Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization
Journal Article
·
· Nuclear Data Sheets
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
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.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- Grant/Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1185479
- Alternate ID(s):
- OSTI ID: 1556225
- Journal Information:
- Nuclear Data Sheets, Vol. 123, Issue C; ISSN 0090-3752
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Cited by: 2 works
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