Applications of nuclear data covariances to criticality safety and spent fuel characterization

M. L. Williams, G. Ilas, W. J. Marshall, B. T. Rearden

Research output: Contribution to journalArticlepeer-review

10 Scopus citations

Abstract

Covariance data computational methods and data used for sensitivity and uncertainty analysis within the SCALE nuclear analysis code system are presented. Applications in criticality safety calculations and used nuclear fuel analysis are discussed.

Original languageEnglish
Pages (from-to)341-345
Number of pages5
JournalNuclear Data Sheets
Volume118
Issue number1
DOIs
StatePublished - Apr 2014

Funding

Acknowledgements: This work was sponsored by the U.S. Nuclear Regulatory Commission Office of Research. The authors thank Doro Wiarda for performing the benchmark critical calculations, and GRS for providing the XSUSA code that was used for sampling the nuclear data. This manuscript has been authored by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.

FundersFunder number
UT-Battelle LLC
U.S. Nuclear Regulatory Commission

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