DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Historical perspectives of BEPU research in US

Abstract

Civilian nuclear energy started in earnest in the 1950s and experienced rapid growth in 1960-80s with increasingly larger reactors. These reactors were initially regulated based on the experience from the smaller reactors, but this could not be applied to the larger power reactors. Therefore, in 1974 the US Nuclear Regulatory Commission set up safety requirements based on defense in depth in 10 CFR 50.46, and set of guidance in 10 CFR 50 presented in Appendix K, for models and simulations of reactor safety analyses, to ensure conservatism in predicted safety parameters. These methods resulted in both conservative safety margins as well as economic and operational penalties. In the late 1970s and early 1980s, a large number of experiential programs provided data that allowed for the creation of best estimate models. These best estimate models showed the conservatism in Appendix K models. In 1988-89, USNRC modified the regulations and allowed the use of best estimate models provided they were coupled to a reliable and defensible measure of uncertainty in the prediction of safety parameters. This change in regulation strongly encouraged global activity for the development of best estimate codes and methods. To aide in this development, the USNRC provided one acceptablemore » approach, the Code Scaling, Acceptability and Uncertainty Evaluation Methodology (CSAU). This approach was later refined in the Evaluation Model Development and Assessment Process (EMDAP).« less

Authors:
 [1];  [2]
  1. Brookhaven National Lab. (BNL), Upton, NY (United States)
  2. US Nuclear Regulatory Commission (NRC), Rockville, MD (United States)
Publication Date:
Research Org.:
Brookhaven National Lab. (BNL), Upton, NY (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA), Office of Nonproliferation and Verification Research and Development (NA-22)
OSTI Identifier:
1601334
Report Number(s):
BNL-213628-2020-JAAM
Journal ID: ISSN 0029-5493; TRN: US2103626
Grant/Contract Number:  
SC0012704
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Engineering and Design
Additional Journal Information:
Journal Volume: 358; Journal Issue: C; Journal ID: ISSN 0029-5493
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION; 22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Rohatgi, Upendra S., and Kaizer, Joshua S. Historical perspectives of BEPU research in US. United States: N. p., 2019. Web. doi:10.1016/j.nucengdes.2019.110430.
Rohatgi, Upendra S., & Kaizer, Joshua S. Historical perspectives of BEPU research in US. United States. https://doi.org/10.1016/j.nucengdes.2019.110430
Rohatgi, Upendra S., and Kaizer, Joshua S. Tue . "Historical perspectives of BEPU research in US". United States. https://doi.org/10.1016/j.nucengdes.2019.110430. https://www.osti.gov/servlets/purl/1601334.
@article{osti_1601334,
title = {Historical perspectives of BEPU research in US},
author = {Rohatgi, Upendra S. and Kaizer, Joshua S.},
abstractNote = {Civilian nuclear energy started in earnest in the 1950s and experienced rapid growth in 1960-80s with increasingly larger reactors. These reactors were initially regulated based on the experience from the smaller reactors, but this could not be applied to the larger power reactors. Therefore, in 1974 the US Nuclear Regulatory Commission set up safety requirements based on defense in depth in 10 CFR 50.46, and set of guidance in 10 CFR 50 presented in Appendix K, for models and simulations of reactor safety analyses, to ensure conservatism in predicted safety parameters. These methods resulted in both conservative safety margins as well as economic and operational penalties. In the late 1970s and early 1980s, a large number of experiential programs provided data that allowed for the creation of best estimate models. These best estimate models showed the conservatism in Appendix K models. In 1988-89, USNRC modified the regulations and allowed the use of best estimate models provided they were coupled to a reliable and defensible measure of uncertainty in the prediction of safety parameters. This change in regulation strongly encouraged global activity for the development of best estimate codes and methods. To aide in this development, the USNRC provided one acceptable approach, the Code Scaling, Acceptability and Uncertainty Evaluation Methodology (CSAU). This approach was later refined in the Evaluation Model Development and Assessment Process (EMDAP).},
doi = {10.1016/j.nucengdes.2019.110430},
journal = {Nuclear Engineering and Design},
number = C,
volume = 358,
place = {United States},
year = {2019},
month = {11}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record

Citation Metrics:
Cited by: 8 works
Citation information provided by
Web of Science

Save / Share:

Works referenced in this record:

Overview of the NURESAFE European Project
journal, September 2017


Statistical aspects of best estimate method—I
journal, June 2003


Illustration of Sampling-Based Methods for Uncertainty and Sensitivity Analysis
journal, June 2002


Application of PWR LOCA margin with the revised Appendix K rule
journal, January 1992


Determination of Appendix K Conservatisms for Westinghouse Pressurized Water Reactors Using TRAC-PD2/MOD1
journal, January 1987

  • Rohatgi, U. S.; Yuelys-Miksis, Christine; Saha, Pradip
  • Nuclear Technology, Vol. 76, Issue 1
  • DOI: 10.13182/NT87-A33895

Determination of Sample Sizes for Setting Tolerance Limits
journal, March 1941


The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis
journal, November 1998


Application of Fractional Scaling Analysis to Loss of Coolant Accidents, System Level Scaling for System Depressurization
journal, July 2009

  • Wulff, Wolfgang; Zuber, Novak; Rohatgi, Upendra S.
  • Journal of Fluids Engineering, Vol. 131, Issue 8
  • DOI: 10.1115/1.3155994

An integrated structure and scaling methodology for severe accident technical issue resolution: Development of methodology
journal, November 1998