Sensitivity and parametric evaluations of significant aspects of burnup credit for PWR spent fuel packages [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Corporate Author:	Oak Ridge National Laboratory. (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Washington, D.C. : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1996.
Subjects:	Spent Fuel Elements. Transport. Burnup. Criticality. Spent Fuel Casks. Design. Pwr Type Reactors. Actinides. Isotope Ratio. Fission Products. S Codes. Numerical Data. Nuclear Fuels ;21 Nuclear Power Reactors And Associated Plants.

Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages

Published 1993

Online Access

Government Document Electronic eBook