CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy, 2004.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: vp : digital, PDF file
Additional Creators:: Oak Ridge National Laboratory
United States. Department of Energy
United States. Department of Energy. Office of Scientific and Technical Information
Access Online:: www.osti.gov

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Summary:

The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and attempts to answer this question: What type of SNF cask would be produced if we were to start over and design SNF casks based on today's requirements? The characteristics for a next-generation SNF cask system are examined and are found to be essentially the same in Russia and the United States. It appears that the new depleted uranium dioxide (DUO2)-steel cermet material will enable these requirements to be met. Depleted uranium (DU) is uranium in which a portion of the 235U isotope has been removed during a uranium enrichment process. The DUO2-steel cermet material is described. The United States and Russia are cooperating toward the development of a next-generation, dual-purpose, storage and transport SNF system.

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Note:

Published through SciTech Connect.
10/03/2004.
Americas Nuclear Energy Symposium (ANES 2004), Miami, FL (US), 10/03/2004--10/06/2004.
Forsberg, C.W.; Shapovalov, V.I.; Haire, M.J.; Matveev, V.Z.

Funding Information:

AC05-00OR22725

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