Abstract: An automatically adjusting seismic restraint system for nuclear fuel storage in one embodiment comprises a free-standing first fuel storage component (FSC) configured to contain nuclear fuel, and a stationary second FSC configured to receive the first fuel storage component. An inter-body gap formed between the FSCs includes at least one seismic restraint assembly. The assembly includes a stationary wedge member fixedly coupled to the second FSC and a movable loose wedge member engaged with and supported in place by the stationary wedge member. The stationary wedge member defines an inclined load bearing surface slideably engaged with a mating inclined load bearing surface of the loose wedge member. During a seismic event or thermal expansion of the first FSC, the first FSC moves towards the second FSC which shrinks the inter-body gap and the loose wedge member is vertically displaced relative to the stationary wedge member while maintaining engagement therewith.

Abstract: Conformal coatings provide environmental protection for sensitive military electronics. Preliminary MCNP™ modeling of metal oxide impregnated acrylic conformal coatings indicates an effective shield for gammas below 10 keV and a reduction in neutron displacement damage to Si-based electronics across the Watt spectrum. This work provides data which can allow an optimal overall shielding worth per total weight to eventually be evaluated.

Abstract: Techniques for inspecting a weld of a nuclear waste canister include positioning a gamma ray image detector near a nuclear waste canister that encloses nuclear waste. The nuclear waste canister includes a housing that includes a volume in which the waste is enclosed and a top connected to the housing with at least one weld to seal the nuclear waste in the nuclear waste canister. The techniques further include receiving, at the gamma ray image detector, gamma rays from the nuclear waste that travel through one or more voids in the weld; generating an image of the received gamma rays with the gamma ray image detector; and based on the generated image, determining an integrity of the at least one weld.

Abstract: Provided herein are polysiloxane-based composite materials comprising a high weight percentage of elemental components (e.g., elemental boron, elemental copper, elemental bismuth, elemental lead) and low levels of carbon nanofibers. The elemental components may be present in the composite materials at levels greater than 25% by weight. Also provided herein are methods of forming the composite materials that have desirable flexibility and shielding properties. The invention provides a versatile composite material that is compliant and moldable, while still comprising high levels of the elemental shielding components. The materials are particularly useful for applications in which radiation shielding or neutron capture are desired.

Abstract: A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall. The neutron absorbing layer or layers are designed to absorb neutron particles radiated from the radioactive nuclear waste and the metal layers are designed to absorb gamma particles radiated from the radioactive nuclear waste as well as radiated from the neutron absorbing layer or layers that result from reactions associated with absorption of neutron particles.

Abstract: An underground ventilated system for storing nuclear waste materials. The system includes a storage module having an outer shell defining an internal cavity and an inner shell. A majority of the height of the outer shell may be disposed below grade. The outer shell may include a hermetically sealed bottom. First and second canisters are positioned in lower and upper portions within the cavity respectively in vertically stacked relationship. A centering and spacing ring assembly is interspersed between the first and second canisters to transfer the weight of the upper second canister to the lower first canister. The assembly may include centering lugs which laterally restrain the first and second canisters in case of a seismic event. A natural convection driven ventilated air system cools the canisters to remove residual decay heat to the atmosphere. In one non-limiting embodiment, the shells are made of steel.

Abstract: A storage basket for radioactive materials, defining housings parallel to each other and each extending along a housing axis parallel to a longitudinal central axis of the basket, the latter including: a plurality of transverse plates, traversed by a plurality of openings; a plurality of housing tubes arranged parallel to the longitudinal central axis of the basket. The housing tubes are arranged in alternation with the transverse plates along the axis, such that the inner lateral surface of each housing is defined, successively along this axis, at least by the inner surface of a first housing tube, the inner surface of one of the openings of a first transverse plate, and the inner surface of a second housing tube.

Abstract: The present disclosure relates to a sliding type transfer cask for transferring spent nuclear fuel. The sliding type transfer cask includes a transfer container having a space for accommodating a canister; a neutron shielding body disposed around an outer circumference; and an opening/closing portion coupled to a lower portion of the transfer container. The opening/closing portion includes a support portion that has a first through-hole communicating with the transfer container and supports the transfer container; a base plate that is arranged below the support portion; and a lid assembly that includes a first lid portion and a second lid portion. The first lid portion includes a first lid and a first motor for sliding the first lid. The second lid portion includes a second lid and a second motor for sliding the second lid.

Abstract: A canister for storing spent nuclear fuel includes an elongated shell, baseplate enclosing the bottom end of the shell, and removable top lid bolted to the shell. The shell may have a dual thickness comprising a lower portion with first thickness and upper portion with greater second thickness by comparison. The upper portion is formed by an annular boss defining a fastening portion of the shell including plural threaded bores for engaging the lid bolting. The fastening portion may protrude radially outwards or inwards in different embodiments. The lid has a mounting flange receiving the bolts and is seated on the top end of shell. The mounting flange does not protrude radially beyond the outer surface of the fastener portion to minimize the diameter of the canister for placement inside an outer radiation shielded overpack or cask for transport/storage. The shell may optionally include cooling fins.

Abstract: A cask includes a cask body, an outer cylinder, a plurality of fins, and a plurality of neutron shields. The cask body has a tubular shape around a central axis and is capable of housing fuel assemblies. The outer cylinder has a tubular shape surrounding the cask body. The fins are aligned in a circumferential direction in a tubular space formed between the cask body and the outer cylinder, and connect an outer peripheral surface of the cask body and an inner peripheral surface of the outer cylinder to divide the tubular space into a plurality of divided spaces. The neutron shields contain a neutron shielding material with which the divided spaces are filled. Each neutron shield includes a void portion extending in the axial direction along the central axis. Accordingly, it is possible to reduce stress that may be exerted on the outer cylinder or other components by thermal expansion of the neutron shielding material when the fuel assemblies are housed in the cask.

Abstract: A passively cooled storage module for spent nuclear fuel includes an elongated body including a top end, bottom end, sidewall, baseplate, detachable lid, and cavity for holding a fuel canister containing heat-emitting spent nuclear fuel assemblies. Cooling air inlet ducts spaced draw ambient cooling air radially inwards into a lower portion of the cavity. The air flows upwards in the cavity along the canister and is discharged from the top end of the module to atmosphere via natural circulation. The air inlet ducts may have a multi-angled and recurving configuration comprising one or more obliquely angled sections in one embodiment. The exterior inlet end openings of the inlet ducts are arranged at a higher elevation than the interior outlet end openings to prevent the ingress of standing and flood-related waters. The ducts and lid include radiation shielding features.

Abstract: A method of storing high level radioactive waste, and specifically a method of adjusting or controlling the temperature of ventilation air flowing through a storage cavity of a ventilated system. The method includes positioning a metal canister containing high level radioactive waste in a storage cavity of the ventilated system. The ventilated system includes a cask body, a cask lid, a plurality of inlet ducts, and at least one outlet duct so that ventilation air can flow from atmosphere into the storage cavity where it is heated and then back out to the atmosphere. The method includes progressively reducing a cross-sectional area of one or more of the inlet ducts and/or the outlet duct over time so that a rate at which the ventilation air is heated within the storage cavity is maintained above a predetermined threshold to mitigate the risk of stress corrosion cracking in the metal canister.

Abstract: A container and system for handling damaged nuclear fuel, and a method of making the same. In one embodiment, the invention is a damaged fuel container having a specially designed top cap that can be detachably coupled to the elongated tubular wall by simply translating the top cap into proper position within the elongated tubular wall, wherein biased locking elements automatically lock the top cap to the elongated tubular wall. In another embodiment, the vent screens of the damaged fuel container are integrally formed rather than being separate components. In still other embodiments, the lower vent screens are arranged on an upstanding portion of the damaged fuel container. In an even further embodiment, the elongated tubular wall is formed by an extrusion process.

Abstract: A nuclear reactor containment system including a nuclear reactor and a container enclosing the nuclear reactor. The container includes a number of heat removal systems each having an active state and an inactive state, wherein the heat removal systems dissipate heat from the container more efficiently in the active state than in the inactive state, and wherein the heat removal systems are structured to switch from the inactive state to the active state based on a temperature of the container.

Abstract: An object of the invention is to provide a radiation-shielding material that has a high radiation-shielding capability and can be easily coated, molded and sheeted. Metals or the like having a radiation-shielding capability are blended with an elastomer precursor in a high concentration thereby providing a radiation-shielding material that has a higher radiation-shielding capability than ever before and can be easily coated, molded and sheeted in any desired configuration.

Abstract: A vessel for removing radionuclides from a liquid. The vessel comprises a shielded housing comprising an outer shell and an inner shell disposed within the outer shell. The housing defines an ion exchange chamber between the inner and outer shells. The vessel also comprises an inlet fluidly coupled with the ion exchange chamber, the inlet being configured for fluid communication with a source of the liquid, and an outlet fluidly coupled with the ion exchange chamber, the outlet being configured for fluid communication with a destination of the liquid. The vessel further comprises a first fluid passage extending between an exterior of the vessel and the inner shell and a second fluid passage extending between the exterior of the vessel and the inner shell.

Abstract: An underground ventilated system for storing nuclear waste materials. The system includes a storage module having an outer shell defining an internal cavity and an inner shell. A majority of the height of the outer shell may be disposed below grade. The outer shell may include a hermetically sealed bottom. First and second canisters are positioned in lower and upper portions within the cavity respectively in vertically stacked relationship. A centering and spacing ring assembly is interspersed between the first and second canisters to transfer the weight of the upper second canister to the lower first canister. The assembly may include centering lugs which laterally restrain the first and second canisters in case of a seismic event. A natural convection driven ventilated air system cools the canisters to remove residual decay heat to the atmosphere. In one non-limiting embodiment, the shells are made of steel.

Abstract: A module for storing high level radioactive waste includes an outer shell, having a hermetically closed bottom end, and an inner shell forming a cavity and being positioned inside the outer shell to form a space therebetween. At least one divider extends from the top to the bottom of the inner shell to create a plurality of inlet passageways through the space, each inlet passageway connecting to a bottom portion of the cavity. A plurality of inlet ducts each connect at least one of the inlet passageways and ambient atmosphere, and each includes an inlet duct cover affixed atop a surrounding inlet wall, the inlet wall being peripherally perforated. A removable lid is positioned atop the inner shell and has at least one outlet passageway connecting the cavity and the ambient atmosphere, the lid and the top of the inner shell being configured to form a hermetic seal therebetween.

Abstract: A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a ventilated system for storing high level waste emitting heat, the system comprising: an air-intake shell forming an air-intake cavity; a plurality of storage shells, each storage shell forming a storage cavity; a lid positioned atop each of the storage shells; an outlet vent forming a passageway between an ambient environment and a top portion of each of the storage cavities; and a network of pipes forming hermetically sealed passageways between a bottom portion of the air-intake cavity and at least two different openings at a bottom portion of each of the storage cavities such that blockage of a first one of the openings does not prohibit air from flowing from the air-intake cavity into the storage cavity via a second one of the openings.

Abstract: A fuel storage system for storing and drying nuclear fuel rods includes a vertically oriented capsule defining an internal cavity. A plurality of fuel rod storage tubes is disposed in the cavity. In one embodiment, each storage tube has a transverse cross section configured and dimensioned to hold no more than one fuel rod. Intact or damaged fuel rods may be stored in the storage tubes. After the fuel rods are loaded into the capsule, a lid is attached to a previously open top end of the capsule. In one embodiment, the lid may be sealed welded to the capsule for forming a gas tight enclosure. The interior of the capsule and multiple fuel rods contained therein may be dried together simultaneously via flow conduits formed in the lid that can be fluidly connected to a suitable drying process such as a forced gas dehydration system.

Abstract: A description of a bottle container assembly for use by patients for daily handling of glass insulin ampules and/or a variety of prescription medications and small medicine bottles. The container assembly is designed for frequent daily use at home, work or travel. It is constructed to address the safe handling, use and safe storage of medicines and in particular the storage of a variety of glass ampules containing insulin or other hypodermic solutions. The invention provides a safe, suitable and reusable container assembly to hold various insulin ampules replacing the fragile cardboard boxes they are shipped in by the manufacturers.

Abstract: An apparatus for holding radioactive objects includes a base and a central pillar extending upwardly between a bottom end coupled to the base and a top end above the base. A plurality of inner segments are spaced around the central pillar, and a plurality of outer segments are spaced around the inner segments to form pairs. The inner segments, the outer segments and the central pillar may be coupled together to permit limited radial movement of at least one of the segments of each pair. Each pair may define a generally vertical, object-receiving channel arranged between the inner and outer segment of the pair. The segments of each pair may be adapted to bear against an object in the channel of the pair to laterally restrain the object and facilitate heat transfer from the object.

Abstract: A system for receiving and storing high level radioactive waste comprising: an enclosure comprising walls having inlet ventilation ducts, a roof comprising an array of holes, and a floor; an array of metal shells located in an internal space of the enclosure, the array of metal shells being co-axial with the array of holes in the roof so that containers holding high level radioactive waste can be lowered through the array of holes in the roof and into the array of metal shells; the array of metal shells acting as load bearing columns for the roof; and each of the metal shells comprising (i) an expansion joint for accommodating thermal expansion and/or contraction of the metal shells; and (ii) one or more holes at a bottom portion of the metal shell.

Abstract: A concrete storage module (26) is adapted to slideably receive a cylindrical canister assembly (12) therein. Heat dissipation fins (62) and a tubular heat shield (96) are disposed within the module to help dissipate heat emitted from the nuclear fuel assemblies stored in the canister to air flowing through the module. The canister assembly (12) is composed of a basket assembly (70) constructed from multi-layer structural plates disposed in cross-cross or egg carton configuration. A single port tool (106) is provided for draining water from the canister (12) and replacing the drain water with make-up gas. The single port tool is mounted in the cover (100) of the canister and is in fluid flow communication with the interior of the canister.

Abstract: The invention relates to a thermal conduction element (20) for a package for transporting and/or storing radioactive materials, comprising: an internal part (30) intended to be in contact with a lateral body (14) of the package; an external part (34) intended to form a portion of an external envelope (24) of said package, holding radiological protection means (22); an intermediate part (32) arranged between the internal and external parts, the internal, external and intermediate parts being produced from copper and one of the alloys thereof. According to the invention, the external part (34) is equipped, at each of its two opposite ends, with an area (36) for connection by welding to another thermal conduction element (20), each connection area (36) being produced from steel.

Abstract: A product cartridge for a radionuclide including a product vial having a permeable cap and surrounded by a radiation shield and a filling cartridge having a separate radiation shield, the filling cartridge is supported adjacent the permeable cap by coupling the radiation shield of the filling cartridge to the radiation shield of the product vial, the filling cartridge is moveable within the radiation shield of the filling cartridge to engage and pierce the permeable cap during filling of the product vial, the filling cartridge includes an aperture on an end opposite the product vial that receives a radionuclide, a scavenger that removes heavy metals from the radionuclide and a filter that filters the biological contaminants, simultaneously venting the product vial as the radionuclide flows from the aperture through the filling cartridge and into the product vial.

Abstract: A device for purifying a fluid is disclosed. The aforesaid device comprises: (a) a passage adapted for conducting a flow of the fluid, said passage provided with input and output openings; (b) a plurality of elongate members coated with a titanium oxide disposed within the passage; (c) fastening means for mechanically fixating terminals of the elongate members within the passage; (d) at least one source of ultraviolet radiation adapted for illuminating the elongate members; (e) pumping means adapted for generating the fluid flow through the passage from the input opening to the output opening. The fastening means comprises at least two fasteners. Each fastener comprises two mutually orthogonal spaced apart pluralities of parallel rods. The rods are adapted for restricting lateral displacement of the elongate members.

Abstract: A container system, for radioactive waste and method for using the same is provided. The system includes a canister configured for holding radioactive waste and a lid system. In one embodiment, the lid system comprises a two-part lid assembly including a confinement lid and a shielded lifting lid. The confinement lid is detachably mounted to the confinement lid. In use, the lifting lid supports die confinement lid for lifting and placement on the canister. The lifting lid further shields operators while the confinement lid is mounted to the canister. Thereafter, the lifting lid is removed and may be reused for confinement lid mountings on other canisters. In one embodiment, the confinement lid is bolted to the canister. The canister may be disposed in a protective overpack for transport and storage.

Abstract: A method of transferring a radioactive payload and a method of performing work within a cavity of a shielding container. In one embodiment, the invention is a method comprising a) positioning a shield-gate apparatus atop a first shielding container, the shield-gate apparatus comprising a body, a passageway extending through the body, and one or more movable shielding gates that are open; and b) lifting a removable shielding lid of the first shielding container through the passageway, wherein during closing of the one or more shielding gates the removable shielding lid is maintained in a position in which either: (1) a bottom surface of the removable shielding lid is disposed within the passageway at a height above the one or more shielding gates; or (2) the bottom surface of the removable shielding lid is substantially flush with the top surface of the body of the shield-gate apparatus.

Abstract: A packaging device for the transport and/or storage of a radioactive medium generating flammable gases and/or explosives via radiolysis, comprising a plurality of canisters intended to contain the radioactive medium, each canister defining an inner storage space accessible via an opening for filling the medium, on which plug-forming means are mounted. According to the invention, the device also comprises a structure forming a chamber, and means for placing in communication allowing a fluid communication to be set up between the inner storage space and the chamber.

Abstract: The present invention is directed to a new manufacturing process for a FRP honeycomb structure where the honeycomb core assembly is arranged parallel to the surface. The honeycomb core is made from FRP prepreg with double structural walls and is manufactured by stiffening using heat and pressure. In a honeycomb core assembly set tank, a plurality of internal tanks are gathered in honeycomb core assembly. An internal tank FRP wall maintains the pressure of the internal tank, while an external FRP wall, heat foamed plastic resin and rigid FRP hull of set tank endure the external shock loading. A honeycomb core structure of six-corner cell can be infinitely arranged, and its structural position is unique. A set tank in which a plurality of internal tanks are gathered into a honeycomb core assembly can be arranged in infinite combinations, such that the total capacity can be extremely large.

Abstract: A storage container is carried into a nuclear-reactor containment, and then, the core structure is housed in the storage container. In this process, a bottom cover is carried to a storage-container body by using a moving device. The storage-container body and the bottom cover are positioned by adjusting the position of the bottom cover on the moving device while the bottom cover is supported by free bearings. The bottom cover is then attached to the storage-container body.

Abstract: A system for storing high level radioactive waste. In one embodiment, the invention can be a system comprising an overpack body extending along a vertical axis and having a cavity for storing high level radioactive waste, the cavity having an open top end and a floor; an overpack lid positioned atop the overpack body to enclose the open top end of the cavity; an air inlet vent for introducing cool air into the cavity, the air inlet vent comprising an annular air inlet plenum and an annular air inlet passageway, the annular air inlet plenum extending radially inward from an outer surface of the overpack body to the annular air inlet passageway, the annular air inlet passageway extending upward from the annular air inlet plenum to an opening in the floor, and an air outlet vent in the overpack lid for removing warmed air from the cavity.

Abstract: A system and method of transferring a radioactive payload using a shield-gate apparatus, including a method of performing work within a cavity of a shielding container using a shield-gate apparatus and shielding block, in one embodiment, the invention is a system comprising: a shield-gate apparatus comprising a body, a passageway extending along an axis through the body, and one or more movable shielding gates; a shielding block positioned atop the body of the shield-gate apparatus to enclose a first opening of the passageway; and a retaining feature that prevents relative transverse movement between the shielding block and the shield-gate apparatus while allowing relative rotation between the shielding block and the shield-gate apparatus about a central axis of the shielding block.

Abstract: A radioactive substance storage container 100 includes a body 10 and a lid 10 having a sealed structure, and a basket 5 housed in the body 1 to hold fuel assemblies. The basket 5 includes a neutron shielding material. The radioactive substance storage container 100 includes a subcritical-performance reinforcing member 20 including a neutron shielding material and located between an inner periphery of the body 1 and an outer periphery of the basket 5.

Abstract: A composition of matter that experiences an increase rate of radioactive emission is presented. The composition comprises a radioactive material and particles having affinity for Hydrogen or its isotopes. When exposed to Hydrogen, the composition's emission rate increases. Methods of production are also presented.

Abstract: The invention concerns a cask for a canister containing radioactive material, comprising a canister extraction assembly and designed so that it can bring the canister to an extraction position inside the cask housing in which this canister is free of any contact with the inner surface. Also, one of two elements from among a carriage and a support structure of the assembly is provided with a guide ramp cooperating with a ramp follower provided on the other of the two elements, the ramp being designed so that a relative translational movement between the carriage and the structure, in the longitudinal direction of the cask, causes the changeover of the two elements from a drawn-together position to a drawn-apart position, or conversely.

Abstract: Disclosed is a radioactive contaminant container including a wall that defines a containing space for containing radioactive contaminants and shields at least a portion of radiation irradiated from the radioactive contaminants, and the wall has an outer shape of a hexagonal cylinder or a substantially hexagonal cylinder.

Abstract: A radioactive material handling assembly (10) includes an outer housing (12) and an inner cell (14). The inner cell defines a radioactive material containment/handling chamber (16) and is removably mountable inside the outer housing. Handling means is operable from outside the inner cell to handle radioactive materials located in the containment/handling chamber. At least one of the outer housing and the inner cell is predominantly of a shielding material which is opaque to radioactivity.

Abstract: A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a ventilated system for storing high level waste emitting heat, the system comprising: an air-intake shell forming an air-intake cavity; a plurality of storage shells, each storage shell forming a storage cavity; a lid positioned atop each of the storage shells; an outlet vent forming a passageway between an ambient environment and a top portion of each of the storage cavities; and a network of pipes forming hermetically sealed passageways between a bottom portion of the air-intake cavity and at least two different openings at a bottom portion of each of the storage cavities such that blockage of a first one of the openings does not prohibit air from flowing from the air-intake cavity into the storage cavity via a second one of the openings.

Abstract: An apparatus and method for inter-unit transfer of spent nuclear fuel. In one aspect, the invention is a method of transferring high level radioactive waste comprising: a) loading high level radioactive waste into a water-filled cavity of a canister body having an open top end at a first location; b) coupling a lid to the canister body to enclose the open top end; c) removing a volume of water from the cavity so that a water level of the water within the cavity is above a top end of the high level radioactive waste and a space exists between the water level and a bottom surface of the lid; d) hermetically sealing the cavity; and e) transferring the canister to a second location, the water level remaining above the top end of the high level radioactive waste during the transfer.

Abstract: A fuel basket spacer, and system and method for storing high level radioactive waste. In one aspect, the invention is an apparatus for transporting and/or storing radioactive materials comprising: a body having a cavity for receiving radioactive materials; a basket positioned in the cavity comprising a plurality of cells; and a structure having an outer surface and an inner surface forming a central passageway; the structure positioned in the cavity so that the basket extends through the central passageway of the structure; and wherein the internal perimeter of the structure corresponds to the external perimeter of the basket in size and shape and the external perimeter of the structure corresponds to the perimeter of the cavity in size and shape. Circumferential clearances are provided between structure and the basket and the structure and the body that are eliminated when exposed to a residual heat load of the radioactive waste.

Abstract: A plurality of first plate members 10 is stacked with long side ends 10LT1 and 10LT2 thereof abutting to each other. Plate member joint bodies 100 are formed by attaching connecting members 30 to side surfaces 10S of the stacked first plate members 10, and connecting the first plate members 10. Further, the plate member joint bodies 100 are so disposed to face each other, and the connecting members 30 projecting from the side surfaces 10S of the first plate members 10 are inserted into recesses formed at both long side ends of second plate members 20. A recycled fuel assembly storage basket 1 is thus formed. Recycled fuel assemblies are stored in spaces surrounded by the first plate members 10 and the second plate members 20.

Abstract: According to one general aspect there is a needle package apparatus that comprises a top portion and a bottom portion; a plurality of needle slots exact distance apart that allows to place a plurality of needles that contain radioactive seeds; a cylindrical coil that is inserted to the plurality of needle slots to hold said plurality of needles, wherein said cylindrical coil prevents the leakage of the radiation from the radioactive seeds; a set of hinges located at the end of said needle package within the outer most said plurality of needle slots; wherein the hinges can be bend to change the angle of said top portion of said needle package by a medical personnel to create a stand; and a single end enclosure located at the distal end of said cylindrical coil to provide an enclosed cylinder.

Abstract: Disclosed is a radioactive contaminant container including a wall that defines a containing space for containing radioactive contaminants and shields at least a portion of radiation irradiated from the radioactive contaminants, and the wall has an outer shape of a hexagonal cylinder or a substantially hexagonal cylinder.

Abstract: A system and method of transferring a radioactive payload using a shield-gate apparatus, including a method of performing work within a cavity of a shielding container using a shield-gate apparatus and shielding block, in one embodiment, the invention is a system comprising: a shield-gate apparatus comprising a body, a passageway extending along an axis through the body, and one or more movable shielding gates; a shielding block positioned atop the body of the shield-gate apparatus to enclose a first opening of the passageway; and a retaining feature that prevents relative transverse movement between the shielding block and the shield-gate apparatus while allowing relative rotation between the shielding block and the shield gate apparatus about a central axis of the shielding block.

Abstract: A system for receiving and storing high level radioactive waste comprising: an enclosure comprising walls having inlet ventilation ducts, a roof comprising an array of holes, and a floor; an array of metal shells located in an internal space of the enclosure, the array of metal shells being co-axial with the array of holes in the roof so that containers holding high level radioactive waste can be lowered through the array of holes in the roof and into the array of metal shells; the array of metal shells acting as load bearing columns for the roof; and each of the metal shells comprising (i) an expansion joint for accommodating thermal expansion and/or contraction of the metal shells; and (ii) one or more holes at a bottom portion of the metal shell.

Abstract: In one embodiment, a system and method for dry storage comprises removing spent fuel rods from their fuel rod assemblies and placing the freed fuel rods in a storage cell of a dry storage canister with a high packing density and without a neutron absorber material present.

Abstract: A method of using automatic whole body personnel contamination monitors and/or means for decontaminating individuals exposed to radioactive material contamination is provided. The inventive method involves the use of these monitors and/or decontamination means in intermodal containers of mobile-unit structures dedicated to responding to radiological emergency situations. Also provided are such mobile-unit structures, as well as systems that employ such mobile-unit structures.

Abstract: The invention concerns a vessel for processing, transfer, accumulation and/or transfer of material containing civilian or military origin plutonium, in the form of plutonium oxide, carbide and/or nitride. The plutonium is preferably present in a concentration not higher than a guaranteed maximum between 20 and 50% wt. in said material, possibly with other actinides such as americium, neptunium, or curium. Said material is preferably in form of powder, granulate and/or tablets. The vessel comprises a volume of 20 to 70 liters for containing said material, demarcated at least by two substantially parallel walls, these two walls being separated by a distance e between 8 and 15 cm.