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

M. L. Williams; D. Wiarda; G. Ilas; W. J. Marshall; B. T. Rearden

doi:10.1016/j.nds.2014.12.016

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

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

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

Abstract

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

Original language	English
Pages (from-to)	92-96
Number of pages	5
Journal	Nuclear Data Sheets
Volume	123
DOIs	https://doi.org/10.1016/j.nds.2014.12.016
State	Published - Jan 1 2015

Funding

Acknowledgements: This work was sponsored by the US Department of Energy, Nuclear Criticality Safety Program. ∗ Corresponding author: [email protected]; This manuscript has been authored by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the US Department of Energy. The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes.

Access to Document

10.1016/j.nds.2014.12.016

Cite this

@article{7f2a329cee74442fa001d7a0ec8b3219,

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

abstract = "A new covariance data library based on ENDF/B-VII.1 was recently processed for the SCALE nuclear analysis code system. The multigroup covariance data are discussed here, along with testing and application results for critical benchmark experiments. 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.",

author = "Williams, {M. L.} and D. Wiarda and G. Ilas and Marshall, {W. J.} and Rearden, {B. T.}",

note = "Publisher Copyright: {\textcopyright} 2014 Elsevier Inc.",

year = "2015",

month = jan,

day = "1",

doi = "10.1016/j.nds.2014.12.016",

language = "English",

volume = "123",

pages = "92--96",

journal = "Nuclear Data Sheets",

issn = "0090-3752",

publisher = "Elsevier",

}

TY - JOUR

T1 - Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization

AU - Williams, M. L.

AU - Wiarda, D.

AU - Ilas, G.

AU - Marshall, W. J.

AU - Rearden, B. T.

PY - 2015/1/1

Y1 - 2015/1/1

N2 - A new covariance data library based on ENDF/B-VII.1 was recently processed for the SCALE nuclear analysis code system. The multigroup covariance data are discussed here, along with testing and application results for critical benchmark experiments. 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.

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

UR - http://www.scopus.com/inward/record.url?scp=84920837551&partnerID=8YFLogxK

U2 - 10.1016/j.nds.2014.12.016

DO - 10.1016/j.nds.2014.12.016

M3 - Article

AN - SCOPUS:84920837551

SN - 0090-3752

VL - 123

SP - 92

EP - 96

JO - Nuclear Data Sheets

JF - Nuclear Data Sheets

ER -

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

Abstract

Funding

Access to Document

Other files and links

Fingerprint

Cite this