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.
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.
Charles W. Pennington - Alpharetta GA George C. Carver - Suwanee GA
Assignee:
NAC International, INC - Norcross GA
International Classification:
G21F 500
US Classification:
2505061, 2505071, 2505181, 376403
Abstract:
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.
Apparatuses And Methods For Mechanical Shielding And Cooling
Charles W. Pennington - Alpharetta GA, US George Carver - Norcross GA, US
Assignee:
NAC International, Inc. - Norcross GA
International Classification:
G21C 19/00
US Classification:
376272, 376293, 376294, 2505061, 2505181, 220 404
Abstract:
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.
Apparatus And Methods For Achieving Redundant Confinement Sealing Of A Spent Nuclear Fuel Canister
Charles W. Pennington - Alpharetta GA, US George Carver - Norcross GA, US
Assignee:
NAC International, Inc. - Norcross GA
International Classification:
G21C 13/00 G21C 19/00
US Classification:
376203, 2505061, 376272
Abstract:
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.
Methods For Transporting And Canistering Nuclear Spent Fuel
Disclosed are methods for transporting and canistering nuclear spent fuel. In one embodiment, the method for transporting and canistering nuclear spent fuel comprises providing a canister that includes a mechanical closure for a lid on a container. The canister containing the nuclear spent fuel is loaded into a transport cask, and the transport cask is sealed at the power plant. It is preferred that the lid is not installed on the canister at the power plant. The transport cask containing the canister and nuclear spent fuel is transported to a remote facility. At the remote facility, the transport cask is opened and the lid of the canister is installed using the mechanical closure to seal the canister after the canister is transported to the remote facility. The canister containing the spent nuclear fuel is placed into an overpack, which is stored at the remote facility.
Methods For Demonstrating Moderator Exclusion For Nuclear Criticality Safety
Disclosed are methods for assuring that requirements for fissile material transportation are met to comply with the double contingency principle for preventing nuclear criticality by excluding moderator in-leakage. In one embodiment, a method includes designing and fabricating a canister to achieve an acceptable application, and verifying pre-shipment operation to assure that a transport system is properly assembled to meet its licensed transport configuration.
Systems And Methods For Loading And Transferring Spent Nuclear Fuel
Gary Tjersland - Atlanta GA, US Tom Danner - Norcross GA, US George Carver - Norcross GA, US Charles W. Pennington - Alpharetta GA, US
International Classification:
G21C 19/00
US Classification:
376272
Abstract:
Disclosed are systems and methods for loading and transferring spent nuclear fuel. In one embodiment, among others, the system comprises a transfer cask that contains spent nuclear fuel and shields radioactivity of the spent nuclear fuel, and an immersion tank that receives transfer casks within. The immersion tank has fluid that is circulated in the immersion tank, thereby cooling and providing shielding for the received transfer cask containing the spent nuclear fuel.
Mountain Valley Medical Center 92 Bettys Crk Rd, Dillard, GA 30537 (706)7466571 (phone), (706)7465643 (fax)
Education:
Medical School American University of the Caribbean School of Medicine Graduated: 1982
Languages:
English Spanish
Description:
Dr. Pennington graduated from the American University of the Caribbean School of Medicine in 1982. He works in Dillard, GA and specializes in Family Medicine. Dr. Pennington is affiliated with Mountain Lakes Medical Center.