An apparatus is provided for storing hazardous waste material, which includes one or more of spent nuclear fuel, radioactive material, and fissionable material. A fusible alloy material, for example, a eutectic material, resides within the apparatus and surrounds the hazardous waste material. In the preferred embodiments, it is suggested that the fusible alloy material exhibits liquidus and solidus or melting temperatures that are between about 100 and 300 degrees Fahrenheit for facilities using the apparatus and methods for liquid storage pool loading applications. For facilities using the apparatus and methods for dry loading, the fusible alloy materials may exhibit liquidus and solidus or melting temperatures that are between about 100 and 650 degrees Fahrenheit. The fusible alloy material is introduced in a liquid phase and eventually solidifies into a solid phase as the temperature of the hazardous waste material and/or the local environment decreases.

An apparatus is provided for storing hazardous waste material, which includes one or more of spent nuclear fuel, radioactive material, and fissionable material. A fusible alloy material, for example, a eutectic material, resides within the apparatus and surrounds the hazardous waste material. In the preferred embodiments, it is suggested that the fusible alloy material exhibits liquidus and solidus or melting temperatures that are between about 100 and 300 degrees Fahrenheit for facilities using the apparatus and methods for liquid storage pool loading applications. For facilities using the apparatus and methods for dry loading, the fusible alloy materials may exhibit liquidus and solidus or melting temperatures that are between about 100 and 650 degrees Fahrenheit. The fusible alloy material is introduced in a liquid phase and eventually solidifies into a solid phase as the temperature of the hazardous waste material and/or the local environment decreases.

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 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.

An apparatus, system and method for handling and translating high level radioactive waste. The apparatus comprises a body for supporting the cask close to the ground so that the cask and the apparatus can pass underneath over head doors. The apparatus further comprises rollers for translating the cask. The apparatus additionally supports the storage cask during spent nuclear fuel transfer procedures.

An apparatus, system and method for handling and translating high level radioactive waste. The apparatus comprises a body for supporting the cask close to the ground so that the cask and the apparatus can pass underneath over head doors. The apparatus further comprises rollers for translating the cask. The apparatus additionally supports the storage cask during spent nuclear fuel transfer procedures.

A shipping container containing an unirradiated nuclear fuel assembly is lifted off the ground by operating a crane to raise a lifting tool comprising a winch. The lifting tool is connected with the shipping container by a rigging line connecting with the shipping container at a lifting point located on the shipping container between the top and bottom of the shipping container, and by winch cabling connecting with the shipping container at the top of the shipping container. The shipping container is reoriented by operating the winch to adjust the length of the winch cabling so as to rotate the shipping container about the lifting point. Shortening the winch cabling rotates the shipping container about the lifting point from a horizontal orientation to a vertical orientation, while lengthening the winch cabling rotates the shipping container about the lifting point from the vertical orientation to the horizontal orientation.

A shipping container containing an unirradiated nuclear fuel assembly is lifted off the ground by operating a crane to raise a lifting tool comprising a winch. The lifting tool is connected with the shipping container by a rigging line connecting with the shipping container at a lifting point located on the shipping container between the top and bottom of the shipping container, and by winch cabling connecting with the shipping container at the top of the shipping container. The shipping container is reoriented by operating the winch to adjust the length of the winch cabling so as to rotate the shipping container about the lifting point. Shortening the winch cabling rotates the shipping container about the lifting point from a horizontal orientation to a vertical orientation, while lengthening the winch cabling rotates the shipping container about the lifting point from the vertical orientation to the horizontal orientation.

A system for producing technetium-99m from molybdate-100. The system comprises: a target capsule apparatus for housing a Mo-100-coated target plate; a target capsule pickup apparatus for engaging and delivering the target cell apparatus into a target station apparatus; a target station apparatus for receiving and mounting therein the target capsule apparatus. The target station apparatus is engaged with a cyclotron for irradiating the Mo-100-coated target plate with protons. The irradiated target capsule apparatus is transferred to a receiving cell apparatus comprising a dissolution/purification module for receiving therein a proton-irradiated Mo-100-coated target plate. A conveyance conduit infrastructure interconnects: (i) the target capsule pickup apparatus with the target station apparatus, (ii) the target station apparatus and the receiving cell apparatus; and (iii) the receiving cell apparatus and the dissolution/purification module.

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.