Abstract: A system for handling a radioactive source includes a container containing a radioactive source and a cap mounted on the container to retain the radioactive source inside the container. The cap has a first locking structure and a second locking structure. The system further includes a handling tool having a support shaft, a first locking tip adapted to form a first lock with the first locking structure, and a second locking tip adapted to form a second lock with the second locking structure. The first and second locking tips are slidably coupled to the support shaft.

Abstract: A method and apparatus for transporting radiopharmaceuticals. Typically, the apparatus is a two-part assembly, each part having an exterior shell, a radiation shield and a non-porous lining. Additionally, the assembled apparatus has a sealed internal chamber suitable for carrying a syringe or a sharps container containing a syringe. The internal chamber of the radiopharmaceutical pig is lined with a non-porous lining, typically a durable plastic, that prevents contamination of the radiopharmaceutical doses, the radiation shield, or the environment. Additionally, the non-porous lining can be quickly and easily cleaned and sterilized, avoiding the often difficult, to impossible, task of cleaning and sterilizing the radiation shield of the radiopharmaceutical pig. The non-porous lining is surrounded by a radiation shield that is typically comprised of elemental lead. The radiation shield prevents radiation from the radiopharmaceutical from contaminating the user or environment.

Abstract: This invention deals with multi-component composite materials and techniques for improved shielding of neutron and gamma radiation emitting from transuranic, high-level and low-level radioactive wastes. Selective naturally occurring mineral materials are utilized to formulate, in various proportions, multi-component composite materials. Such materials are enriched with atoms that provide a substantial cumulative absorptive capacity to absorb or shield neutron and gamma radiation of variable fluxes and energies. The use of naturally occurring minerals in synergistic combination with formulated modified cement grout matrix, polymer modified asphaltene and maltene grout matrix, and polymer modified polyurethane foam grout matrix provide the radiation shielding product. These grout matrices are used as carriers for the radiation shielding composite materials and offer desired engineering and thermal attributes for various radiation management applications.

Abstract: The invention relates to a container (1) intended for transport/storage of radioactive materials, the container comprising a container body (2) and at least one handling device (8) mounted using attachment screws (38) in a base housing (30) delimited by a base housing wall (32). According to the invention, a sealing plate (50) covering the attachment screws is installed removably in a plate housing (52) delimited by a plate housing wall (56) provided on the handling device and by a portion (58) of the base housing wall. Furthermore a seal (66) is provided inserted between a peripheral wall (60) external to the plate and the portion (58) of the base housing wall, and a seal (74) inserted between a peripheral wall (68) external to the plate and the plate housing wall (56).

Abstract: Corner of each square pipe is molded into a terrace shape having steps. When a basket is constructed by these square pipes, steps of adjoining square pipes are assembled together face to face. Fuel rod aggregates are housed inside the square pipes and in a cells formed between the square pipes. Since the adjoining square pipes are assembled in a staggered arrangement, boundaries of the cells are defined by the walls of the square pipes itself.

Abstract: Heat conductive fins (107) are welded along both sides of a belt-like member (105a) with a margin left along edges of the both sides, thereby to form a unit (105c). The unit (105c) is welded to a body (101) with the heat conductive fins (107) from the outside of each fin. Next, another belt-like member (105b) is covered over a gap between adjacent belt-like members (105a, 105a), and these members are welded from the outside. With this arrangement, there is no need to weld in a narrow and long space and the entire welding step is carried out from the outside, which makes it easier to assemble a cask.

Abstract: The invention relates to a container system for the transport and storage of highly reactive materials, which comprises an outer container (1) that encompasses at least one inner container (2) in which the radioactive material is disposed. The inner container (2) is resiliently received in the inner container so as to absorb shocks. The outer container (1) comprises a cylinder (4) whose jacket (5) consists of prestressed reinforced concrete molded by centrifugal action and is provided with a lid (6) and a bottom pate (7) that consist of reinforced concrete. Like the outer container (1), an intermediate container may consist of prestressed reinforced concrete molded by centrifugal action and may encompass the inner container (2). Preferably, the concrete parts of the outer container (1) and the intermediate container (3) are provided with, e.g., boroxyde as an additional neutron absorber.

Abstract: A basket has a lattice-like section for accommodating individual used nuclear fuel in predetermined positions in a cask. The basket is made from aluminum composite material having good neutron absorption ability, excellent mechanical property and workability. The aluminum composite material is made by having, in an Al or Al alloy base phase, B or B compound with a neutron absorption ability and an additive element, e.g. Zr or Ti, for giving a high strength property, and subjecting to a sintering under pressure.

Abstract: In the metal billet to be used for hot dilation forming, a forward side with respect to the pressing direction has a quadrate section and its diagonal length is not more than an inner diameter of a container. Moreover, a backward side with respect to the pressing direction has a circular section and its diameter is substantially same as the inner diameter of the container. The metal billet is heated to a temperature suitable for press working and is set into a container for press forming. While a center of a workpiece of the metal billet is being bored by a boring punch to be operated by a pressing machine, the metal billet is hot-dilated so that a bottomed container for a cask is formed.

Abstract: Packaging system for radioactive materials having: a vial with closure for accommodating the radioactive material; a first casing to be opened, enclosing the vial, and essentially made from a transparent material, which has a capture cross-section selected for shielding at least a part of the emitted radiation; and a second casing to be opened, made from a material with a high capture cross-section (Z) for essentially shielding the remaining radiation, the second casing enclosing the first casing.

Abstract: A stainless steel slab containing B, wherein a protecting material is joined onto at least two faces across the bloom from each other in a stainless steel bloom containing B of 0.3–2.5 mass %, being integrated into one-piece by forming a weld metal comprising a stainless steel with chemical composition that satisfies the relationship expressed by following formulas (1)–(4), and a method to produce a steel product by rolling said slab. Further, it is preferable to interpose an insert material between above stainless steel bloom and above protecting material in bonding process. 15?Cr eq?30,??(1) 4?Cr eq?Ni eq?17,??(2) Cr eq=Cr+1.5 Si+Mo?5 B,??(3) Ni eq=Ni+30 (C+N)+0.5 Mn??(4) Herein, each symbol of a chemical element designates the content (mass %) of relevant chemical element contained in steel.

Abstract: A pharmaceutical pig is used to transport a syringe containing a liquid radiopharmaceutical from a radiopharmacy to a medical facility for administration to a patient. The pharmaceutical pig includes an elongate polymer cap that is removably attached to an elongate polymer base. The elongate polymer cap includes a cap shell that completely encloses a cap shielding element and the elongate polymer base includes a base shell that completely encloses a base shielding element. Preferably the polymer utilized for the cap shell and the base shell is polycarbonate resin, e.g., LEXAN®. An inner liner is not utilized and the cap shielding element and the base shielding element, which are preferably, but not necessarily, made of lead, are completely sealed and unexposed.

Abstract: A rotatable and replaceable plunger type multi-source radiator is provided for equipment correlation and radiation experiment. The rotatable and replaceable plunger type multi-source radiator comprising a radiation source rod, a rotatable radiation source selection device, staircases radiation aperture, radiation shields, and a mechanic operation arm for replacing radiation source. The plunger type rotatable and replaceable multi-source radiator of the present invention is capable of preventing radiation leakage and mutual interferences among radiation sources, providing precise positioning, safety operation, and simple replacement of radiation sources.

Abstract: It is an object of the present invention to obtain a containment concrete cask which has heat removal capacity maintained at the conventional level or beyond it and which prevents radiation from leaking to the outside. In a concrete cask, a shielding body composed of concrete and heat transfer fins made from metal are provided between an inner shell and an outer shell made from metal, and an accommodation portion for accommodating a radioactive substance is provided inside the inner shell. The accommodation portion has a containment structure to be insulated from the outside of the cask. In the heat transfer fins, the portions thereof at the outer shellside are provided in contact with the outer shell and the portions thereof at the inner shell side are cut so as to form a separation portion with respect to the inner shell.

Abstract: A radiation applicator system is structured to be mounted to a radiation source for providing a predefined dose of radiation for treating a localized area or volume, such as the tissue surrounding the site of an excised tumor. The applicator system includes an applicator and an adapter. The adapter is formed for fixedly securing the applicator to a radiation source, such as a radiosurgery system which produces a predefined radiation dose profile with respect to a predefined location along the radiation producing probe. The applicator includes a shank and an applicator head, wherein the head is located at a distal end of the applicator shank. A proximate end of the applicator shank couples to the adapter. A distal end of the shank includes the applicator head, which is adapted for engaging and/or supporting the area or volume to be treated with a predefined does of radiation.

Abstract: After a syringe containing a radioactive sample therein and housed in a radiation shield case is mounted on a radioactive sample holder and set in a radioactive sample measuring apparatus, an upwardly projecting handle of the radioactive sample holder is depressed to cause a syringe holder base supported on second shafts to lower a flange of the syringe held by the syringe holder base, pulling the syringe out of the radiation shield case. Then, the amount of radioactivity of the radioactive sample contained in the syringe is measured.

Abstract: A system and method for storing spent nuclear fuel below grade that affords adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a system comprising: a body having a cavity for receiving and storing a spent fuel canister, a major portion of the body positioned below grade; the body having at least one inlet ventilation duct extending from an above grade inlet to a below grade outlet in the cavity. The inlet ventilation duct can be a en elongated substantially S-shape extending from a side wall of the body to the bottom of the cavity. In another aspect, the invention is a method of storing a spent fuel canister using the system.

Abstract: The invention relates to a component support (29) for use in a radioisotope generator, the component support comprising a latching member (5) movable between an engaging position and an open position characterised by further including a bracing member (13) mechanically associated with the latching member and adapted to prevent movement of the latching member to the open position.

Abstract: A radiation-shielding container assembly defines a central axis and includes an elongated body portion having a closed end, an open end, and an outer surface extending between the open and closed ends. An inner surface is spaced radially inwardly from the outer surface, and a frusto-conical body surface extends radially inwardly from the outer surface adjacent the open end. A cap portion of the container is securable to the body portion and includes a closed end and an open end that is spaced from the closed end. The open end includes a frusto-conical cap surface that is matingly engageable with the frusto-conical body surface such that when the cap portion is secured to the body portion, the frusto-conical body surface and the frusto-conical cap surface overlap each other along a plane that is perpendicular to the axis, thereby preventing a straight-line path for radiation to escape from the container.

Abstract: Encapsulation of an inner facing surface of a lead shield of a radiopharmaceutical pig. The inner facing surface defines a chamber in which is inserted a radiopharmaceutical syringe. The encapsulation protects the inner facing surface against contamination due to leaks of the contents of the radiopharmaceutical syringe and further obviates the need for a sharps container to enclose the syringe during transport. The outer facing surface may likewise be encapsulated and secured to the encapsulation of the inner facing surface.

Abstract: A primary lid is set in a top opening of a vessel body that contains radioactive substance, and closes the top opening. The peripheral edge portion of the primary lid is welded to the inner peripheral surface of the vessel body. As the primary lid is welded, steam in the vessel body is discharged to the outside through a discharge hole in the primary lid, and a shield gas is filled into or run through a space in the outer peripheral portion of the primary lid, so as to prevent the steam from flowing into the welding portion.

Abstract: Materials and methods of manufacturing radiation shielded enclosures is presented that may replace the use of lead, granite and other undesirable materials and manufacturing methods. The present invention provides a high-density radiation shielding enclosure manufactured using a fiberglass lay-up or pressure spaying process and tungsten powder. The method of manufacture may include applying a tungsten powder in an epoxy, caulking, sealant, adhesive or elastomeric compound to the radiation shielding enclosure in order to seal any cracks, holes, joints or other radiation leaks.

Abstract: A radiopharmaceutical pig device that includes two pig sections and two complementary engaging elements that engage each other. One of the two complementary engaging elements in integral with one of the two pig sections. By holding the other of the two complementary engaging elements stationary while the two complementary engaging elements are engaged, the other section of the pig may be removed from the pig without having to grasp the sidewall of the one of the two pig sections. This other of the complementary engaging elements may be part of a pig retainer brace, a shipping container, and L-Block shield or a counter top.

Abstract: A container device (10) for storing hazardous material comprises a substantially cylindrical container block which has a central axial cylindrical through passage (13) and includes a group of storage vessels (12) for the hazardous material positioned between the central passage and the circumferential surface of the container block and which further includes a cylindrical concrete body (14) enveloping the group of storage vessels. The storage vessels (12) are positioned adjacent to one another along a closed curve, and sections of the circumferential surfaces of adjacent storage vessels (12) form the predominant part of the wall of the central passage (13). The concrete body directly contacts the storage vessels (12) over substantially all the parts of said circumferential surfaces, which do not constitute said sections. When the container device is made, the remaining parts of the circumferential surfaces of the storage vessels (12) form a permanent formwork in which the concrete body (14) is cast.

Abstract: In the cask, a shape within a cavity of a barrel main body is formed in a shape corresponding to an outer shape of a basket. The basket has a structure obtained by alternately piling up plate-like members vertically. A heat conducting plate is provided on an outer periphery of the plate-like member. Accordingly, since the basket and the cavity are in a state of being in contact state in a wide area, an efficiency of heat conduction is improved.

Abstract: The invention is a door actuator and alignment apparatus for opening and closing the 15,000-pound horizontally sliding door of a storage overpack. The door actuator includes a ball screw mounted horizontally on a rigid frame including a pair of door panel support rails. An electrically powered ball nut moves along the ball screw. The ball nut rotating device is attached to a carriage. The carriage attachment to the sliding door is horizontally pivoting. Additional alignment features include precision cam followers attached to the rails and rail guides attached to the carriage.

Abstract: A method for grouting a decommissioned nuclear reactor containing residual water. A first, water-absorbent grout is used to grout the bottom portion of the reactor vessel. The water-absorbent grout is formed of cement and a water-absorbent particulate material, such as expanded perlite, exfoliated vermiculite or granulated bentonite. Excess water is absorbed by the particulate material, so that the residual water is incorporated in the fill material when it sets. A set retarder may be included to extend the time for uptake of residual water by the particulate material. Foam may also be included to reduce density and increase pumpability. The remaining, upper portion of the reactor vessel is grouted using lightweight cellular cement grout, lacking the water-absorbent particulate material, so that total weight of the fill remains low enough that the grouted vessel can be removed using the facility's installed crane system.

Abstract: Resin (106) for shielding neutrons is provided at the outer periphery of a shell main body (101) that shields the ?-rays. Basket (130) is constructed of a plurality of angular pipes (132) having neutron absorbing property. The inside of a cavity (102) of the shell main body (101) is processed to match its shape with the external shape of the basket (130), and the angular pipes (132) are inserted into this cavity (102) to be brought into contact with the inner surface of the cavity (102). Used nuclear fuel aggregates are accommodated and stored in latticed cells structured by the angular pipes (132). Thermal conductivity of decay heat generated from the used nuclear fuel aggregates is improved as the outer surface of the angular pipes (132) and the inner surface of the cavity (102) are in direct contact with each other.

Abstract: A device for storing heat-generating hazardous material, particularly radio-active fuel for nuclear reactors, comprises a substantially cylindrical, reinforced concrete body (11) with a cylindrical through center passage (13) and a plurality of axially elongate, substantially cylindrical storage spaces for accommodating the hazardous material which are disposed around and parallel to and radially spaced spaced from the center passage. The storage spaces are formed by sealed storage vessels (21) containing a fluid coolant and made of a heat-conducting material and being encapsulated in the concrete body (11). Heat transferred inwardly from the storage vessels (21) is carried away from the device by air or other fluid coolant flowing upwardly in the center passage (13).

Abstract: A method and apparatus of dispensing a radiopharmaceutical wherein a source of flushing fluid is connected to a first port of a fluid delivery set; a pressurizing unit of a powered injector system (including a powered injector and the pressurizing unit) is connected to a second port of the fluid delivery set; air is purged from the fluid delivery set; and, after purging air from the fluid delivery set, a third port of the fluid delivery set is connected to a source of the radiopharmaceutical. A valve system is included to control flow of fluid. A syringe is operatively connected with a powered injector. A radioactive shield encloses the syringe during operation to protect personnel from detrimental effects. A dose calibrator measure the radioactivity in the syringe.

Abstract: A radiation shield sheet includes a raw utilizing sheet, which includes a plurality of fibers and a plurality of matrixes reinforced together to define a predetermined crossed structure having a plurality of trapping meshes formed between the fibers and matrixes respectively, and a shielding layer, which is made by a predetermined amount of radiation inadmissible material capable of attenuating an intensity of a predetermined electromagnetic radiation, coated on an exposure surface of the raw utilizing sheet, wherein a portion of the shielding layer is captured in the trapping meshes so as to securely bond the radiation shielding layer on the raw utilizing sheet.

Abstract: The invention discloses a method for making two sided Multi-Chip Modules (MCMs) that will allow most commercially available integrated circuits to meet the thermal and radiation hazards of the spacecraft environment using integrated package shielding technology. The invention describes the technology and methodology to manufacture MCMs that are radiation-hardened, structurally and thermally stable using 3-dimensional techniques allowing for high density integrated circuit packaging in a radiation hardened package.

Abstract: An apparatus, transfer cask, system, and method for defueling a nuclear reactor and transferring spent nuclear fuel from a spent nuclear fuel to a storage cask for long terms storage. In one aspect, the invention is an apparatus for use in transferring a canister of spent nuclear fuel from a transfer cask to a storage cask, the apparatus comprising a radiation absorbing shield surrounding a portion of a hole through which the canister can pass; means for securing the apparatus to the top surface of the storage cask; means for securing the bottom surface of the transfer cask to the apparatus; wherein the transfer cask securing means and the storage cask securing means are positioned on the apparatus so that when the apparatus is secured to both the transfer cask and the storage cask, the cavity of the transfer cask, the hole, and the cavity of the storage cask are substantially aligned; and means for moving the bottom lid in a horizontal direction once the bottom lid is unfastened from the bottom surface.

Abstract: Heat conductive fins are welded along both sides of a belt-like member with a margin left along edges of the both sides, thereby to form a unit. The unit is welded to a body with the heat conductive fins from the outside of each fin. Next, another belt-like member is covered over a gap between adjacent belt-like members, and these members are welded from the outside. With this arrangement, there is no need to weld in a narrow and long space and the entire welding step is carried out from the outside, which makes it easier to assemble a cask.

Abstract: The invention provides a method and device for applying radiation to a wound cavity resulting from a lumpectomy. The device comprises a non-deformable body of PTFE or similar material, with a rounded head and elongate stem or handle. The stem defines a channel which extends to the centre of the head for receiving a radiation source from a High Dose Rate, Remotely Controlled After-loading Brachytherapy Unit (HDRRCABU). The head of the device is inserted into the wound cavity and the wound is closed, so that the tissue forming the wound cavity is given a precisely controlled dose of radiation in a matter of minutes/hours rather than days/weeks.

Abstract: An apparatus that acts as a shield for radiopharmaceuticals and protects individuals from radioactivity includes a first body with a first hollow core, a second body with a second hollow core and a third body with a third hollow core. The first hollow core, second hollow core and third hollow core collectively house a hypodermic syringe. A first connection means releasably communicates the first body with the second body. A second connection means releasably communicates the first body with the third body. The third body comprises means for lowering the hypodermic syringe into a well counter to measure radioactivity of the radiopharmaceutical it contains.

Abstract: Encapsulation of an inner facing surface of a lead shield of a radiopharmaceutical pig. The inner facing surface defines a chamber in which is inserted a radiopharmaceutical syringe. The encapsulation protects the inner facing surface against contamination due to leaks of the contents of the radiopharmaceutical syringe and further obviates the need for a sharps container to enclose the syringe during transport.

Abstract: A canister is provided for storing, transporting, and/or disposing of spent nuclear fuel. The canister includes a canister shell, a top shield plug disposed within the canister, and a leak-tight closure arrangement. The closure arrangement includes a shear ring which forms a containment boundary of the canister, and which is welded to the canister shell and top shield plug. An outer seal plate, forming an outer seal, is disposed above the shear ring and is welded to the shield plug and the canister.

Abstract: A storing device includes a radioactive material container, a radioactive material container outer shield and a ring member. The container includes a lower cup portion, an upper cup portion which is securely engaged to the lower cup portion, and a chamber with a cushion member mounted in a top and a bottom end thereof, which is formed inside the container for storing radioactive material. The outer shield includes a base portion and a lid which is securely covered on the base portion, the base portion further including a room to accommodate the radioactive material container. The ring member is pivotedly mounted to a top end of radioactive material container, and is rested between the lid and the upper cup portion. When the lid is opened, the ring member will stand out of the base portion for a tool to conveniently move out the container from the outer shield.

Abstract: A sealable container for receiving toxic waste for long-term storage is described, the container comprising sheet metal members welded together to form a main fillable volume; four hollow, sheet metal, vertically directed leg portions situated at corner positions on the container, and, a separate lid member fixable to the container to seal at least the main fillable volume wherein the majority of the weld length utilized in the container construction is constituted by fillet welds. Further constructions are described having means to prevent flotation of waste in a liquid grout prior to solidification thereof and constructions where the leg volumes are independently fillable of the main volume.

Abstract: An apparatus that acts as a shield for radiopharmaceuticals and protects individuals from radioactivity includes a first body with a first hollow core, a second body with a second hollow core and a third body with a third hollow core. The first hollow core, second hollow core and third hollow core collectively house an insert. The insert houses a hypodermic syringe. A first connection means releasably communicates the first body with the second body. A second connection means releasably communicates the first body with the third body. The second body comprises a piston actuator. The piston actuator can be operated to depress the piston of the hypodermic syringe while the first body is in communication with the second body, and while the third body is removed.

Abstract: A preferred storage system includes a container, a closure lid, and a compression link. Preferably, the container includes an outer wall, which defines an interior, and a first open end. The closure lid is configured to be inserted within the open end of the container, and is adapted to engage in a sealing relationship with the outer wall of the container. Preferably, the compression link includes a container engagement surface and a closure lid engagement surface. The compression link is configured to engage between the closure lid and the outer wall of the container to retain the closure lid in sealing engagement with the container. The container engagement surface and the closure lid engagement surface are configured to extend outwardly from each other, with the container engagement surface being adapted to engage the outer wall of the container and the closure lid engagement surface being adapted to engage the closure lid. Methods also are provided.

Abstract: Apparatus for containing, transporting, and storing or disposing of radioactive machinery, including decommissioned nuclear reactor pressure vessels. An improved, economically-produced container allows easier handling and packaging of machinery within plants where the machinery has been installed, and offers improved shock absorption and attenuation characteristics, especially when packaging is complete, through the provision, for example, of integral fenders. The invention also includes methods of making the container.

Abstract: A method for storing nuclear fuel in a container (10) including a concrete body and a fuel receiver embedded in the concrete body, comprises the steps of: providing formwork (62) for the concrete body and supporting the fuel receiver within the formwork; placing the formwork in an immersed position in a pool (54) containing a body of water; placing concrete in the immersed formwork (62); and removing the formwork with the concrete body cast therein from the pool (52).

Abstract: A radiation-shielding container has an elongated cylindrical base and a cylindrical cap that define a cavity. A reduced portion of the cap extends into the base and includes a planar end surface that engages an internal shoulder within the base, and an external shoulder that engages an annular end surface of the base. The cap is secured to the base by rotating the cap such that tabs defined on the reduced portion slide along inwardly sloping lower engagement surfaces of the base until the tabs abut stop surfaces of the base and are secured by upper engagement surfaces. Removal of the cap is accomplished by rotating the cap in the opposite direction to disengage the tabs from the upper engagement surfaces.

Abstract: Corner of each square pipe is molded into a terrace shape having steps. When a basket is constructed by these square pipes, steps of adjoining square pipes are assembled together face to face. Fuel rod aggregates are housed inside the square pipes and in a cells formed between the square pipes. Since the adjoining square pipes are assembled in a staggered arrangement, boundaries of the cells are defined by the walls of the square pipes itself.

Abstract: A device (10) for storage of hazardous material, especially heat-producing hazardous material, such as radioactive spent nuclear reactor fuel, comprises a substantially cylindrical reinforced concrete body (12) and has an axially elongate storage space (18) for the hazardous material. A prestressed reinforcement (17) having reinforcing members (28, 29) extending helically about the storage space (18) is provided in the concrete body (12) adjacent to the outer side thereof. Preferably, the reinforcing members (28, 29) are divided into two groups, one inside the other, the hand of the reinforcing members (28) of one of the groups being opposite to the hand of the reinforcing members (29) of the other group. Also preferably, the ends of the concrete body are provided with end covers (15, 16) in which the reinforcing members (28, 29) are anchored.

Abstract: Substantially pure uranium hexafluoride is shipped in a conventional overpack. A cylinder includes a vessel with a cylindrical sidewall A head permanently affixed to the sidewall closes one end of the vessel. A valve controls the flow of matter into and out of the vessel. A sealing surface connected to the vessel surrounds the valve. A cap covers the valve and a pair of seals is located between the sealing surface and the cap. The volume between the two seals, the cap and the sealing surface defines a test volume. A test port connects the test volume and an exterior surface of the vessel, and fasteners press the cap against the sealing surface. A maximum rate of leakage from within the cap to the atmosphere outside the cap is determined by measuring the leakage rate into the test volume with a leak testing apparatus connected to the test port. Thereafter the cylinder is placed in a conventional overpack.

Abstract: A radiation-shielding container has an elongated cylindrical base and a cylindrical cap that define a cavity. A reduced portion of the cap extends into the base and includes a planar end surface that engages an internal shoulder within the base, and an external shoulder that engages an annular end surface of the base. The cap is secured to the base by rotating the cap such that tabs defined on the reduced portion slide along inwardly sloping lower engagement surfaces of the base until the tabs abut stop surfaces of the base and are secured by upper engagement surfaces. Removal of the cap is accomplished by rotating the cap in the opposite direction to disengage the tabs from the upper engagement surfaces.

Abstract: An unirradiated nuclear fuel assembly component transport system that includes a clamshell-type inner liner that opens along its axial dimension to load and unload the fuel component being transported. The exterior dimensions of the liner conform to a generic overpack tubular container. The overpack is separable into an upper and lower section with the lower section having a V-shaped channel extending along its longitudinal axis. The liner is supported in the V-shaped channel by at least one row of shock mounts on either side of the channel. The lower section of the overpack is secured from rotation and the top section is latchably engaged to the lower section of the overpack.