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:
-
- 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}
}
Free Publicly Available Full Text
Publisher's Version of Record
Other availability
Cited by: 2 works
Citation information provided by
Web of Science
Web of Science
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.