Published 2004 | Version v1
Miscellaneous

BEPU methods and combining of uncertainties

  • 1. Jozef Stefan Institute, Ljubljana (Slovenia)

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)

Part of:
BE-2004: International meeting on updates in best estimate methods in nuclear installation safety analysis. Proceedings

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