The present disclosure relates to a transfer cask for transferring spent nuclear fuel. The transfer cask transfers a canister storing the spent nuclear fuel and includes a transfer container having a space for accommodating the canister; a neutron shielding body arranged on an outer periphery of the transfer container to shield neutrons; and an opening/closing portion that is coupled to a lower portion of the transfer container and opens and closes the lower portion of the transfer container, wherein the opening and closing portion, a support portion supporting the transfer container and having a first through hole in communication with the transfer container; a lid assembly having a first lid portion and a second lid portion that open and close the first through hole; and a base plate on which the support portion is seated and a second through hole through which the canister is drawn out is formed.

A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The suspended container may be hollow and a solution of fissile materials and salt materials may be provided within the suspended container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the suspended container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.

A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The suspended container may be hollow and a solution of fissile materials and salt materials may be provided within the suspended container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the suspended container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.

The present invention concerns a hood for handling and confinement of at least two objects of slender shape, including an external enclosure and internal enclosures inside the external enclosure and at least one motor fixed above an internal enclosure and inside a barrel, the motor(s) being adapted to rotate the screw of the screw-nut mechanism of each internal enclosure and therefore the nut over a stroke A, and first and second mechanical control means, arranged in part above the cover of the external enclosure, respectively for manually guiding the internal enclosures in translation over a stroke A0 and manually pivoting the barrel in order to bring a holding member of one of the internal enclosures opposite the opening in the bottom of the external enclosure. Application to the handling and confinement of nuclear material sample holders.

A travel system (20) for a canister storage, transfer, or transport system generally includes a support structure (22), at least one traveling device (24) for preparing, inspecting, and/or repairing the canister, and a base ring (26) for supporting the traveling device and providing for rotational movement of the traveling device relative to the support structure.

A nuclear waste fuel storage system includes an unventilated cask including inner and outer shells, an annular space between the shells containing radiation shielding, and sealed baseplate. Threaded anchor bosses are affixed to the top end of the cask. A heavy free-floating radiation shielding lid is loosely coupled the top end of the cask in a movable manner via the anchor bosses by bolt assemblies which loosely secure the lid to the cask. An internal cavity of the cask which holds a nuclear waste fuel canister is sealed by an annular gasket compressed between the lid and cask, thereby forming a gas tight pressure vessel operable to retain internal pressures exceeding atmospheric. During a cask overpressurization condition, the lid automatically moves between a normal downward sealed position on the cask to an installer-adjustable raised relief position ajar from the cask to relieve excess pressure to atmosphere.

A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The suspended container may be hollow and a solution of fissile materials and salt materials may be provided within the suspended container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the suspended container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.

The present disclosure relates to a transfer cask for transferring spent nuclear fuel. The transfer cask transfers a canister storing the spent nuclear fuel and includes a transfer container having a space for accommodating the canister; a neutron shielding body arranged on an outer periphery of the transfer container to shield neutrons; and an opening/closing portion that is coupled to a lower portion of the transfer container and opens and closes the lower portion of the transfer container, wherein the opening and closing portion, a support portion supporting the transfer container and having a first through hole in communication with the transfer container; a lid assembly having a first lid portion and a second lid portion that open and close the first through hole; and a base plate on which the support portion is seated and a second through hole through which the canister is drawn out is formed.

A travel system (20) for a canister storage, transfer, or transport system generally includes a support structure (22), at least one traveling device (24) for preparing, inspecting, and/or repairing the canister, and a base ring (26) for supporting the traveling device and providing for rotational movement of the traveling device relative to the support structure.

A methodology and device that is capable of packaging highly radioactive materials configured in long elongated linear shapes into tight coils that can easily be placed into the small payload storage areas of typical commercially available radioactive material shipping containers. The design of the device allows the reconfiguration of the radioactive material to manually occur in a manner that allows the operator of the device to remain shielded from the radiation to prevent over-exposure of the operator to the nuclear radiation being emitted from the radioactive material.