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

Journal Article · Sun Jun 15 00:00:00 EDT 2014 · Nuclear Data Sheets

DOI:https://doi.org/10.1016/j.nds.2014.12.016· OSTI ID:1185479

Williams, M. L. ^[1]; Wiarda, D. ^[1]; Ilas, G. ^[1]; Marshall, W. J. ^[1]; Rearden, B. T. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Recently, we processed a new covariance data library based on ENDF/B-VII.1 for the SCALE nuclear analysis code system. The multigroup covariance data are discussed here, along with testing and application results for critical benchmark experiments. Moreover, 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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA)
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1185479
• Alternate ID(s): OSTI ID: 1556225
• Journal Information: Nuclear Data Sheets, Vol. 123, Issue C; ISSN 0090-3752
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

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