A disposal system is provided for transferring material to a container. The disposal system includes a discharge chute having a mating surface. The mating surface is configured to engage with a container, and the discharge chute is configured to extend and retract so that the mating surface moves along a path between an extended position and a retracted position. The disposal system also includes at least one controller that is configured to cause the discharge chute to extend and retract.

A disposal system is provided for transferring material to a container. The disposal system includes a discharge chute having a mating surface. The mating surface is configured to engage with a container, and the discharge chute is configured to extend and retract so that the mating surface moves along a path between an extended position and a retracted position. The disposal system also includes at least one controller that is configured to cause the discharge chute to extend and retract.

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 reactor building capable of shortening a time required for spent fuel removal while protecting spent fuel stored in a spent fuel pool from a falling object is provided. The reactor building includes a spent fuel pool 5, a spent fuel rack 6 located in the spent fuel pool 5 and configured to store spent fuel 14, and a protection slab 8 located above the spent fuel rack 6.

Methods for nuclear power plant maintenance which reduces outage time while a polar crane is maintained. In some examples, the method includes the steps of placing an auxiliary crane on a set of rails of a polar crane, using the auxiliary crane to perform maintenance work while the polar crane is maintained, and removing the auxiliary crane after maintenance work on the polar crane is completed. In some further examples, the method includes placing a second auxiliary crane on the set of rails. Still in other example, bridge motors are used to turn the rails, allowing the auxiliary crane to reach every area of the plant floor.

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.

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.

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.

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.