The present disclosure relates to a sliding type transfer cask for transferring spent nuclear fuel. The sliding type transfer cask includes a transfer container having a space for accommodating a canister; a neutron shielding body disposed around an outer circumference; and an opening/closing portion coupled to a lower portion of the transfer container. The opening/closing portion includes a support portion that has a first through-hole communicating with the transfer container and supports the transfer container; a base plate that is arranged below the support portion; and a lid assembly that includes a first lid portion and a second lid portion. The first lid portion includes a first lid and a first motor for sliding the first lid. The second lid portion includes a second lid and a second motor for sliding the second lid.

The present disclosure relates to a sliding type transfer cask for transferring spent nuclear fuel. The sliding type transfer cask includes a transfer container having a space for accommodating a canister; a neutron shielding body disposed around an outer circumference; and an opening/closing portion coupled to a lower portion of the transfer container. The opening/closing portion includes a support portion that has a first through-hole communicating with the transfer container and supports the transfer container; a base plate that is arranged below the support portion; and a lid assembly that includes a first lid portion and a second lid portion. The first lid portion includes a first lid and a first motor for sliding the first lid. The second lid portion includes a second lid and a second motor for sliding the second lid.

A nuclear fuel, the nuclear fuel comprising uranium aluminide grains, wherein the uranium aluminide grain properties are selected for good isotope extraction after irradiation and chemical digestion.

Apparatus and method for drying spent nuclear fuel loaded in a cavity of a canister. A non-reactive gas discharged from the canister is selectively circulated through one of a contaminated circulation system and a non-contaminated circulation system according to a measured radiation dose rate.

Cleanup systems include plural coolant inputs that are physically combined to create a single flow at a desired filtering temperature. Filter(s) are used to clean the coolant, and coolant flowing therethrough will damage the filter or not be adequately filtered if having temperature in excess of an operating temperature of the filter. The inputs have different temperatures, and mixing them creates a combined flow at a desired temperature. The amount of each flow is selected based on its individual temperature to achieve this desired temperature. The combined flow is then conditioned with the filter at an operable temperature and returned to the coolant origin for the inputs. No heat exchangers or heat loss to outside heat sinks are required. Cleanup systems may be used with any coolant loop, including Rankine-cycle electricity generation systems like nuclear power plants, combustion boilers, and steam generators, and heat transfer systems.

A system for preparing a container holding radioactive waste for dry storage. In one aspect, the invention can be a system for preparing a container having a cavity loaded with radioactive elements for dry storage, the system comprising: a gas circulation system comprising a condenser module, a desiccant module, and a gas circulator module; the gas circulation system configured to form a hermetically sealed closed-loop path when operably connected to the cavity of the container; and means for adding and removing the desiccant module as part of the hermetically sealed closed-loop path.

A system for preparing a container holding radioactive waste for dry storage. In one aspect, the invention can be a system for preparing a container having a cavity loaded with radioactive elements for dry storage, the system comprising: a gas circulation system comprising a condenser module, a desiccant module, and a gas circulator module; the gas circulation system configured to form a hermetically sealed closed-loop path when operably connected to the cavity of the container; and means for adding and removing the desiccant module as part of the hermetically sealed closed-loop path.

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.

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.

A system and method for drying cavities containing spent nuclear fuel is devised. The invention utilizes a non-intrusive procedure that is based on monitoring the dew point temperature of a non-reactive gas that is circulated through the cavity. In one aspect, the invention is a system for drying a cavity loaded with spent nuclear fuel comprising: a canister forming the cavity, the cavity having an inlet and an outlet; a source of non-reactive gas; means for flowing the non-reactive gas from the source of non-reactive gas through the cavity; and means for repetitively measuring the dew point temperature of the non-reactive gas exiting the cavity.