Living PSA program: LIPSAS development for safety management of an LMFBR plant
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
- 2. O-arai Engineering Center, Ibaraki (Japan)
Description
During construction and subsequent operation of a nuclear power plant, many changes occur in components, systems and operating procedures, which continuously modify the configuration of the power plant. A living PSA program can assess and manage safety-related operations and plant changes by adequately reproducing plant models and structured databases corresponding to the changes in system configuration. A living PSA system, LIPSAS, has been developed for the Japanese prototype liquid metal-cooled fast-breeder reactor (LMFBR), Monju, which is in the preoperation functional test stage. In order to utilize the LIPSAS as a risk management tool, equations for the schematic time history of the plant risk level and the relative risk criteria have been developed. Experience with LIPSAS shows that this program is a prospective tool to support decisions that affect plant safety, although a continuing and significant resource commitment of the operations staff at the site is still required. (author)
Additional details
Publishing Information
- Journal Title
- Reliability Engineering and System Safety
- Journal Volume
- 44
- Journal Issue
- 3
- Journal Page Range
- p. 325-334.
- ISSN
- 0951-8320
- CODEN
- RESSEP
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 26045259
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- LMFBR TYPE REACTORS; PROBABILISTIC ESTIMATION; SAFETY ANALYSIS
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTORS