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: 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 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: 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: A transport container for nuclear fuel is provided with an outer container having internal insulation, the insulation defining an internal cavity. The cavity receives a plurality of fuel containers wherein the internal volume of the fuel containers is at least 5% of the external volume of the outer container. The container allows substantially higher volume proportions of enriched fuel to be safely transported than is possible with prior containers.

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 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 high-polymer neutron shielding material which scarcely reduces the hydrogen number density when exposed to a high temperature of 150 to 200° C. for a long time period A heat-setting type epoxy resin is employed. The base resin is selected from various epoxy resins such as bisphenol A type epoxy resin. The hardener is selected from alicyclic polyamine, polyamide amine, aromatic polyamine, acid anhydride, and so on. These materials are mixed and hardened at a temperature higher than the room temperature. To give a flame resistance to the hardened resin, a fire retardant such as magnesium hydroxide is added to the mixture. To improve the neutron shielding performance of the hardened resin, a neutron absorbing material is added to the mixture. Further, to increase the moderating performance, hydrogenated bisphenol A epoxy resin is used as the base resin or metal hydride or hydrogen absorbing alloy is added.

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 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 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: 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 transport container for nuclear fuel is provided with an outer container having internal insulation, the insulation defining an internal cavity. The cavity receives a plurality of fuel containers wherein the internal volume of the fuel containers is at least 5% of the external volume of the outer container. The container allows substantially higher volume proportions of enriched fuel to be safely transported than is possible with prior containers.

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: An improved nuclear shielding material based on a resistant organic matrix that is flexible or resilient after room temperature polymerization, and sufficiently fluid before polymerization so as to effectively fill voids in radiation containment structures. The material can be formulated to undergo pyrolysis and transform into a strong ceramic material. Along with the organic matrix the material contains a primary radiation shielding component such as tungsten carbide powder. Additional optional components include: a neutron absorbing/gamma blocking compound such as boron carbide powder, a heat conducting material such as diamond powder, a high temperature resistant compound such as silicon dioxide powder, a second neutron blocking compound which also imparts electrical conductivity, namely barium sulfate powder, and a hydrogen gas surpassing component which readily absorbs hydrogen such as sponge palladium. Refractory materials and rare earth oxides can be included to favor effective ceramic transition.

Abstract: A canister containing spent fuel assemblies is contained in a body of a transportation cask. A top opening of a vessel body of the canister is closed by a lid welded to the vessel body. A ring-shaped elastic tube is provided between the inner surface of the upper end portion of the body and the outer surface of the upper end portion of the vessel body. The tube seals the gap between these surfaces to prevent a fluid from getting into the gap between the surfaces through the top opening of the body. An inspection space for the insertion of a tester for detecting the welding state of the lid is defined between the inner surface of the upper end portion of the body and the outer surface of the upper end portion of the vessel body.

Abstract: A lifting lug for a nuclear-waste container has a tubular body having an inner end formed with a flange adapted to be bolted to the container and a transverse wall set in and tightly fitted to a smaller-diameter outer end of the tubular body. The wall is a separate piece from the body and is press-fitted to the tubular body. The wall is mounted at a load point of the lifting lug. In addition the wall is formed of a disk and/or a ring, typically as one unitary piece with the disk and ring spaced from each other.

Abstract: A method and apparatus for transporting syringes containing radioactive material. The apparatus includes a radiopharmaceutical pig having an inner chamber in which a sharps container can be secured. The sharps container has a housing and an attachable cap. The method includes assembling the radiopharmaceutical pig so that the chamber of the radiopharmaceutical pig contains the syringe in the sharps container housing. The radiopharmaceutical pig is disassembled, where upon the syringe is removed, discharged, and then replaced in the sharps container housing. The cap of the sharps container is affixed to the housing of the sharps container, thus enclosing the contaminated syringe therein. The radiopharmaceutical pig is assembled so that its chamber contains the sharps container and the syringe. The radiopharmaceutical pig is transported to a disposal area, where it is disassembled and the sharps container containing the syringe is placed in a particular disposal container.

Abstract: An apparatus, system, and method of storing and transferring a canister of spent nuclear fuel. In one aspect, the apparatus is a lid for a ventilated vertical overpack having a chamber for receiving spent nuclear fuel, the lid having ventilation ducts. In one aspect, the system comprises: a lid for a ventilated vertical overpack having a chamber for receiving spent nuclear fuel, the lid having ventilation ducts; and a ventilated vertical overpack having a cylindrical body including lower ventilation ducts, a bottom, and a chamber formed by the body and the bottom adapted for receiving a canister of spent nuclear fuel.

Abstract: An unirradiated nuclear fuel assembly transport canister that includes a clamshell type fuel assembly inner liner that has interior dimensions that closely conform to the outer envelope of the fuel assembly to be transported and exterior dimensions that conform to a generic overpack tubular container. The liner is inserted into the overpack tubular container which is in turn supported by a shock absorbing suspension system within a birdcage frame.

Abstract: A transport container for nuclear fuel is provided with an outer container having internal insulation, the insulation defining an internal cavity. The cavity receives a plurality of fuel containers wherein the internal volume of the fuel containers is at least 5% of the external volume of the outer container. The container allows substantially higher volume proportions of enriched fuel to be safely transported than is possible with prior containers.

Abstract: A segmented lattice rack to store fuels coming from nuclear reactors, whose walls are made of plates joined orthogonally forming a mesh defining multiple cell cavities which are longitudinally coupled forming a sandwich comprising a central part coinciding with the active part of the stored element, being from a material obtained from neutronic poisons, preferably boron treated steel; whilst the end areas coinciding with the non-active part of the stored radioactive element are of normal stainless steel, joined to each other and with the adjacent components by means of welding or pretensioning.

Abstract: A system and method for moving a canister of spent nuclear fuel from a first location, which may be within a nuclear power generation facility to a second location such as a storage cask that is used for short-term or long-term storage of spent nuclear fuel includes a first lifting mechanism for engaging a transfer cask and a second lifting mechanism for engaging and lifting the canister of spent nuclear fuel. Preferably, the method is practiced by first positioning a canister of spent nuclear fuel within the transfer cask and then engaging the transfer cask with the first lifting mechanism. The canister is engaged with the second lifting mechanism. The transfer cask having the canister positioned within is moved to the vicinity of a storage cask, and the canister is lowered from the transfer cask into the storage cask by the second lifting mechanism without disengagement of the first lifting mechanism from the transfer cask.

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: A container for storing and transporting device containing radioactive materials used for medical procedures is disclosed. Such devices may include a radioactive shielding material which contains a portion of the radioactivity emitted by the radioactive material. The container has an upper portion and a lower portion, and at least one of the portions includes a radiation shielding material, such as lead, steel or other appropriate shielding materials. Devices containing radioactive material are placed within the container. The container secures the devices against lateral movement within the container. The radiation shielding material of the lower portion of the container may cooperate with the radiation shielding material of the device to contain more of the emitted radiation than is contained by the device alone. The container and the holder may be sterilizable to allow such devices to be transported and sterilized for medical use.

Abstract: The basket comprises a bundle of tubes (10) connected to each other by an assembly structure (14) so as to form a regular network of compartments (16). Cross pieces (12) are placed between the tubes (10) so as to define a second wall approximately continuous around each compartment (16) surrounding the first wall materialized by tubes (10) and at least partially in contact with this wall. Thus, baskets with compartments with arbitrarily shaped cross sections, and particularly square, rectangular, hexagonal or circular cross sections, can be made for a limited cost.

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: 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: An apparatus that transports radiopharmaceuticals and protects individuals from radioactivity that includes a first body with a first hollow core open on a first edge and a second edge. The first hollow core surrounds an insert containing a hypodermic syringe. There is a second body with a second hollow core open on a first edge and closed on a second edge. The second hollow core surrounds the insert with the hypodermic syringe. A third body with a third hollow core open on a first edge has the third hollow core fixedly communicating with a hollow stem open on a second edge. The third hollow core surrounds the insert with the hypodermic syringe. A first connection means releasably communicates the first body with the second body and a second communication means releasably communicates with the first body and third body for providing protection from the radioactive agent.

Abstract: A container for storing and transporting device containing radioactive materials used for medical procedures is disclosed. Such devices may include a radioactive shielding material which contains a portion of the radioactivity emitted by the radioactive material. The container has an upper portion and a lower portion, and at least one of the portions includes a radiation shielding material, such as lead, steel or other appropriate shielding materials. Devices containing radioactive material are placed within the container. The container secures the devices against lateral movement within the container. The radiation shielding material of the lower portion of the container may cooperate with the radiation shielding material of the device to contain more of the emitted radiation than is contained by the device alone. The container and the holder may be sterilizable to allow such devices to be transported and sterilized for medical use.

Abstract: An apparatus and method for transporting radiopharmaceutical substances. The apparatus comprises a radiation shielding pig having an elongated sidewall that extends between two ends and that defines an elongated, interior chamber. The sidewall is thinner than each of the ends. A radiation shield defines at least one cavity. The shield has two open ends and a central area between the open ends that is thicker than each of the two open ends. Also, a method of assembling and disassembling the apparatus includes, placing a syringe filled with a radiopharmaceutical substance into the pig; placing the pig containing the filled syringe in the radiation shield; placing the pig and the shield into an ammunition can for transporting the radioactive substance contained in the syringe.

Abstract: A transport container for nuclear fuel assemblies, of right prismatic shape, which has an external envelope and an internal structure defining at least one housing for receiving and holding a fuel assembly.

Abstract: An improved method and apparatus for transporting a syringe containing radioactive material that provides many advantages, including the safe enclosure of the syringe both before and after use, which reduces the possibility of contamination of the radiopharmaceutical pig. The present invention also provides a radiopharmaceutical pig that eliminates the need for a protective plastic outer shell and has a convenient grip. Finally, the present invention allows the user to readily determine if a syringe within a closed sharps container is full or spent without handling the container.

Abstract: A system and method for rapidly analyzing elemental abundances in rock or soil samples (14) under field conditions. The system uses a portable neutron source (12) to allow neutron activation analysis of elements having identifiable radioactive decay characteristics. A radiation detector (18) detects radiation released by the sample (14) and provides radiation testing results to an amplifier (26) for computing the concentration of trace elements in the sample with a high degree of accuracy.

Abstract: According to the present invention there is provided a container for the storage and transport of nuclear fuel elements comprising a plurality of elongate compartments for receiving the nuclear fuel elements, the compartments being defined by a first set of plates intersecting with a second set of plates, the first set of plates extending perpendicularly with respect to the second set of plates to define compartments having a rectangular cross section, wherein the plates include an interlocking joint, the interlocking joint comprising at least one projection provided on one plate and a recess formed in the other plate, and wherein a retaining portion is provided in the recess for engagement by the projection so as to interlock the plates.

Abstract: A high-polymer neutron shielding material which scarcely reduces the hydrogen number density when exposed to a high temperature of 150 to 200° C.

Abstract: A needle holder for use in a seed handling assembly that is made as a box-like open-sided metal frame having a bottom, a top and opposed side frame members with a pair of steel shielding plates enclosing the sides of the frame. The top frame member defines at least one row of holes for receiving elongated needles containing radioactive seeds. Feet are attached to opposite sides of the frame to enable the needle holder to be free standing. Lifting elements are attached to the frame to enable the needle holder to be picked up and moved while needles are held in the needle holder and for a person lifting and moving the needle holder to be shielded from radioactive seeds in a needle.

Abstract: A container body of a concrete cask includes a storage portion that stores a canister. A refilling system includes a reduction cylinder having an outside diameter smaller than the diameter of the storage portion and an inside diameter larger than the diameter of the canister, a first lift mechanism configured to raise and lower the reduction cylinder between a down position in the storage portion and an up position wherein it is drawn out of the storage portion, and a second lift mechanism having a holding portion for holding one end portion of the canister and configured to raise and lower the canister with respect to the container body. In refilling operations, the canister is loaded into and unloaded from the storage portion of the container body by the second lift mechanism with the reduction cylinder set in the storage portion.

Abstract: A vessel for the shipment of uranium hexafluoride includes a cylindrical wall closed by pair of approximately semi-ellipsoidal heads welded to form a sealed container. A service valve is located in one end. The valve is covered by a removable, watertight valve protection cover assembly. The vessel also includes a test port by means of which the integrity of the valve protection cover assembly may be tested after the cylinder has been filled with uranium hexafluoride and the valve protection assembly has been installed. The valve protection assembly is shaped so that it fits within the envelope of the standard 30B cylinders. The distal end of the valve protection assembly is recessed from a plane defined by the open end of the surrounding chime by at least one half inch, and preferably by ¾ inch or more. Accordingly, the fits within an overpack already approved by the NRC and used by shippers of uranium hexafluoride.

Abstract: A container for storing and transporting device containing radioactive materials used for medical procedures is disclosed. Such devices may include a radioactive shielding material which contains a portion of the radioactivity emitted by the radioactive material. The container has an upper portion and a lower portion, and at least one of the portions includes a radiation shielding material, such as lead, steel or other appropriate shielding materials. Devices containing radioactive material are placed within the container. The container secures the devices against lateral movement within the container. The radiation shielding material of the lower portion of the container may cooperate with the radiation shielding material of the device to contain more of the emitted radiation than is contained by the device alone. The container and the holder may be sterilizable to allow such devices to be transported and sterilized for medical use.

Abstract: The invention relates to a wall segment (10) for device, such as a cabin, a wall or a screen, protecting against laser beams from a laser source (38) and enclosing a work or effective zone, this wall segment comprising an inner wall (12) adjacent to the work or effective zone and an outer wall (14) parallel to the inner wall (12) and farther away from the work and effective zone than the inner wall (12). To activate an emergency OFF system to shut down the laser source or the processing machine, the inner and outer walls (12) and (14) resp. are metallic, for instance of iron or steel sheetmetal, the inner wall (12) being fitted at least on its side (18) facing the work or effective zone with a highly absorbent coating (16) and the side (22) of the outer wall (14) facing the inside wall (12) being of lower absorption.

Abstract: The invention concerns a container for transporting or storing radioactive materials comprising two separate confinement chambers, nested one in the other. The outer confinement chamber comprises at least an inside part of a body (10), a lid (12) and sealing members (16) interposed between them. The inner confinement chamber comprises a container (18) a plug (22) and sealing members (24) interposed between them. A flange (18b) of the container is supported against a shoulder (20) of the body (10). The plug (22) is pressed against the flange (18b) by fixing members (28, 30) advantageously anchored in the body (10).

Abstract: A dry radioactive substance storage facility stores spent fuel assemblies from nuclear power plants. The facility comprises a structure having a storage room storing storage tubes containing spent fuel assemblies. An air inlet duct defining an air inlet passage through which air is supplied into the storage room and a stack defining an air discharge passage through which air from the storage room is discharged outside are connected to the storage room. Radiation shielding members are disposed on the side of the air inlet duct and on the side of the stack, respectively, in the storage room to intercept radiation propagating toward the air inlet passage and the air discharge passage.

Abstract: An improved nuclear shielding material that is flexible so as to effectively fill voids in radiation containment structures. Under very high temperatures the material is designed to undergo pyrolysis and transform into a strong ceramic material. The material contains a number of components, the first of which is a polymeric elastomer matrix such as a two part self-polymerizing system like RTF silicone rubber. Additional components include: a compound to shield gamma radiation like tungsten carbide powder, a neutron absorbing/gamma blocking compound such as boron carbide powder, a heat conducting material such as diamond powder, a high temperature resistant compound such as silicon dioxide powder, a second neutron absorbing compound which also imparts electrical conductivity, namely barium sulfate powder, and a hydrogen gas surpassing component which readily absorbs hydrogen such as sponge palladium.

Abstract: A system for storing exothermic materials to enhance heat removal is provided that includes a first canister and a second canister. Preferably, the first canister incorporates a canister wall defining a first storage volume that is adapted to receive exothermic material therein. The second canister incorporates an inner wall and an outer wall, with the inner wall defining a canister-receiving, volume that is adapted to receive at least a portion of the first canister therein. Additionally, the outer wall and the inner wall may define a second storage volume which is adapted to receive exothermic material therein.

Abstract: A method and apparatus for transporting syringes containing radioactive material. The apparatus includes a radiopharmaceutical pig having an inner chamber in which a sharps container can be secured. The sharps container has a housing and an attachable cap. The method includes assembling the radiopharmaceutical pig so that the chamber of the radiopharmaceutical pig contains the syringe in the sharps container housing. The radiopharmaceutical pig is disassembled, where upon the syringe is removed, discharged, and then replaced in the sharps container housing. The cap of the sharps container is affixed to the housing of the sharps container, thus enclosing the contaminated syringe therein. The radiopharmaceutical pig is assembled so that its chamber contains the sharps container and the syringe. The radiopharmaceutical pig is transported to a disposal area, where it is disassembled and the sharps container containing the syringe is placed in a particular disposal container.

Abstract: A container for storing and transporting needle cartridges containing radioactive materials used for medical procedures is disclosed. Such needle cartridges may include a radioactive shielding material which contains a portion of the radioactivity emitted by the radioactive material. The container of the present invention has an upper portion and a lower portion, and at least one of the portions includes a radiation shielding material, such as lead, steel or other appropriate shielding materials. Needle cartridges containing radioactive material are placed within the container for storage and shipping. The container secures the needle cartridges against lateral movement within the container to protect them from breakage or release of the radioactive materials contained in the needle cartridges. The radiation shielding material of the lower portion of the container may cooperate with the radiation shielding material of the device to container more of the emitted radiation that is contained by the device alone.