Packaging design criteria for the MCO cask | Zendy

M.D. Clements | Zendy

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Packaging design criteria for the MCO cask

Author(s) -

M.D. Clements

Publication year - 1996

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/464056

Subject(s) - spent nuclear fuel , tonne , cask , environmental science , radioactive waste , waste management , nuclear engineering , engineering

Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the K Basins to a Canister Storage Building in the 200 East Area. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks

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