Abstract: Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.

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: Described herein, are methods for providing a protective coating to a storage container for storing nuclear material, the method comprising depositing nickel particles on at least one surface of the substrate to produce the protective coating, wherein the nickel particles are deposited by cold spraying a composition comprising nickel particles and a carrier gas comprising nitrogen. In one aspect, the carrier gas consists essentially or consists only of nitrogen. The methods do not require pretreatment or modification of the nickel particles prior to cold spraying, which makes the methods described herein economically practical. The coatings produced by the methods described herein possess several advantageous properties including, but not limited to, high adhesion strength to the storage system and low porosity. The coatings produced by the methods described herein are effective against chemical attack such as, for example, CISCC.

Abstract: Embodiments of a thermal divider insert for a dry storage, spent nuclear fuel cask are disclosed. The thermal divider insert enables safe storage of the hazardous nuclear material when one or more air inlets have been fully or partially blocked to an extent that insufficient air flows into the air inlets and through the cask for adequate cooling of the hazardous nuclear material. A concrete overpack contains a metal canister with the hazardous nuclear material. The overpack has an inside surface that is spaced from an outer surface of the canister to create an annular region that permits flow of air between the surfaces for cooling the canister. Air inlets near the bottom of the overpack communicate air from an outside into the annular region. Outlet vents near the top of the overpack communicate air from the annular region to the outside.

Abstract: A containment cask is disclosed for safely transporting and storing radioactive hazardous waste in a dry air environment. The cask comprises a single drum containing the radioactive hazardous waste, a sealed and shielded containment vessel containing the drum, and an outer container. The outer container can be in the form of an outer shield vessel (OSV) made from iron to provide further shielding. This outer container is appropriate for a drum having higher activity waste. The outer container can also be in the form of an overpack assembly that adds protection for atmospheric hazards, but adds little in terms of shielding. This outer container is appropriate for a drum having lower activity waste.

Abstract: A container is designed to safely store radioactive debris. The container has an overpack having an elongated body extending between a top end and a bottom end. A basket is situated inside of the overpack. The basket has elongated canisters. Each of the canisters has an elongated body extending between a top end and a bottom end. At least one of the canisters has an insert with a plurality of elongated perforated tubes that contain radioactive debris. The perforations enable gas flow, primarily air, through the side wall to enable evaporation of liquid, primarily water, from the radioactive debris, by increasing the exposed surface area of the debris.

Abstract: A modular portable cask transfer (MPCT) facility is capable of transferring a canister containing spent nuclear fuel materials from or to a transportation cask respectively to or from a storage overpack. A transfer cask is utilized for the transfer. Telescoping legs enable movement of the transfer cask independent of the canister, which is moved using a hoist. Due to its modular configuration, the MPCT facility can be assembled, disassembled, and moved from one nuclear power plant to another.

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: Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.

Abstract: A container is designed to safely store radioactive debris from, for example, a nuclear reactor meltdown, in water or air. The container, with preferably although not necessarily all metal parts, has an overpack having an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top. A basket is situated inside of the overpack. The basket has a plurality of elongated cylindrical canisters that are in parallel along their lengths. Each of the canisters has an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top.

Abstract: A transfer cask system for cooling spent nuclear fuel during the transfer from a spent nuclear fuel pool to a storage or transfer cask is disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. The transfer cask includes spacing components which define an annular region between the transfer cask and the canister. The transfer cask includes air inlets near a bottom end that permit air to flow through the defined annular region and exit at the open top of the transfer cask, thereby cooling the fuel within the canister. The transfer cask further comprises a neutron shield configured to absorb additional heat and shield radiation that may be generated within the canister. The transfer cask includes a transfer door that can open and close and has support rails that can support a spent nuclear fuel canister located in the transfer cask.

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: Systems and methods of the disclosure are directed toward removing moisture from, and controlling the temperature of, spent nuclear fuel stored in spent fuel containers and the containers themselves. A vacuum system may remove vapor and gas from the container to reduce pressure and stimulate moisture evaporation. The potentially radioactive gas exiting the spent fuel container can also be transported to a radioactive waste gas system. A non-reactive gas is then circulated through a circulation path, which is communicatively coupled to a spent fuel container. The non-reactive gas can absorb heat and/or moisture from the spent fuel stored within the spent fuel container. Accordingly, heat can be removed by a heat exchanger coupled to the circulation path. Condensate moisture can also be removed from the circulation path.

Abstract: Disclosed are apparatus and methods for storing or transporting spent nuclear fuel. In one embodiment, a container for storing spent nuclear fuel comprises a plurality of elongated tubes that receives spent nuclear fuel rods. Each tube has four sidewalls and four corners defining a rectangular cross section. The plurality of tubes is arranged in an alternating pattern. An attachment means attaches together the plurality of tubes at the corners so that two adjacent sidewalls of adjacent tubes are substantially aligned.

Abstract: Disclosed are the apparatus and methods for closing a canister that stores and transports spent nuclear fuel. In one embodiment, the canister includes a canister shell that includes an open end. A closure lid is inserted within the open end of the canister shell. The closure lid engages the open end of the canister shell to provide a weld area that is substantially on the outer circumference of the closure lid. The weld area includes a first weld layer and a second weld layer. The first weld layer welds the closure lid to the canister shell at the weld area and closes the canister. The second weld layer also welds the closure lid to the canister shell at the weld area, providing a redundant closure seal, and is disposed substantially on top of the first weld layer. The method for closing the canister is provided herein.

Abstract: A transport or storage cask comprises a cask body, a modular thermal conducting and shielding system and a mechanical attachment. The modular thermal conducting and shielding system includes a modular fin and a modular neutron shield. The mechanical attachment retains the modular thermal conducting and shielding system to the cask body. The modular fin is disposed between the modular neutron shield and the cask body. The modular fin is capable of dissipating thermal energy from the cask body.

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 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.