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 language | English |
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Pages (from-to) | 341-345 |
Number of pages | 5 |
Journal | Nuclear Data Sheets |
Volume | 118 |
Issue number | 1 |
DOIs | |
State | Published - 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.
Funders | Funder number |
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UT-Battelle LLC | |
U.S. Nuclear Regulatory Commission |