Nac International Inc.

Other

Charles W Pennington

George C Carver

Willington J Lee

An apparatus is provided for storing hazardous waste material, which includes one or more of spent nuclear fuel, radioactive material, and fissionable material. The apparatus comprises a containment vessel that encloses the hazardous waste material. A fusible alloy material, for example, a eutectic material, resides within the containment vessel 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.

Apparatus and methods for storing hazardous materials by encasing same in a fusible metal alloy

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.

Apparatus and methods for storing hazardous waste materials by encasing same in a fusible metal alloy

Systems and methods of the disclosure are directed toward removing moisture from, and controlling the temperature of, spent nuclear fuel stored in spent fuel containers and the containers themselves. A vacuum system may remove vapor and gas from the container to reduce pressure and stimulate moisture evaporation. The potentially radioactive gas exiting the spent fuel container can also be transported to a radioactive waste gas system. A non-reactive gas is then circulated through a circulation path, which is communicatively coupled to a spent fuel container. The non-reactive gas can absorb heat and/or moisture from the spent fuel stored within the spent fuel container. Accordingly, heat can be removed by a heat exchanger coupled to the circulation path. Condensate moisture can also be removed from the circulation path.

System and method to control spent nuclear fuel temperatures

Disclosed are the apparatus and methods for closing a canister that stores and transports spent nuclear fuel. In one embodiment, the canister includes a canister shell that includes an open end. A closure lid is inserted within the open end of the canister shell. The closure lid engages the open end of the canister shell to provide a weld area that is substantially on the outer circumference of the closure lid. The weld area includes a first weld layer and a second weld layer. The first weld layer welds the closure lid to the canister shell at the weld area and closes the canister. The second weld layer also welds the closure lid to the canister shell at the weld area, providing a redundant closure seal, and is disposed substantially on top of the first weld layer. The method for closing the canister is provided herein.

Apparatus and methods for achieving redundant confinement sealing of a spent nuclear fuel canister

A transport or storage cask comprises a cask body, a modular thermal conducting and shielding system and a mechanical attachment. The modular thermal conducting and shielding system includes a modular fin and a modular neutron shield. The mechanical attachment retains the modular thermal conducting and shielding system to the cask body. The modular fin is disposed between the modular neutron shield and the cask body. The modular fin is capable of dissipating thermal energy from the cask body.

Apparatuses and methods for mechanical shielding and cooling

A preferred storage system includes a container, a closure lid, and a compression link. Preferably, the container includes an outer wall, which defines an interior, and a first open end. The closure lid is configured to be inserted within the open end of the container, and is adapted to engage in a sealing relationship with the outer wall of the container. Preferably, the compression link includes a container engagement surface and a closure lid engagement surface. The compression link is configured to engage between the closure lid and the outer wall of the container to retain the closure lid in sealing engagement with the container. The container engagement surface and the closure lid engagement surface are configured to extend outwardly from each other, with the container engagement surface being adapted to engage the outer wall of the container and the closure lid engagement surface being adapted to engage the closure lid. Methods also are provided.

Storage vessels and related closure methods

A preferred embodiment may generally be construed as providing a method for storing fissile material, such as spent nuclear fuel (SNF), and includes the steps of: providing a storage container configured to receive the fissile material therein; and applying a coating to a surface of the storage container. Preferably, the coating is formed, at least in part, of a neutron-absorbing material and is adapted to reduce neutron multiplication and/or provide a shielding of the fissile material received within the storage container. Systems also are provided.

Systems and methods for storing fissile materials

A system for storing exothermic materials to enhance heat removal is provided that includes a first canister and a second canister. Preferably, the first canister incorporates a canister wall defining a first storage volume that is adapted to receive exothermic material therein. The second canister incorporates an inner wall and an outer wall, with the inner wall defining a canister-receiving, volume that is adapted to receive at least a portion of the first canister therein. Additionally, the outer wall and the inner wall may define a second storage volume which is adapted to receive exothermic material therein.

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Alpharetta, GA, United States of America

Charles W Pennington