Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks /

Bibliographic Details
Main Author:	Mueller, D. E. (Author)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, September 2015.
Subjects:	Fission products > Handling. Monte Carlo method. Actinide elements. Fuel burnup (Nuclear engineering) Spent reactor fuels > Storage. Spent reactor fuels > Transportation. Pressurized water reactors.
Online Access:	https://purl.fdlp.gov/GPO/gpo61036

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