Abstract:
A separable multi-component cask for spent nuclear fuel transport and storage includes a vertically elongated outer cylinder having a neutron radiation shielding composition and a vertically elongated inner cylinder having a gamma radiation blocking composition. The inner cylinder includes a cavity configured to hold a spent nuclear fuel canister. The inner cylinder is detachably mounted and nested inside a cavity of the outer cylinder and is separable therefrom during spent fuel cask loading operations in a staged manner. An air ventilation annulus formed between the first and second cylinders forms a heat removal passage to remove heat emitted by the radioactive canister when placed inside the second cylinder. A pair of removably coupled mating top flanges on the inner and outer cylinders supports and suspends the inner cylinder in a cantilevered manner, thereby allowing the directly heated inner cylinder to thermally expand to a greater degree than the outer cylinder.
Abstract:
Processes for shutting down a regeneration reactor and for removing spent solid from the regeneration reactor may comprise shutting off a feed comprising an ionic liquid to the regeneration reactor, cooling the regeneration reactor, removing at least a portion of the ionic liquid from the regeneration reactor, purging the regeneration reactor with N 2 191 gas, introducing water into the regeneration reactor to form an acidic liquid in the regeneration reactor, and dumping the acidic liquid and the spent solid from the regeneration reactor. The acidic liquid may be neutralized with a basic liquid to provide a neutralized liquid. The spent solid may be separated from the neutralized liquid. In an embodiment, noble metal(s) may be recovered from the spent solid.
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. Nuclear fuel assemblies for powering nuclear reactors generally comprise large numbers of fuel rods that are contained in discrete fuel rod assemblies.
Abstract:
It is common to store decayed radioactive waste in waste packages, lowered into vertical concrete cylindrical storage containers called tile holes. These containers of these packages decay over time and may become fragile, making it difficult to remove them using conventional methods. A retrieval tool has been developed, comprising a cylinder that fits between the tile hole internal diameter and the outside diameter of the waste package inside the tile hole. Inflatable air wedges are equally spaced inside the cylinder. The air wedges are inflated to a low pressure (2.1 psig) to provide uniform grip to the outside of the packages, minimizing the risk of damage to the decayed containers. A back-up system uses horizontal safety bars at the bottom of the cylinder, which may be rotated to form a partial platform under the waste package, preventing the package from falling in the event of a failure.
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:
According to the present invention there is provided a container for the storage or transport of nuclear fuel elements comprising a plurality of elongate compartments for receiving the nuclear fuel elements, the compartments being defined by a first set of plates intersecting with a second set of plates, the first set of plates extending perpendicularly with respect to the second set of plates to define compartments having a rectangular cross section, wherein at an intersection of a first plate in the first set of plates and a second plate in the second set of plates, the first and second plates are interconnected by joint which comprises a locking pin extending through a passage formed through and parallel to adjacent longitudinal edges of the plates.