Abstract: Embodiments of the present disclosure are directed to systems, components, and methods for transferring canisters containing radioactive material, for example, from a container assembly using a transfer assembly to a horizontal storage module (HSM). Systems in accordance with various embodiments of the present disclosure include, for example, a vertical to horizontal (VTH) transfer station for a canister and method of transfer, a horizontal to horizontal (HTH) transfer station for a canister and methods of transfer, a transport wagon system for transporting a canister to a horizontal storage module (HSM), and an HSM system for long-term storage of a canister.

Abstract: Embodiments of the present disclosure are directed to systems, components, and methods for transferring canisters containing radioactive material, for example, from a container assembly using a transfer assembly to a horizontal storage module (HSM). Systems in accordance with various embodiments of the present disclosure include, for example, a vertical to horizontal (VTH) transfer station for a canister and method of transfer, a horizontal to horizontal (HTH) transfer station for a canister and methods of transfer, a transport wagon system for transporting a canister to a horizontal storage module (HSM), and an HSM system for long-term storage of a canister.

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: 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: 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: A composite basket assembly (10) for radioactive fuel containment includes a plurality of cask disks (20) disposed together in face-to-face relationship by connecting rods (40) extending through the disks. The disks are formed with interior cells (124) and a grid structure (122) to form discrete compartments for individual fuel assemblies. A neutron-absorbing material (34) is incorporated into the disks to absorb radioactive emissions from the stored fuel.

Abstract: A method of transferring radioactive material from a contaminated area to a container assembly generally includes acquiring radioactive material in a contaminated area, wherein the contaminated area includes at least one shielding wall, and moving the material in the substantially horizontal orientation through an aperture in a shielding wall into a container assembly. Other systems, methods, and components for transferring radioactive material are provided.

Abstract: A rack assembly for nuclear fuel assemblies generally includes a frame assembly and a container assembly including a plurality of individual fuel containers designed to contain individual fuel assemblies, wherein the individual fuel containers are received within and supported by the frame assembly. The rack assembly further includes a shielding assembly including at least one of an inner shielding assembly comprising a substantially continuous shield between the individual fuel containers and an outer shielding assembly comprising a substantially continuous shield around at least a portion of the outer surfaces of the rack assembly. A rack storage system generally includes a plurality of rack assemblies.

Abstract: Embodiments of the present disclosure provide systems and methods for capturing user interface operations. Briefly described, in architecture, one embodiment of the system, among others, includes logic configured to monitor an operation performed by an application interface; logic configured to determine whether the operation is at least one milestone event that is to be saved, wherein the at least one milestone event is a user-interface operation for a process in a particular field of operation; and logic configured to save milestone event information from a user, the information including identification of the user performing the operation and a computer application that was being accessed by the user for the process. Other systems and methods are also included.