Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization

A new covariance data library based on ENDF/B-VII.1 was recently processed for the SCALE nuclear analysis code system. The multigroup covariance data are discussed here, along with testing and application results for critical benchmark experiments. The cross section covariance library, along with co...

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Bibliographic Details
Published in:Nuclear data sheets 2015-01, Vol.123
Main Authors: Williams, M.L., Wiarda, D., Ilas, G., Marshall, W.J., Rearden, B.T.
Format: Article
Language:English
Subjects:
AFTER-HEAT
BENCHMARKS
DATA COVARIANCES
FISSION PRODUCTS
INTEGRAL CROSS SECTIONS
NUCLEAR DATA COLLECTIONS
NUCLEAR FUEL CYCLE AND FUEL MATERIALS
NUCLEAR PHYSICS AND RADIATION PHYSICS
REACTOR SAFETY
SPENT FUELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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Description
Summary:A new covariance data library based on ENDF/B-VII.1 was recently processed for the SCALE nuclear analysis code system. The multigroup covariance data are discussed here, along with testing and application results for critical benchmark experiments. The cross section covariance library, along with covariances for fission product yields and decay data, is used to compute uncertainties in the decay heat produced by a burned reactor fuel assembly.
ISSN:0090-3752
1095-9904
DOI:10.1016/J.NDS.2014.12.016