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

Abstract

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.

Authors:
 [1];  [1];  [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1185479
Alternate Identifier(s):
OSTI ID: 1556225
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Data Sheets
Additional Journal Information:
Journal Volume: 123; Journal Issue: C; Journal ID: ISSN 0090-3752
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Williams, M. L., Wiarda, D., Ilas, G., Marshall, W. J., and Rearden, B. T. Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization. United States: N. p., 2014. Web. doi:10.1016/j.nds.2014.12.016.
Williams, M. L., Wiarda, D., Ilas, G., Marshall, W. J., & Rearden, B. T. Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization. United States. https://doi.org/10.1016/j.nds.2014.12.016
Williams, M. L., Wiarda, D., Ilas, G., Marshall, W. J., and Rearden, B. T. Sun . "Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization". United States. https://doi.org/10.1016/j.nds.2014.12.016. https://www.osti.gov/servlets/purl/1185479.
@article{osti_1185479,
title = {Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization},
author = {Williams, M. L. and Wiarda, D. and Ilas, G. and Marshall, W. J. and Rearden, B. T.},
abstractNote = {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.},
doi = {10.1016/j.nds.2014.12.016},
journal = {Nuclear Data Sheets},
number = C,
volume = 123,
place = {United States},
year = {Sun Jun 15 00:00:00 EDT 2014},
month = {Sun Jun 15 00:00:00 EDT 2014}
}

Journal Article:

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Cited by: 2 works
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