BEPU methods and combining of uncertainties
Description
After approval of the revised rule on the acceptance of emergency core cooling system (ECCS) performance in 1988 there has been significant interest in the development of codes and methodologies for best-estimate loss-of-coolant accident (LOCAs) analyses. The Code Scaling, Applicability and Uncertainty (CSAU) evaluation method was developed and demonstrated for large-break (LB) LOCA in a pressurized water reactor. Later several new best estimate plus uncertainty methods (BEPUs) were developed in the world. The purpose of the paper is to identify and compare the statistical approaches of BEPU methods and present their important plant and licensing applications. The study showed that uncertainty analysis with random sampling of input parameters and the use of order statistics for desired tolerance limits of output parameters is today commonly accepted approach. The existing BEPU methods seems mature enough while the future research may be focused on the codes with internal assessment of uncertainty. (author)
Additional details
Publishing Information
- Imprint Title
- BE-2004: International meeting on updates in best estimate methods in nuclear installation safety analysis. Proceedings
- Imprint Pagination
- 376 p.
- Journal Page Range
- p. 103-110
Conference
- Title
- International meeting on updates in best estimate methods in nuclear installation safety analysis
- Acronym
- BE-2004
- Dates
- 14-18 Nov 2004
- Place
- Washington, DC (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36058519
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ECCS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; RELIABILITY; SAFETY STANDARDS; STATISTICS; TOLERANCE
- Descriptors DEC
- ACCIDENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MATHEMATICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; STANDARDS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 34 refs, 1 fig