Abstract: A storage rack for storing spent nuclear fuel assemblies using a minimum space of a storage pool. The storage rack includes a plurality of tubular cells with a plurality of moderating members of neutron-absorbing material coupled thereto, and a base member coupled to the tubular cells for supporting the tubular cells substantially perpendicular thereto. The tubular cells are constructed of a plurality of prebent panels forming side portions of the cells. At least one of the prebent panels form at least two of the side portions of at least two of the tubular cells which are diagonally arranged relative to each other.

Abstract: A shipping shim (30) for restraining nuclear fuel rods (11, 12, 13) in a nuclear fuel assembly (10) which accommodates varied sized gaps (g.sub.1, g.sub.2, g.sub.3, g.sub.4) between fueled and non-fuel bearing members in the fuel assembly.

Abstract: A radiation-shielding storage/transport container has a cast-iron vessel having an open end defining an end face, a steel ring engaging the end face and forming at least one annular seat, a weld unitarily bonding the ring to the end face, and a cover secured to the steel ring in the seat thereof. The cast-iron vessel is formed at its open end with an annular seat having a shoulder surface forming the end face. The weld is an aluminothermic weld that extends over the entire surface of the interface between the ring and the vessel. The ring is formed with two such seats and the cover includes an inner plug cover and an outer cover each in a respective one of the seats. The outer cover is of steel and a second peripheral weld connects the outer cover to the respective seat.

Abstract: A radioactive source is mounted at one end of a rod and a ball-shaped coupler is disposed at the other end of the rod. An apparatus for handling a plurality of radioactive sources respectively mounted at one end of a plurality of rods having a ball-shaped coupler disposed at the other end of each said rod includes a shaft having a canister at one end of the shaft and a clip at another position on the shaft. The canister defines a plurality of compartments for respectively receiving a plurality of said mounted radioactive sources. The clip defines a plurality of chambers for respectively receiving a plurality of the ball-shaped couplers. The rods are flexible and semirigid and the distance between the canister and the clip is such in relation to the distance between the radioactive source and the ball-shaped coupler on the rod that the rods must be flexed after the radioactive sources are received in the compartments in order to insert the ball-shaped couplers into the chambers of the clip.

Abstract: An arrangement for the underwater storage of environmentally hazardous waste, particularly radioactive or chemical waste, includes at least one secondary capsule (1) in the form of a cylindrical concrete body. The concrete body has a central, axially extending storage cavity (3). The cavity has the form of a shaft which is open at one end thereof and into which a waste-containing primary capsule (2) can be inserted, whereafter the open end of the shaft or cavity is sealed. Arranged in spaced relationship around the circumference of the concrete body (1) are a number of ballast chambers (4) which can be filled with water to varying degrees and the total, combined volume of the chambers is such as to enable the concrete body to be brought to a buoyant state, by emptying the chambers.

Abstract: The spent nuclear fuel rods stored in a wet pit are extracted dry and transported dry to a transport container for dry transportation to a storage area or treatment center. The spent nuclear fuel rods are withdrawn from the wet pit, held within a cask that may be selectively closed at the bottom and transferred while the rod is dry after it is removed from the wet pit and then positioned over a dry container with an open top for a dry transfer of each of the rods to the container. Between the container and the cask is a closure that includes a shield plug and a shielding base that supports the shield plug and allows the shield plug to be moved on guide rails to the position above the open top of the container where the shield plug may then be raised allowing the shielding base to be moved out of position on the rails and the shield plug lowered to close off the container.

Abstract: A storage frame for nuclear reactor fuel assemblies includes a base plate. A plurality of shafts stand erect on and are secured to the base plate. The shafts each have a substantially rectangular cross section and are disposed diagonally opposite one another in a checkerboard-type configuration. The shafts have longitudinal edges adjacent one another with an offset defining a gap therebetween. At least two connecting elements join at least some of the diagonally opposite shafts together along the longitudinal edges by spanning the gap. The at least two connecting elements include at least one first connecting element being associated with a respective pair of the longitudinal edges and have a high rigidity in a first direction parallel to the base plate. The at least two connecting elements also include at least one second connecting element being associated with a respective pair of the longitudinal edges and having a high rigidity in a second direction parallel to the base plate.

Abstract: A containment structure (1) for storage of nuclear fuel or liquids which have been in contact with nuclear fuel includes a concrete wall (3) and a concrete floor (2) with a corrosion resistant liner (5) fixed to and in contact with the walls and floor except at the junctions of the walls and floor at which the liner is curved to provide "soft corners" (7) to permit movement of the liner relative to the concrete walls and floor.The term "soft corner" as used in the context of the present specification denotes a region providing a gap or empty space or collapsible or compressible material, eg foam, between the stainless steel liner and the concrete walls and floor. Any collapsible or compressible material employed needs to be stable to the radioactive environment and for this reason it is preferred that a gap or empty space is employed.

Abstract: A tank especially suited for nuclear applications is disclosed. The tank comprises a tank shell for protectively surrounding the liquid contained therein; an inlet positioned on the tank for passing a liquid into the tank; a sump positioned in an interior portion of the tank for forming a reservoir of the liquid; a sloped incline for resting the tank thereon and for creating a natural flow of the liquid toward the sump; a pump disposed adjacent the tank for pumping the liquid; and a pipe attached to the pump and extending into the sump for passing the liquid therethrough. The pump pumps the liquid in the sump through the pipe and into the pump for discharging the liquid out of the tank.

Abstract: A process for dismantling equipment that is buried, unsheltered, at risk of contamination and possibly is irradiating, and a vessel for implementing this process. According to the invention, buried equipment at risk of contamination, for example, an off-line effluent pipe, is dismantled in sections under cover of a movable vessel (124) placed above the section to be dismantled (12, 14). The invention also concerns a vessel (124) that has a self-supporting structure built around a deck (126) equipped with an elongated central opening (148) giving access to the section to be dismantled (12, 14).

Abstract: A storage canister for spent nuclear fuel rods, having loading and storage configurations, has an open end and an apertured end wall, and means therein defining a plurality of rod locations. The canister also has movable means therein for vertically offsetting adjacent rods within the canister so that any pair of adjacent rods are vertically offset from each other. The movable means is positioned during loading to permit fluid flow into and out of the canister through the apertured end wall and in the storage configuration blocks at least one of the apertures in the end wall. The movable means may also be used to lift the fuel rods such that their tops extend above the canister body to permit removal of one or more rods. A closure member for the open end has a locking mechanism for locking it to the canister and a tamper indicating mechanism.

Abstract: The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps.

Abstract: In combination with a nuclear power generating facility including a composite fuel pool including a reactor cavity and a spent fuel pool fluidly connectable to the reactor cavity, the composite fuel pool at least partially containing a primary fluid, a nuclear reactor vessel positioned in the reactor cavity, a residual heat removal system installed in the facility and fluidly connectable to the reactor vessel, and a spent fuel pool cooling system installed in the facility and fluidly connectable to the spent fuel pool, a temporary cooling system is provided, comprising a primary heat exchange system including a primary heat exchanger for transferring heat from a primary fluid to a secondary cooling fluid. The primary heat exchanger is temporarily locatable in the facility, and is temporarily fluidly connected to the composite fuel pool.

Abstract: A container for nuclear fuel comprises a number of cells for receiving the nuclear fuel. The cells have removable lids and are disposed in a progressive manner in a parallel series relationship. A vent is provided between adjacent cells and an inlet for a pressurizing gas is located at the first cell. A valve at the last cell allows fluid to be discharged from that cell.

Abstract: The device (25, 26) comprises a tubular body (40) mounted axially movable on a flange (5) of a transport structure (4) for an object (6), a spring (36) for return of the tubular body (40) towards an unclamped position, an arrangement for manual displacement (19, 20, 16, 21) of the tubular body (40) between its unclamped position and a clamping position, carried by the flange (5), a rod mounted slidably in the axial direction of the tubular body (40) to a limited extent and carrying a shoe (14, 15), and a second spring for elastic return interposed between an abutment fastened to the tubular body (40) and the end of the sliding rod opposite the shoe (14, 15).

Abstract: The device comprises a cradle (4) having at least one supporting surface on which the object (6) rests, at least one flange (5) pivotably mounted on the cradle (4) and members (14, 16, 20) for locking the flange (5a, 5b) in its turned-down position. The device further comprises a bearing block (38) connected to the flange in an articulated manner, a shoe (40) mounted on the bearing block (38) for limited displacement and having two bearing surfaces (40a) directed towards the object (6), in the turned-down position of the flange, and a leaf spring (41) interposed between the bearing block (38) and the shoe (40).

Abstract: A spent fuel rack for storing fresh fuel assemblies, or spent fuel assemblies removed from a nuclear reactor, which includes a base plate having multiple cells of modular construction welded at their bottom ends to the plate. The cells are formed of L-shaped sections having walls which support neutron absorbing material, and the walls of one cell are common to the adjacent cells. The base plate includes openings primarily for receiving the bottom nozzle of a fuel assembly, but they further serve as access openings for apparatus used for leveling the base plate. There is also means for receiving and locking the engaging mechanism of lifting apparatus which means is wholly within the periphery of the base plate.

Abstract: Apparatus for locating a floatable platform, comprises upstanding support members arranged to be adjacent to an article submerged in a liquid, and extendible members depending from the platform. The extendible members on initial extension are arranged to locate on the support members, and further extension of the extendible members raises the platform from a buoyant to a partially-buoyant state. A laser device on the platform is arranged to scan a stationary coded target so as to determine the position of the platform.

Abstract: A flux trap neutron absorber arrangement for use in a fuel storage body between a pair of fuel storage cans which receive and store nuclear fuel assemblies includes separate pockets spaced from one another and extending vertically along and attached to the exterior of each of the adjacent side walls of adjacent spaced storage cans, an elongated flat plate of a thermal neutron absorber material mounted in each pocket, the plates of thermal neutron absorber material being likewise spaced from one another and defining a fast neutron slow-down region therebetween, a slab of a metal hydride disposed in the fast neutron slow-down region between the plates of thermal neutron absorber material and the separate pockets on the adjacent side walls, a canister containing the slab of the metal hydride being disposed in the fast neutron slow-down region, the canister being connected to at least one of the adjacent side walls of the adjacent storage cans.

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: A method and an apparatus for the disposal of low-level radioactive wastes are disclosed. Under the disclosed method, the waste is first introduced into a preconstructed multipurpose container which comprises a polyethylene inner container disposed within an outer concrete shell. Processing of the waste is carried out within the multipurpose container. The filled container is then transported to a disposal site, followed by storage of the waste at the storage disposal site.The claimed apparatus comprises an empty multipurpose storage container for use in the method. The multipurpose container is adapted for receiving and storing low-level radioactive waste, and comprises a polyethylene inner container disposed within an outer concrete shell.

Abstract: A process for the continuous disposal of radioactive waste is disclosed. The process involves (a) separating materials contaminated with radionuclides into categories containing radionuclides with similar half-lives; (b) accumulating radioactive materials for each category in containers over a predetermined time interval; (c) sealing the containers and storing them until the radioactivity is reduced to safe levels; (d) disposing of the material as conventional waste; and (e) repeating steps (a) through (d) with a new batch of material. The method can be practically used to process radioactive wastes having half-lives of up to 50 years.

Abstract: A nuclear reactor system pressure vessel comprises a steel inner liner part, an intermediate insulative layer part and an outer pre-stressed concrete part encasing these parts. Use of the pre-stressed construction allows for construction of pressure vessels of larger size than heretofore, and this coupled with utilization of squatter reactor cores allows natural convective circulation in the reactor vessel of the heated water pool in the higher capacity systems currently being introduced. The reactor pressure vessel because of its suitability allows enhanced natural steam separation in the vessel and eliminates need for use of centrifugal steam separators. The outer vessel part can be a cast single piece structure or it can be an integrated concrete segment assembled structure embodying pre-stressing tendons arranged in various orientations to effect pre-stressing.

Abstract: The apparatus of the present invention is a plate of neutron absorbing material. The plate may have a releasable locking feature permitting the plate to be secured within a nuclear fuel assembly between nuclear fuel rods during storage or transportation then removed for further use or destruction.The method of the present invention has the step of placing a plate of neutron absorbing material between nuclear fuel rods within a nuclear fuel assembly, preferably between the two outermost columns of nuclear fuel rods. Additionally, the plate may be releasably locked in place.

Abstract: A fail-safe storage rack is provided for interim storage of spent but radioactive nuclear fuel rod assemblies. The rack consists of a checkerboard array of substantially square, elongate receiving tubes fully enclosed by a double walled container, the outer wall of which is imperforate for liquid containment and the inner wall of which is provided with perforations for admitting moderator liquid flow to the elongate receiving tubes, the liquid serving to take up waste heat from the stored nuclear assemblies and dissipate same to the ambient liquid reservoir. A perforated cover sealing the rack facilitates cooling liquid entry and dissipation.

Abstract: Gamma radiation leaving the surface of a radioactive materials storage vessel is measured and monitored using a plurality of gamma ray absorbing calorimeters. The gamma ray energy absorbed is converted into heat and such heat is measured or indicated for the purpose of monitoring expected radioactive decay processes of the stored radioactive materials. Material leakage or removal from storage is detected and defined by deviations from the normal expected decay in gamma radiation. Such deviation or lack of deviation, as the case may be, provide the desired accountability of the radioactive materials. Since there can be several bands of gamma ray radiation, both flux and its energy level may be determined by using different gamma absorbing materials in the calorimeters selected for the known possible energy levels of the decaying radioactive material.

Abstract: The fixed structure (10) incorporates an abutment surface (10a) upon which a corresponding abutment surface (8a) of the transportable element (1) comes to bear, with the interposition between the abutment surfaces (8a, 10a) of at least two concentric annular sealing joints (13a, 13b). The pressure in the space (18) between the sealing joints (13a, 13b) and bounded by the abutment surfaces (8a, 10a) is measured during the emplacement of the transportable element (1) to determine whether it is leakproof. The measured maximum pressure and/or the variation of pressure measured over time is compared with predetermined values corresponding to a correct emplacement of the transportable element (1).

Abstract: A nuclear fuel rod consolidation structure. A storage canister has a grid structure positioned in its interior. The grid structure is provided with a plurality of hexagonally shaped individual cells in a triangular pitch array. This provides nearly a two to one consolidation ratio. The grid structure provides positive radial support to the fuel rods to maintain the triangular pitch array if the canister is not fully loaded or some of the fuel rods are removed. The positive guidance allows use of the existing rod pulling device for loading fuel rods into the structure.

Abstract: A container for material contaminated with a toxic substance or a radionuclide has a base with recesses. A highly absorbent cementitious material is disposed in the recesses for absorbing any liquid in the container. The cementitious material is made by mixing together a sodium bentonite clay slurry and a cement slurry at a water/solids ratio of about 1.5/1. Subsequent heating of the mixture removes capillary water without substantially dehydrating any hydrated cement.

Abstract: A method for the long term storage of radioactive hazardous waste in a hollowed out chamber of salt bed in which sealed, relatively incompressible containers of hazardous materials are immobilized in a regular spaced array with the remaining space in the chamber filled with a granular compressive load equalization medium.

Abstract: A spent nuclear fuel storage bridge comprising either a stationary or mobile structure supported from the walls of a spent nuclear fuel storage pool. The structure may have either a pivotally mounted or non-pivotally mounted lower basket or cage portion which occupies a region of the vertical space between the pool water surface and the existing pool floor supported fuel storage racks. Using the bridge, at least a ten-foot deep barrier of biological shield water and at least a two-foot space between the top of the existing racks and the bottom of the bridge can be maintained in a storage pool of typical geometrics and dimensions. By limiting the height of the basket portion of the bridge, up to a three-foot space beneath the biological shield water may be provided to accommodate underwater horizontal transference of spent fuel storage canisters to and from the bridge. The width of the basket portion is determined by the spent fuel length and the resulting storage canister length.

Abstract: The transfer cupboard (1) comprises a solid body (2) made of a radiation-absorbing material, in which is provided an axially directed receptacle (3) for receiving the assembly (4). The cupboard (1) comprises at least one circuit (15) for cooling the assembly (4) by gas and integrated in the body (2) of the cupboard (1). The cooling circuit comprises at least one main axially directed gas-circulating channel (16) formed in the body (2) of the cupboard, at least one device (18) for the circulation of gas in the cooling circuit (15), and at least one device (17) for purifying the circulating gas, which are arranged in the vicinity of one end of the main channel (16). Two secondary channels (20, 21) formed in the body (2) of the cupboard make it possible to connect each of the ends of the main channel (16) to a corresponding end of the receptacle (3) for the fuel assembly (4), by which the cooling circuit is closed again.

Abstract: A cask basket construction for storing and transporting nuclear waste material, such as spent nuclear fuel assemblies or fuel rods. The construction is comprised of a plurality of individual storage cells for storing the nuclear material, with the plurality of storage cells rigidly affixed to one another to form a high strength, lightweight, unitary array of storage cells. Thermal loading elements positioned between walls of adjacent ones of the cells as well as a coolant flow is provided to transfer heat generated by the nuclear material contained in the storage cells to the outer portions of the cask basket construction. A heat path is included for dissipating the heat transferred away from the center of the array of storage cells. The thermal loading elements further serve as an integral structural component of the array for enhancing the structural strength thereof.

Abstract: A container for storing and transporting radioactive material is provided comprising: a vessel, having an upwardly open cavity for accommodating radioactive material; and a cap covering the top surface of the vessel to seal the cavity. The vessel and cap walls have a core of radioactive shielding material such as cementatious, concrete enveloped and isolated within a continuous metal lining. The metal lining allows the container to be held under water, improves the impact resistance of the container and forms a barrier in a geological disposal facility. The lower edge of the cap and upper edge of the vessel are welded together to seal the cavity. The vessel includes lifting lugs for lifting the vessel and container.

Abstract: A single canister process container for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining their integrity at temperature necessary to oxide the zirconium-based cladding. The process container also has means to introduce and remove fluids to and from the container.

Abstract: A detection unit (20) is moved under water inside the fuel storage pond (15), over the entire height and in the vicinity of a wall of the cell (2). The detection unit (20) comprises at least one probe for monitoring the thickness of the material. The probe readings are collected from a region (22) situated above the pond (15) and these readings are compared with reference measurements. The monitoring process makes it possible to verify the presence of the neutron-absorbing material in the side walls (10) of the cell (2).

Abstract: An apparatus for monitoring the pressure within a cask containing radioactive materials is disclosed. The apparatus comprises a differential pressure sensor sealingly connected to a bore that penetrates through the wall of the cask for directly monitoring the pressure of the helium gas contained within the cask and for providing a first barrier between the helium gas and the ambient atmosphere. An evacuated sensor chamber surrounds both the outlet end of the through-wall bore and the differential pressure sensor for providing a second barrier between the helium and the ambient atmosphere as well as a vacuum reference point for the differential pressure sensor. An absolute pressure sensor is connected in parallel to the through-wall bore to allow the system operator to determine whether or not a reduction in the pressure sensed by the differential pressure sensor is the result of a leakage condition in the cask, or in the evacuated sensor chamber.

Abstract: The present invention relates to the retrievable storage of high-level nuclear spent fuel (waste). Such waste, which generates heat as it decays, is packed in sealed containers (2) which are placed in a repository site comprising a tunnel or drift (5) in a geological rock formation (50) for permanent or long-term storage. Elongated, sealed cooling enhancement devices (7) are emplaced in boreholes (8) extending from the inside surfaces (16 a-b) of the drift (5) and carry heat from the location of the waste containers (5) to farther distances in the repository site. Applicable sealed cooling enhancement devices disclosed are heat pipes (7), thermal syphons (307), superconductor rods, and heat pumps (407).

Abstract: A method of evacuating a container to a vacuum for use in treating radioactive wastes by placing the waste into the container, evacuating, sealing off and thereafter compressing the container, the method being characterized by placing the waste into the container, forming over the waste a filter layer of particulate material fulfilling one of the following requirements: and sealing off and compressing the container.(1) A layer having a thickness of at least 5 mm and formed of a particulate material not smaller than 40 .mu.m to less than 105 .mu.m in mean particle size;(2) A layer having a thickness of D in mm and formed of a particulate material not smaller than 105 .mu.m to not greater than 210 .mu.m in mean particle size d in .mu.m, the thickness D and the mean particle size d having the relationship represented by:D.gtoreq.(20/105).times.d-15;and thereafter aspirating a gas through the filter layer from thereabove to evacuate the container and sealing off and compressing the container.

Abstract: A container for a radioactive material in which the cover is welded to the container by a dual weld disposed in a welding gap between the cover and the container wall, the gap having a bottom formed by opposed flanges on the cover and the wall. The root layer of the weld is formed by a tungsten electrode gas shielded arc welding process. A superimposed added layer is formed by a submerged arc welding process.

Abstract: A low cost, minimum weight cask for the storage of fuel assemblies is disclosed herein, along with a method for the construction thereof. The cask generally comprises a wall assembly for defining a cask interior that is complementary in shape to a rectangular array of radioactive fuel assemblies that is formed from four flat, metallic wall plate members having mutually parallel side edges which are adjoined be welds that penetrate only part way through the thicknesses of the wall plate members. The cask further includes a floor plate attached to the bottom of the wall assembly, and a lid that is detachably connectable to the top of the wall assembly. A basket assembly formed from parallel and uniformly spaced plates of borated aluminum interconnected in "egg crate" fashion is disposed in the rectangular interior of the cask. To minimize weight, each of the corners of the wall assembly is truncated.

Abstract: Apparatus for cutting a cruciform shaped radioactive control rod into three separate cut sections, the cruciform shaped radioactive control rod being of the type having four substantially equidistantly spaced sheaths extending from and along a large portion of the length thereof, each sheath containing at least one radioactive rod, and a velocity limiter at one end thereof, the apparatus including a first cutting device for cutting the velocity limiter away from the remainder of the control rod to form a first one of the cut sections; and a second cutting device for simultaneously cutting the remainder of the control rod along the lengthwise direction thereof and substantially transverse to the first cutting device, to form two chevron shaped sections as the remaining two of the cut sections.

Abstract: Provision is made for a container which stores and shields radioactive material. Included in the container is an enclosure defining a hollow chamber in which radioactive material is storable. A closure assembly cooperates with the enclosure in such a manner that an internal plug thereof effects a preselected gas-impervious sealing engagement. The closure assembly includes a lug which is rotatable to urge the assembly into sealing engagement and which torsionally fails following achievement of the desired sealing engagement of the closure plug to thereby prevent the lug from being subsequently used to open the container. The container and closure members provides desired radioactive shielding.

Abstract: A filling apparatus for the ordered, complete filling of a container with rods, such as spent nuclear fuel rods, in a hexagonally close-packed structure, includes a device for orderly positioning a first row of rods at predetermined positions in a container which has an opening formed in a side thereof opposite the positioning means and an interior with a given width. Two slides disposed one above the other can reach through the opening over the entire given width of the interior of the container. Each of the slides has depressions formed therein defining support teeth. The depressions define openings at predetermined positions for receiving rods of a row. The depressions in one of the slides is offset relative to the depressions in the other of the slides so that the support teeth in one of the slides covers the openings in the other of the slides when the slides are superimposed.

Abstract: A nuclear power plant that is of a walk-away type with an encapsulated reaction core in a glass matrix pool having a reactive Thorium/U.sup.233 composition in a containment structure that radiates thermal energy for use in a closed gas cycle with a split path having a common compressor with an output that divides into a first path communicating with the thermal source and a second path communicating with an intercooler, the two paths combining in a turbine with an expander that discharges to a common collector for return to the compressor.

Abstract: A transport and storage container for nuclear fuel elements comprises a vessel with a removable internal structure. The internal structure defines a plurality of elongate compartments to receive fuel elements and the walls of the compartments are formed by inter-engageable elongate rectangular plates disposed at right angles to one another. Spider assemblies arranged at intervals along the length of the structure hold the plates together.

Abstract: A stowage rack is disclosed for dry transport of nuclear fuel elements in a plurality of elongated, parallel, adjacent prismatic cells. The rack is formed from first and second sets of materials, the first set of materials fulfilling the function of mechanical strength and thermal conductivity, and the second set of materials fulfilling the function of neutron absorption. The stack may be formed entirely of materials fulfilling the function of mechanical strength and thermal conductivity, with the neutron absorption materials being provided within the walls of the cells. Alternatively, materials providing mechanical strength and thermal conductivity may be stacked alternately with materials providing neutron absorption.

Abstract: A tamper-proof closure 10 is inserted by means of positioning tool 20 into a nuclear fuel consolidation storage canister 30. The closure 10 includes a grooved weakened portion 44, which if it exceeds its elastic limit when the base 12 is flexed during removal attempts will indicate any attempts to remove or otherwise tamper with the thus closed canister. Locking tabs 18, on transverse legs 13 and 14 extending from base 12 are engaged in slots 40 in the wall of the opening of canister 30 when the closure 10 is in fuel storage position. Tool 20 has a portion 46 which enters a slot 48 in base 12 at 90.degree. to its working position and then twists to engage spanning portion 42's flanges 43 in slots of flanges 16 on the legs 13 and 14 to retract tabs 18. The base is prevented from flexing on insertion into the container opening by support it receives from portion 46.

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 shipping cask for transporting radioactive material is disclosed herein which comprises an inner vessel having metallic, heat conducting walls, a plurality of heat conductive, mutually parallel ribs, wherein the inside edge of each is connected to the outside surface of the heat conducting wall of the inner vessel, a layer of neutron absorbing cement disposed over the exterior of the inner vessel and between the mutually parallel ribs, and a plurality of flat circumferentially disposed fin members, each of which has two opposing and mutually parallel edges that are welded to the outer edges of two adjacent ribs. The flat circumferentially disposed fin members dissipate heat conducted through the ribs generated by radioactive material within the inner vessel, and further serve both to support and protect the brittle layer of cement, as well as to provide a watertight barrier thereover so that the cask may be submerged or otherwise exposed to water without absorbing any significant amounts.