-ground. The protective and venting cover may be assembled from annular or doughnut-shaped cast concrete members stacked one upon the other. The annuli are axially indexed with respect to the storage cask, such that a venting annulus is formed about the storage cask and the annulus contributes to a defocusing geometry against armor piercing weapons, such as anti-tank "shaped charge" weaponry.

Abstract: The specification describes a container for spent nuclear fuel rods. The basket of the container comprises a plurality of stacked interlocking grid storage assemblies having an "egg crate" structure. The interlocking grid assemblies have radial tab extensions that extend through an intermediate shell and are affixed to an outer casing. The intermediate shell and the outer casing provide double containment, and the radial tab extensions provide heat sinks for transfer of heat from the storage grid assemblies to the exterior of the container.

Abstract: There is provided a method of transporting a nuclear fuel substance capable of increasing an amount of storing the nuclear fuel substance of a transport vessel by lowering the neutron effective multiplication factor by arranging neutron absorber plates among a plurality of nuclear fuel storing drums for storing the nuclear fuel substance, or at the inside of the respective nuclear fuel storing drums in transporting the nuclear fuel substance.According to the present invention, in transporting the nuclear fuel substance by containing a pile of the plurality of nuclear fuel storing drums in series for storing the nuclear fuel substance in the transport container along the vertical central axis of the transport container having substantially the bottomed cylinder shape, the neutron absorber plates each including a component for absorbing neutrons are interposed among the respective nuclear fuel storing drums on planes orthogonal to a vertical central axis of the transport container.

Abstract: A neutron absorbing apparatus which includes two adjacent neutron absorbing plates and a mounting assembly with latching means configured to be easily secured to fuel assemblies while the fuel assemblies remain under water in a fuel storage rack, thereby eliminating the need to remove the fuel assemblies or the fuel storage rack for installation. The two neutron absorbing plates are positioned orthogonally to form a chevron cross section which can be placed about the fuel assemblies by insertion in the existing space between the fuel assemblies and the cell walls of a fuel storage rack. A prescribed orientation of the chevron configured neutron absorbing plate in the cells of the fuel storage rack together with the selected use of a single neutron absorbing plate economically provides sufficient neutron absorption in all radial directions about the fuel assemblies to maintain safe storage conditions in closely packed fuel storage racks.

Abstract: The invention relates to a capsule for the containment of spent nuclear fuel, wherein the capsule has a cylindrical part which comprises a steel cylinder tightly embraced by a copper layer whose thickness is of the same order as the thickness of the cylinder wall. The copper layer is a continuous layer applied electrolytically over the outer surface of the steel cylinder and has an homogenous grain structure. The invention also relates to a method of producing capsules for the containment of spent nuclear fuel, wherein a steel cylinder of predetermined length and diameter is placed as a cathode in an electrolytic cell containing a copper salt solution as electrolyte. An electric current whose strength is effective in precipitating copper is passed through the cell to the steel cylinder via one or more anodes, while rotating the cylinder, until a copper coating of predetermined thickness has been formed on the outer surface of the cylinder.

Abstract: A sealing system for the engagement of a container (24) beneath a melting pot containing a molten material, comprising a shell (30) surrounding a nozzle (40), the nozzle being located in the axis of the neck of the container and permitting the pouring of the material from the melting pot into the container. The shell (30) has tight connection means with the nozzle (40), a base (32) having a bearing surface for the reception of a corresponding bearing surface on the container neck and at least one bellows (33, 34) surrounding the nozzle and connecting the tight connection means to said base, the bellows being able to render the shell retractable along the nozzle axis, means for introducing a gas flow between said bearing surfaces being provided in order to permit the circulation of part of said flow towards the nozzle.

Abstract: An article, such as a containment system (10), having sides (12) with walls (2) or (24) is made; in one method by using cast, cooled, melted, radioactive metal components where the melted metal has a specific activity over 130 Bq/g; or by providing a contaminated material in the form of a solid, liquid or mixture, and then mixing the contaminated material, to which no more than about 15 weight % of uncontaminated material has been reacted, with a binder, followed by forming the composition into a containment system and then curing it into a mass which contains both contaminated material, and uncontaminated binder acting as a matrix for the contaminated material. This article need not be a containment system but can be a wide variety of objects which are made out of radioactive waste, hazardous waste, and their mixtures.

Abstract: A method and apparatus for generation of electricity from packages of spent-fuel rods either on a remote site or in a permanent underground waste repository. It can also be applied to abandoned deep mines with high temperatures. Also many low-temperature geothermal reservoirs can generate electricity economically. Each individual fuel rod assembly is estimated to produce about 8 kilowatts and the total assemblies in the United States can generate about 63 megawatts of heat. Although this energy cannot be used to generate steam, it is harnessed in the invention by inducing ventilation in shafts constructed as part of an underground mined facility or by installation of ventilation chimneys at reactor sites. Natural ventilation phenomena has been observed and historically used to supply air in mines. It is also the same process that makes chimneys work in fire places and industrial furnaces.

Abstract: A shielded rack loader makes use of a loading rack movable between a shielding structure and a storage tube. A shield plug seals the storage tube. A hoist moves the shield plug and the loading rack. A shield plug cart and a material transfer cart mate with receiving flanges of the rack loader and permit temporary storage and movement of the shield plug and of canisters of transuranic material.

Abstract: A transport/storage container holding spent radioactive fuel elements is cooled by withdrawing gases from inside the container to create a subatmospheric pressure therein, feeding coolant water from a reservoir into the container, withdrawing steam from the container, and condensing the steam outside the container into condensate water. A common pump is used both to withdraw gases and steam from the container. The steam is condensed by contacting it with water drawn from the reservoir. In addition the water drawn from the reservoir is passed countercurrent to the steam in a condenser and the condensate water is fed back to the reservoir.

Abstract: The disclosure relates to packaging and storage containers suitable particularly for the packaging and storage, with optimum filling, of remote-handled hazardous waste; a process for filling the containers; and the implementation of the process for the packaging and storage of compacted nuclear waste. The containers are equipped inside, along one or more axial walls, over substantially the whole of their height h, with locking elements capable of undergoing elastic radial deformation on direct contact with the products introduced therein, the locking elements allowing the introduction and movement of products inside the containers only when force is applied to the products.

Abstract: An installation, designed to stock both nuclear fuel assemblies of square section and control bars of cruciform shape taken from a boiling water nuclear reactor, comprises vertical housings of square section, each able to accommodate a control bar and four assemblies. The housings are formed in and between encasing tubes (22) which rest upon a lower plate (10). After placing a control bar in the housing, a removable unit (30) is inserted which comprises a baseplate (34) surrounding the tip of the bar, four holders (32) resting on this baseplate, and spacer wedges (36) separating the holders. One assembly is then placed in each holder (32).

Abstract: A nuclear fuel assembly storage rack comprising a plurality of identical juxtaposed elongated mutually parallel tubes forming cells for receiving the assemblies. The cells having walls made of a material containing a neutron absorbing element. The tubes being straight and in mutual contact in the lengthwise direction to form a compact bundle which is held together by one or more straps distributed along the length of said bundle.

Abstract: A storage cage for the storage and transport of a plurality of fuel assemblies includes a baseplate having apertures formed therein. A plurality of casings each have an interior and each stand on the baseplate for receiving and storing a fuel assembly. Each of the casings is associated with at least one of the apertures leading into the interior of the casing for supplying and discharging cooling liquid. Each of the casings has a plurality of slots formed therein for supplying and discharging cooling gas. At least one supporting wall forms a load-bearing part with the baseplate and the casings are fastened to the at least one supporting wall.

Abstract: A dry transfer system for spent nuclear fuel (SNF) assemblies includes a transfer container with a sliding sleeve for vertical translation therein. The sliding sleeve includes a number of compartments for receiving a corresponding number of fuel assemblies. The container includes an integral and remotely controllable hoist with a number of individually actuated grapples for latching onto a corresponding number of fuel assemblies. The system further includes a loading stand with an elevator for raising and lowering a fuel basket that also includes a number of compartments for moving fuel assemblies up to and in alignment with the sleeve of the transfer container that is landed on the loading stand.

Abstract: A basket for a cask for transporting, storing, and containing pressurized water nuclear fuel assemblies, including an internal assembly of sleeves has a plurality of sleeves arranged in a uniform pattern and secured within a cylindrical shell. Each of the plurality of independent sleeves being sized to secure and contain a fuel assembly. The internal assembly of sleeves includes a set of single sleeves centrally positioned in the basket, a set of corner sleeves including a single sleeve in each corner of the basket, and a set of double sleeves. An internal support structure is positioned within the basket and includes a cross-shaped central support element and four angle shaped corner supports. Neutron poison material for absorbing neutrons is secured to an inner wall of each of the plurality of sleeves for maintaining fission reactions within the basket below a critical level necessary to sustain a fission reaction.

Abstract: Apparatus for the underwater loading of nuclear materials into concrete containers employing heat removal systems includes a holding vessel and a cover. The holding vessel has a metal bottom and a metal outside wall which define an upwardly open cavity dimensioned to accommodate the concrete container while leaving a gap between the container and the outside wall. A cover covers this gap, while allowing access to the central open cavity of the container. Fasteners and seals fasten and seal the cover to the container and the holding vessel. A method for loading nuclear materials into such concrete containers, utilizing the apparatus of the subject invention, includes the steps of lifting the container into the steel vessel, lowering the cover into place, fastening and sealing the cover onto the container and vessel, and then lowering the container and vessel assembly into the water storage pool.

Abstract: The invention relates to a process for the treatment of natural apatites with a view to the use thereof for storing irradiated fuel elements.This process consists of contacting a natural apatite powder with an acid aqueous solution, e.g. dilute HNO.sub.3 or HCl for between a few seconds and 10 minutes.In this way, the physicochemical properties of the natural apatite are improved by modifying its surface composition in order to make it close to that of hydroxyapatite. This modified apatite can be used as a filling material in irradiated fuel element storage containers.

Abstract: The performance of a compact heat exchanger in which a flow of air is employed to cool a flow of water can be enhanced by spraying water as a fine mist into the stream of coolant air. The water droplets, preferably less than 100 microns in diameter, coat the heat exchanger surface on the air side of the heat exchanger and provide evaporative cooling. The preferred form of heat exchange surface has strip fins.

Abstract: A transport/storage cask for a radioactive material has an inner shell and an outer shell, and between the two shells, a gamma ray shielding layer and a neutron shielding layer are provided. The transport/storage cask also includes heat-conductive members which are provided so as to penetrate through the gamma ray shielding layer and the neutron shielding layer. The transport/storage cask for a radioactive material is capable of containing a radioactive material at an enhanced efficiency, exhibits excellent heat-conductive performance, and effectively shields gamma rays and neutrons.

Abstract: A dry transfer system for spent nuclear fuel (SNF) assemblies includes a transfer container with a sliding sleeve for vertical translation therein. The sliding sleeve includes a number of compartments for receiving a corresponding number of fuel assemblies. The container includes an integral and remotely controllable hoist with a number of individually actuated grapples for latching onto a corresponding number of fuel assemblies. The system further includes a loading stand with an elevator for raising and lowering a fuel basket that also includes a number of compartments for moving fuel assemblies up to and in alignment with the sleeve of the transfer container that is landed on the loading stand.

Abstract: Pressure vessels of nuclear plants are equipped with so-called pressure-vessel fittings for the purpose of receiving fuel assemblies. If a bulky part of that type is to be exchanged, very large transport containers for transporting to a location outside the nuclear plant are required. In order to ensure that smaller transport containers can be used, it is necessary to dismantle the bulky parts. In order to ensure that the dismantling operation can be carried out without complicated holding devices, provision is made for setting down an open transport container on the bottom of a water tank. A bulky part is inserted into the transport container and the bulky part projects a predeterminable amount above an end surface of the transport container. The bulky part is separated above the end surface through the use of a separating device disposed on the end surface of the transport container.

Abstract: A storage tank for radioactive fissile material solutions. The tank comprises at least one cell containing a radioactive solution and a solid neutron-absorbing material while preventing any risk of criticality. A network of substantially vertical tubes is arranged within said cell and metal walls completely separate the radioactive solution from the solid neutron absorbing material. Said tubes contain the neutron absorbing material and are located in compartments defined by the metal walls throughout the radioactive solution. Said tank occupies a reduced floor space.

Abstract: A neutron absorbing apparatus which includes two adjacent neutron absorbing plates and a mounting assembly with latching means configured to be easily secured to fuel assemblies while the fuel assemblies remain under water in a fuel storage rack, thereby eliminating the need to remove the fuel assemblies or the fuel storage rack for installation. The two neutron absorbing plates are positioned orthogonally to form a chevron cross section which can be placed about the fuel assemblies by insertion in the existing space between the fuel assemblies and the cell walls of a fuel storage rack. A prescribed orientation of the chevron configured neutron absorbing plate in the cells of the fuel storage rack together with the selected use of a single neutron absorbing plate economically provides sufficient neutron absorption in all radial directions about the fuel assemblies to maintain safe storage condition sin closely packed fuel storage racks.

Abstract: In a nuclear reactor fuel bundle packaging apparatus including a hollow cylindrical cask (22) and a basket liner assembly (23) receivable within the cask, the basket liner assembly including a plurality of laterally spaced disks (26) rigidly held by a plurality of tie rods (28), and a plurality of elongated hollow basket liners (33) extending through and fixed to the plurality of disks, each hollow basket liner (33) holding a nuclear fuel bundle assembly (10) having an upper tie plate (14), a lower tie plate (16) and a plurality of fuel rods (12) arranged in a substantially square array, extending between the upper and lower tie plates, the improvement comprising an oversized hollow fuel bundle channel (68) received over the fuel bundle assembly, the channel (68) having the same cross sectional shape as the basket liner (33) but sized to fit within the basket liner, the basket liner having at least one slot (74) formed in at least one side thereof at each disk, and at least one spring (72) mounted on the bask

Abstract: A basket for transporting, storing, and containing nuclear fuel assemblies having an assembly of sleeves with a plurality of sleeves arranged in a uniform pattern and secured within a cylindrical shell. Each of the plurality of independent sleeves being sized to secure and contain a fuel assembly. A plurality of alternating sleeves of the plurality of independent sleeves are configured to include an angular shaped separator element secured to each corner of each of the plurality of alternating sleeves. A sheet of neutron absorbing material is positioned between each of the plurality of alternating sleeves for maintaining fission reactions within the basket below a critical level necessary to sustain a fission reaction. A support element for positioning and securing the plurality of independent sleeves is secured within the cylindrical shell. A bottom plate is secured to the bottom of the cylindrical shell providing vertical support for the plurality of independent sleeves.

Abstract: An apparatus for removing and installing a reactor component, such as a circulating pump, by remote operation. The apparatus includes a handling mechanism for transporting various interchangeable containers and tools along a path between a position on top of the suppression pool and a position overlying the reactor component. The handling mechanism has a yoke assembly adapted to receive and support the trunnions of any container or tool, lifting screws for raising and lowering the yoke assembly and an arcuate rack mounted on the shield wall for rotating the yoke assembly around the circumference of the shield wall. A transition collar is latched onto the pump pressure housing. The transition collar has a valve at the top for closing off its interior. Seals arranged between the transition collar and pressure housing to ensure water-tightness.

Abstract: A method for dismantling bulky parts of pressure-vessel fittings of a nuclear plant and for receiving the dismantled parts presents difficulties with regard to radiation-proof handling. In order to solve that problem, a dismantling container which is set down in a water tank is used. The fittings to be dismantled are introduced into the dismantling container. Furthermore, a receiving container for the dismantled parts is inserted into the dismantling container. A dismantling manipulator is supported on the flange of the dismantling container. When the receiving container is full, the dismantling manipulator is moved to the side, the receiving container is extracted and its contents are transferred to a transport container.

Abstract: Disclosed is a transportation and storage assembly for transporting and storing nuclear fuel rod assemblies. The transportation and storage assembly includes a basket assembly (24) designed for failed nuclear fuel rod assemblies, or a basket assembly (122) designed for undamaged nuclear fuel rod assemblies. The basket assemblies (24, 122) are inserted into a canister (22). The canister (22) includes a shell (26) that receives and surrounds the basket assemblies (24, 122), and lids (28, 96) that enclose the shell (26). The basket assemblies (24, 122) include a plurality of apertured plates (36, 124) interconnected by structural members (42, 88) that maintain the plates (36, 124) in a spaced apart relationship, axially aligning the apertures (38, 126) in the plates (36, 124). In the basket assembly (24) for failed nuclear fuel rod assemblies, a container (44) is inserted into a row of axially aligned apertures (122), having a drain passage (104).

Abstract: The present invention provides a cask (10) for transport and short-term storage of spent nuclear fuel. The cask 10 includes a structural shell (14) defining a cavity (40) for receiving spent nuclear fuel. The shell is formed from an upper shell portion (16) formed of a first metal and a lower shell portion (18) formed from a second metal. The first metal utilized to form the upper shell portion has a higher load bearing strength than the second metal utilized to form the lower shell portion. A bearing surface is defined on the upper shell portion by trunnions (30) mounted within sleeves (32) secured to the upper shell portion. The trunnions (30) each define a bearing projection (160) that is engageable to enable hoisting of the cask, with the tensile and shear loads of hoisting the cask being transferred from the trunnions to the trunnion mounting sleeves, and thus to the upper shell portion of the structural shell.

Abstract: An article, such as a containment system (10), having sides (12) with walls (2) or (24) is made; in one method by using cast, cooled, melted, radioactive metal components where the melted metal has a specific activity over 130 Bq/g; or by providing a contaminated material in the form of a solid, liquid or mixture, and then mixing the contaminated material, to which no more than about 15 weight % of uncontaminated material has been reacted, with a binder, followed by forming the composition into a containment system and then curing it into a mass which contains both contaminated material, and uncontaminated binder acting as a matrix for the contaminated material. This article need not be a containment system but can be a wide variety of objects which are made out of radioactive waste, hazardous waste, and their mixtures.

Abstract: An alignment device is used with a spent fuel shipping container including a plurality of fuel pockets for spent fuel arranged in an annular array and having a rotatable cover including an access opening therein. The alignment device includes a lightweight plate which is installed over the access opening of the cover. A laser device is mounted on the plate so as to emit a laser beam through a laser admittance window in the cover into the container in the direction of a pre-established target associated with a particular fuel pocket. An indexing arrangement on the container provides an indication of the angular position of the rotatable cover when the laser beam produced by the laser is brought into alignment with the target of the associated fuel pocket.

Abstract: A shipping container is provided for a hexagonal nuclear fuel assembly including a top nozzle having a top end, an outer barrel, an external shoulder, and an inner barrel; a plurality of grids which support fuel rods; and a bottom nozzle having an internal shoulder within a recess, a spherical taper, and a bottom end. The container may include a housing, a support for the fuel assembly, a top nozzle holder secured to the support, plural grid supports secured to the support, plural clamping frames for clamping the grids, plural guide plates for guiding the fuel assembly between adjacent grid supports, and a bottom nozzle holder secured to the support. The top nozzle holder may include a shoulder holder for holding the external shoulder, an end holder for enclosing and holding the top end, and a shoulder clamp for clamping the shoulder holder to the support.

Abstract: The present invention provides a cask (10) for transport and short-term storage of spent nuclear fuel. The cask 10 includes a structural shell (14) defining a cavity (40) for receiving spent nuclear fuel. The shell is formed from an upper shell portion (16) formed of a first metal and a lower shell portion (18) formed from a second metal. The first metal utilized to form the upper shell portion has a higher load bearing strength than the second metal utilized to form the lower shell portion. A bearing surface is defined on the upper shell portion by trunnions (30) mounted within sleeves (32) secured to the upper shell portion. The trunnions (30) each define a bearing projection (160) that is engageable to enable hoisting of the cask, with the tensile and shear loads of hoisting the cask being transferred from the trunnions to the trunnion mounting sleeves, and thus to the upper shell portion of the structural shell.

Abstract: A skid for transporting a nuclear fuel transportation cask. The skid comprises a supporting member having parallel spaced-apart plates. The plates are aligned perpendicular to a longitudinal axis of the cask, include a semi-circular trough for mating with the cask, and are connected by longitudinal fins parallel to the longitudinal axis of the cask. The skid also comprises a retaining member including parallel spaced-apart plates. The plates of the retaining member are aligned perpendicular to a longitudinal axis of the cask, include a trough for mating with the cask, and are connected by longitudinal fins parallel to the longitudinal axis of the cask. The fins of the supporting member are spaced apart such that when the cask rests in the trough of the supporting member, the fins of the supporting member are aligned with elongate members of the cask neutron radiation shielding material to transfer the load between the cask and the skid.

Abstract: A device for storing cylindrical objects, such as small containers (14) containing radioactive material samples, includes one or more superimposed rotary racks (30, 30'). Each of the racks has circumferentially distributed cavities (32, 32') in which the objects are received. The cavities are radially outwardly open with respect to the vertical rotation axis of the racks (30, 30'). Moreover, their axis is inclined so as to intersect the rotation axis above the cavity. Thus, an accidental escape of the objects is prevented.

Abstract: A shipping container is provided for a hexagonal nuclear fuel assembly including a top nozzle having a top end, an outer barrel, an external shoulder, and an inner barrel; a plurality of grids which support fuel rods; and a bottom nozzle having an internal shoulder within a recess, a spherical taper, and a bottom end. The container may include a housing, a support for the fuel assembly, a top nozzle holder secured to the support, plural grid supports secured to the support, plural clamping frames for clamping the grids, plural guide plates for guiding the fuel assembly between adjacent grid supports, and a bottom nozzle holder secured to the support. The top nozzle holder may include a shoulder holder for holding the external shoulder, an end holder for enclosing and holding the top end, and a shoulder clamp for clamping the shoulder holder to the support.

Abstract: A system for cooling water from a spent fuel pool of a nuclear power generating plant. The system includes a heat exchanger in which a flow of air is employed to cool a flow of pool water. The performance of the heat exchanger is enhanced by spraying water as a fine mist into the flow of coolant air. The water droplets, preferably less than 100 microns in diameter, coat the heat exchange surface on the air side of the heat exchanger and provide evaporative cooling. The preferred form of heat exchange surface has strip fins.

Abstract: The invention relates to a volume delimitation tank (1) for preventing or limiting contamination of the surrounding liquid medium when working with contaminated parts. The volume delimitation tank (1) comprises a sack or channel which constitutes at least the substantially vertical walls (1a-d) of the tank and is made of a material which is capable of being folded, which is radiation-resistant, and resistant to puncture. The walls (1a-d) can be provided with fold notches (27) to obtain a well-defined folding when, for example, lowering at least one wall portion (1a-d) for passing objects out of the tank (1). The walls (1a-d) of the tank (1) are arranged at a bottom part (9). Cleaning equipment (16) is arranged inside the tank (1) for continuous cleaning of the contained volume.

Abstract: A shipping container is provided for a hexagonal nuclear fuel assembly including a top nozzle having a top end, an outer barrel, an external shoulder, and an inner barrel; a plurality of grids which support fuel rods; and a bottom nozzle having an internal shoulder within a recess, a spherical taper, and a bottom end. The container may include a housing, a support for the fuel assembly, a top nozzle holder secured to the support, plural grid supports secured to the support, plural clamping frames for clamping the grids, plural guide plates for guiding the fuel assembly between adjacent grid supports, and a bottom nozzle holder secured to the support. The top nozzle holder may include a shoulder holder for holding the external shoulder, an end holder for enclosing and holding the top end, and a shoulder clamp for clamping the shoulder holder to the support.

Abstract: A neutron absorbing apparatus which includes two adjacent neutron absorbing plates and a mounting assembly with latching means configured to be easily secured to fuel assemblies while the fuel assemblies remain under water in a fuel storage rack, thereby eliminating the need to remove the fuel assemblies or the fuel storage rack for installation. The two neutron absorbing plates are positioned orthogonally to form a chevron cross section which can be placed about the fuel assemblies by insertion in the existing space between the fuel assemblies and the cell walls of a fuel storage rack. A prescribed orientation of the chevron configured neutron absorbing plate in the cells of the fuel storage rack together with the selected use of a single neutron absorbing plate economically provides sufficient neutron absorption in all radial directions about the fuel assemblies to maintain safe storage conditions in closely packed fuel storage racks.

Abstract: A shielding container for the transport and storage of irradiated nuclear fuel elements has a cast-metal vessel provided with a radiation-shielding cover whose cylindrical flange is bolted to a shoulder of a seat in the mouth of this vessel and has a thickness of two to four times the thickness of a projection of this cover extending into the space of the vessel receiving the radioactive material. A further cover has a projection extending into the seat and a flange overlying and bolted to the vessel wall. The thickness of the latter flange is twice the thickness of the projection of the further cover and both covers define annular control compartments whereby the sealing effectiveness can be monitored.

Abstract: A tool set and a method of using those tools in combination is disclosed that are especially well adapted to the function of rearranging and/or replacing the control rods and fuel supports in a boiling water reactor. The tool set includes a grapple that is capable of simultaneously picking up both a control rod and its associated fuel support. A separate unlatching tool is provided for pulling the control rod's release handle in order to decouple the control rod from a control rod drive. A storage rack that may be mounted in the reactor pressure vessel is provided for storing a fuel support and a pair of control rods when the positions of selected control rods are being shifted about the reactor core area. In the method aspect of the invention, the unlatching tool is used to pull the control rod's release handle. Thereafter, the grapple lifts the control rod and its associated fuel support as a unit.

Abstract: A transport, storage, monitoring, and retrieval system for casks including intermediate storage of spent fuel rods from nuclear power plants. The system consists of a powered rail transport car which carries a cask standing on its end. A cross-ways traveling powered rail "under car" unit carries the rail transport car and loaded cask transversely on rails underneath to align with a bay rail which the powered rail car traverses to the cask storage location. Bridge cranes off-load the casks and with monitoring equipment perform remote cask inspections. Bay rails and a pair of cross-ways traveling "under car" units serve for movement of both the transport car and the bridge units. Casks are located automatically at specific addresses for inventory control and data logging of radioactive emissions. The system may operate remotely and cask conditions are monitored from automated retrieved collected at an off-site data base.

Abstract: A tank is disclosed for containing a liquid in which control rod drive shafts of a nuclear power plant are stored. The tank comprises a lower tank portion having a bottom and a tank wall extending outwardly from the bottom for defining a lower storage cavity of the tank. An upper tank portion having walls is removably attached to the lower tank portion for defining an upper storage cavity of the tank. A plurality of tubes are arranged in the lower tank portion for adaptably receiving the shafts for storage.

Abstract: A source capsule containing a radioactive isotope is put inside of an outer protective jacket or capsule and the outer jacket is sealed. The outer protective jacket is so designed that it can be reopened without disturbing the radioactive isotope source capsule contained therein. Thus, when it becomes necessary to recondition the source capsule, the inner source capsule can be removed from the outer protective jacket and it can be re-encapsulated in another outer protective jacket. There is provided an encapsulated radioactive isotope source which comprises an outer protective jacket in the form of a can having a side wall, an integrally formed bottom wall and an open upper end. A source capsule containing a radioactive isotope is received within this outer protective jacket. A jacket cap is received within the outer protective jacket so as to close the open end of the jacket, with the source capsule thus located within the outer protective jacket.

Abstract: Disclosed is a transportation and storage assembly for transporting and storing nuclear fuel rod assemblies. The transportation and storage assembly includes a basket assembly (24) designed for failed nuclear fuel rod assemblies, or a basket assembly (122) designed for undamaged nuclear fuel rod assemblies. The basket assemblies (24, 122) are inserted into a canister (22). The canister (22) includes a shell (26) that receives and surrounds the basket assemblies (24, 122), and lids (28, 96) that enclose the shell (26). The basket assemblies (24, 122) include a plurality of apertured plates (36, 124) interconnected by structural members (42, 88) that maintain the plates (36, 124) in a spaced apart relationship, axially aligning the apertures (38, 126) in the plates (36, 124). In the basket assembly (24) for failed nuclear fuel rod assemblies, a container (44) is inserted into a row of axially aligned apertures (122), having a drain passage (104).

Abstract: A container for disposing of low level radioactive waste and its detection comprises a container having a cylindrical side wall of an enlarged diameter and an enlarged height. The container has a bottom wall with its exterior periphery coupled to the lower edge of the side wall. The container also has an aperture through the center of the bottom wall with an upwardly extending cylindrical support of a reduced diameter and shortened height extending upwardly from the aperture of the bottom wall. A liner is formed of a flexible material. The liner is configured to fit interiorly of the side wall with its upper edges extending over the upper edge thereof. The liner has a lower face adapted to be positioned on the interior face of the bottom wall. The liner also has an upwardly extending cylindrical extension adapted to be positioned over the upwardly extending interior cylinder of the container.

Abstract: The present invention provides a cask (10) for transport and short-term storage of spent nuclear fuel. The cask 10 includes a structural shell (14) defining a cavity (40) for receiving spent nuclear fuel. The shell is formed from an upper shell portion (16) formed of a first metal-and a lower shell portion (18) formed from a second metal. The first metal utilized to form the upper shell portion has a higher load bearing strength than the second metal utilized to form the lower shell portion. A bearing surface is defined on the upper shell portion by trunnions (30) mounted within sleeves (32) secured to the upper shell portion. The trunnions (30) each define a bearing projection (160) that is engageable to enable hoisting of the cask, with the tensile and shear loads of hoisting the cask being transferred from the trunnions to the trunnion mounting sleeves, and thus to the upper shell portion of the structural shell.

Abstract: A transport and storage cask for spent nuclear fuel. A cask body having one open end receives a basket in such a manner so as to maintain a steady state gap between the cask body and basket. Centering keys on the cask body and basket provide the centering function. For ease of manufacture, the basket is formed from multiple layers of rowed carbon steel plates that have complementary grooves in their mating surfaces to form fuel cell channels when the plates are assembled together. Bands are attached together around the plates at narrowed diameter portions on the plates to hold the plates in their assembled position. The gap between the basket and cask body allows the cask to withstand a fire transient without transmitting heat from the fire into the basket.