Applications of Probabilistic Risk Analysis in Nuclear Criticality Safety Design
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:6968027
Many documents have been prepared that try to define the scope of the criticality analysis and that suggest adding probabilistic risk analysis (PRA) to the deterministic safety analysis. The report of the US Department of Energy (DOE) AL 5481.1B suggested that an accident is credible if the occurrence probability is >1 * 10⁻6/yr. The draft DOE 5480 safety analysis report suggested that safety analyses should include the application of methods such as deterministic safety analysis, risk assessment, reliability engineering, common-cause failure analysis, human reliability analysis, and human factor safety analysis techniques. The US Nuclear Regulatory Commission (NRC) report NRC SG830.110 suggested that major safety analysis methods should include but not be limited to risk assessment, reliability engineering, and human factor safety analysis. All of these suggestions have recommended including PRA in the traditional criticality analysis.
- Research Organization:
- Ralph M. Parsons Co., Pasadena, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 6968027
- Report Number(s):
- CONF-920606--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 65
- Country of Publication:
- United States
- Language:
- English
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