Value of burnup credit beyond actinides [electronic resource]

DOE has submitted a topical report to the NRC justifying burnup credit based only on actinide isotopes (U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241). When this topical report is approved, it will allow a great deal of the commercial spent nuclear fuel to be transpo...

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Bibliographic Details
Online Access: Online Access
Corporate Author: United States. Department of Energy. Yucca Mountain Project Office (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Dept. of Energy. Office of Civilian Radioactive Waste Management ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1997.
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Call Number: E 1.99:CONF-971125--
E 1.99:CONF-971125-- Available