A method of stabilizing virgin ion exchange resin material is provided. The method includes rinsing virgin ion exchange resin material with deoxygenated water, introducing the rinsed virgin ion exchange resin material into a gas impermeable vessel and hermetically sealing the vessel. A vessel containing deoxygenated water and virgin ion exchange resin material is also provided. A method of facilitating water treatment in a site in need thereof by providing the gas impermeable vessel containing virgin ion exchange resin material and residual moisture from deoxygenated water is also provided.

A method of stabilizing virgin ion exchange resin material is provided. The method includes rinsing virgin ion exchange resin material with deoxygenated water, introducing the rinsed virgin ion exchange resin material into a gas impermeable vessel and hermetically sealing the vessel. A vessel containing deoxygenated water and virgin ion exchange resin material is also provided. A method of facilitating water treatment in a site in need thereof by providing the gas impermeable vessel containing virgin ion exchange resin material and residual moisture from deoxygenated water is also provided.

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.

The present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material such as calcined material. In certain embodiments, the system comprises a filling nozzle having a valve body having a distal end and an outer surface, the outer surface proximate the distal end being configured to sealingly and removeably couple to an inner surface of a filling port of the container. In certain embodiments, the method comprises (a) coupling an outer surface of a filling nozzle with an inner surface of a filling port of a container to form a first seal (b) adding hazardous waste material into the container (c) decoupling the filling port from the filling nozzle and (d) inserting a fill plug into the filling port, the fill plug forming a second seal with the inner surface of the filling port, the second seal being distally spaced from at least a portion of the first seal with respect to the container.

The invention relates to UF.sub.6 transport and process containers to store UF.sub.6 enriched up to 20 percent by weight .sup.235U in amounts up to 1,500 kg U. The containers include a shell, which has an integral heat exchanger positioned between the exterior and interior surfaces/substrates of the shell. The integral heat exchanger is composed of metal passage voids to pass heat transport fluid. The shell forms an inner chamber, and a partition configuration is positioned within the inner chamber, extending longitudinally along the length of the container, to form a plurality of individual compartments within the inner chamber to store the UF.sub.6. The containers may be produced by additive manufacturing methods.

The invention relates to UF.sub.6 transport and process containers to store UF.sub.6 enriched up to 20 percent by weight .sup.235U in amounts up to 1,500 kg U. The containers include a shell, which has an integral heat exchanger positioned between the exterior and interior surfaces/substrates of the shell. The integral heat exchanger is composed of metal passage voids to pass heat transport fluid. The shell forms an inner chamber, and a partition configuration is positioned within the inner chamber, extending longitudinally along the length of the container, to form a plurality of individual compartments within the inner chamber to store the UF.sub.6. The containers may be produced by additive manufacturing methods.

A canister to store spent nuclear fuel in an underground repository includes a first end portion; a second end portion; and a middle portion attachable to the first and second end portions to define an interior volume of the housing that is sized to enclose at least one spent nuclear fuel assembly. The first and second end portions comprise shielding.

A canister to store spent nuclear fuel in an underground repository includes a first end portion; a second end portion; and a middle portion attachable to the first and second end portions to define an interior volume of the housing that is sized to enclose at least one spent nuclear fuel assembly. The first and second end portions comprise shielding.

Provided is a device and method for containing hazardous waste, including a container for hazardous waste, comprising a hangable bag having an interior volume, the hangable bag being constructed at least in part of collapsible material and configured to be lifted and configured to support an interior bladder, and the interior volume being variable; and an interior bladder, the interior bladder connectable with a through port to a lid.

Provided is a device and method for containing hazardous waste, including a container for hazardous waste, comprising a hangable bag having an interior volume, the hangable bag being constructed at least in part of collapsible material and configured to be lifted and configured to support an interior bladder, and the interior volume being variable; and an interior bladder, the interior bladder connectable with a through port to a lid.