An introductory course of the probabilistic safety assessment (PSA) for LWR. (1) The progress and fundamental philosophy of the application of PSA methodology
Description
The probabilistic safety assessment (PSA) methodology has been well developed and in several countries risk information derived by the probabilistic assessment has been used for making nuclear safety assurance activities reasonable and efficient. The USA has developed risk informed regulation for the purposes of making the regulation more effective so as to provide appropriate allocation of regulatory resources, improvement of plant maintenance rules, reactor oversight process, etc., which leads to current high performance of nuclear power plants in USA. In Japan risk informed approach has been positively studied and then an introductory course of the PSA methodology as its basis was prepared in serial form. This is the first issue showing its progress and fundamental philosophy. (T. Tanaka)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.48.190Abstract (Japanese)
確率論的安全評価(Probabilistic Safety Assessmet: PSA)技術の進歩により、いくつかの国では、確率論的評価によって得られたリスク情報が原子力安全保証活動の合理化·効率化に利用されてきた。米国では、規制資源を適切に配分するために、規制をより効果的にする目的でリスク情報を用いた規制を策定し、プラント保守規則、原子炉監視プロセス等を改善し、現在の米国の原子力発電所の高稼働率につながっている。わが国でもリスク情報の活用に向けて精力的な活動が進められており、PSA技術はその根幹となる技術なので、PSA技術の連載講座が企画された。本号は、その経過と基本的な考え方を示す第1号である。(日本)Additional details
Additional titles
- Original title (Japanese)
- 軽水炉の確率論的安全評価 (PSA) 入門 第1回 PSA技術活用の経緯と基本的考え方
Identifiers
- DOI
- 10.3327/jaesj.48.190;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 48
- Journal Issue
- 3
- Journal Page Range
- p. 190-196
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54068915
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- HAZARDS; HUMAN FACTORS; IN-SERVICE INSPECTION; MAINTENANCE; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; PUBLIC OPINION; REACTOR SAFETY; RISK ASSESSMENT; SAFETY STANDARDS; SOURCE TERMS
- Descriptors DEC
- CALCULATION METHODS; INSPECTION; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; STANDARDS; THERMAL POWER PLANTS
Optional Information
- Notes
- 10 refs., 2 figs., 2 tabs.; This record replaces 37080260