Validation of keff Calculations for Extended BWR Burnup Credit
Abstract
The US Nuclear Regulatory Commission and consensus standards recommend validation of the numerical methods used in criticality safety analyses. This validation requires the comparison of computational results with measurements of physical systems which are neutronically similar to those used in the safety analysis being performed. To this end, this document examines the methods available to generate sensitivity data to help identify systems similar to spent boiling- water reactor (BWR) fuel in a flooded spent nuclear fuel transportation or storage cask. A large number of critical benchmark experiments are surveyed using sensitivity/uncertainty (S/U) techniques to assess their applicability to BWR burnup credit (BUC) beyond the burnup of peak reactivity. Multiple burnups of BWR assemblies are considered herein, as well as the actinide-only (AO) and actinide-and-major-fission-product (AFP) isotope sets. Sample validations are completed for representative application models to demonstrate that appropriate validation is possible and to indicate the bias and bias uncertainty values expected for related applications.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC)
- OSTI Identifier:
- 1492185
- Report Number(s):
- ORNL/TM-2018/797
- DOE Contract Number:
- AC05-00OR22725
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
Citation Formats
Marshall, William J., Clarity, Justin B., and Bowman, Stephen M. Validation of keff Calculations for Extended BWR Burnup Credit. United States: N. p., 2018.
Web. doi:10.2172/1492185.
Marshall, William J., Clarity, Justin B., & Bowman, Stephen M. Validation of keff Calculations for Extended BWR Burnup Credit. United States. https://doi.org/10.2172/1492185
Marshall, William J., Clarity, Justin B., and Bowman, Stephen M. 2018.
"Validation of keff Calculations for Extended BWR Burnup Credit". United States. https://doi.org/10.2172/1492185. https://www.osti.gov/servlets/purl/1492185.
@article{osti_1492185,
title = {Validation of keff Calculations for Extended BWR Burnup Credit},
author = {Marshall, William J. and Clarity, Justin B. and Bowman, Stephen M.},
abstractNote = {The US Nuclear Regulatory Commission and consensus standards recommend validation of the numerical methods used in criticality safety analyses. This validation requires the comparison of computational results with measurements of physical systems which are neutronically similar to those used in the safety analysis being performed. To this end, this document examines the methods available to generate sensitivity data to help identify systems similar to spent boiling- water reactor (BWR) fuel in a flooded spent nuclear fuel transportation or storage cask. A large number of critical benchmark experiments are surveyed using sensitivity/uncertainty (S/U) techniques to assess their applicability to BWR burnup credit (BUC) beyond the burnup of peak reactivity. Multiple burnups of BWR assemblies are considered herein, as well as the actinide-only (AO) and actinide-and-major-fission-product (AFP) isotope sets. Sample validations are completed for representative application models to demonstrate that appropriate validation is possible and to indicate the bias and bias uncertainty values expected for related applications.},
doi = {10.2172/1492185},
url = {https://www.osti.gov/biblio/1492185},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Dec 01 00:00:00 EST 2018},
month = {Sat Dec 01 00:00:00 EST 2018}
}