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

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Bibliographic Details
Author / Creator:	Mueller, D. E., author.
Imprint:	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, September 2015.
Description:	1 online resource (73 unnumbered pages) : color illustrations
Language:	English
Subject:	Fission products -- Handling. Monte Carlo method. Actinide elements. Fuel burnup (Nuclear engineering) Spent reactor fuels -- Storage. Spent reactor fuels -- Transportation. Pressurized water reactors. Actinide elements. Fuel burnup (Nuclear engineering) Monte Carlo method. Pressurized water reactors. Spent reactor fuels -- Storage. Spent reactor fuels -- Transportation.
Format:	E-Resource U.S. Federal Government Document Book
URL for this record:	http://pi.lib.uchicago.edu/1001/cat/bib/10753628

Hidden Bibliographic Details
Other authors / contributors:	U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards, issuing body. Oak Ridge National Laboratory, issuing body.
Notes:	"Manuscript completed: May 2014; Date published: September 2015." Title from title screen (viewed on Sept. 18, 2015). "NUREG/CR-7205." "ORNL/TM-2012/544." Includes bibliographical references (page 21).
Other form:	Print version: Mueller, D. E. Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks
GPO item no.:	1051-H-11 (online)
Govt.docs classification:	Y 3.N 88:25/7205

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