Recent results of level 1 PSA for nuclear power plants in Japan
Creators
- 1. Japan Institute of Nuclear Safety, Tokyo (Japan)
Description
This paper summarizes the recent results of level 1 probabilistic safety assessment (PSA) for nuclear power plants (NPPs) in Japan, focusing on some results at the Japan Institute of Nuclear Safety (JINS) of the Nuclear Power Engineering Test Center (NUPEC). Both governmental organizations including JINS and industry groups are carrying out Level 1 and Level 2 PSA for NPPs. It can be said that the level 1 PSA results obtained by both JINS and industry groups are approximately the same. The core damage frequencies for typical Japanese NPPs, even applying upper 5% values, are small enough to meet the International Atomic Energy Agency's proposal of the value 10-5/reactor year for future plants. The above-mentioned level 1 PSAs do not represent final ones and in the near future, will be reevaluated based on the current methodology and the domestic data bases which are now under development in Japan
Additional details
Publishing Information
- Imprint Title
- CSNI workshop on PSA applications and limitations. Proceedings
- Imprint Pagination
- 475 p.
- Journal Page Range
- p. 35-56.
- Report number
- NUREG/CP--0115
Conference
- Title
- Committee on the Safety of Nuclear Installations (CSNI) on Probabilistic Safety Assessment (PSA) applications and limitations.
- Dates
- 4-6 Sep 1990.
- Place
- Santa Fe, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23008702
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; ATWS; AVAILABILITY; BWR TYPE REACTORS; CONTAINMENT SYSTEMS; DATA BASE MANAGEMENT; DEPRESSURIZATION; DIESEL ENGINES; ERRORS; FAILURE MODE ANALYSIS; FAILURES; FAULT TREE ANALYSIS; FBR TYPE REACTORS; HIGH PRESSURE COOLANT INJECTIO; HUMAN FACTORS; JAERI; JAPANESE ORGANIZATIONS; LOSS OF COOLANT; LOW PRESSURE COOLANT INJECTION; MITIGATION; OUTAGES; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR OPERATORS; REACTOR SAFETY; RESEARCH PROGRAMS; RISK ASSESSMENT; SENSITIVITY; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; BREEDER REACTORS; CONTAINMENT; DESIGN BASIS ACCIDENTS; ECCS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; MANAGEMENT; MOTORS; NATIONAL ORGANIZATIONS; PERSONNEL; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; REMOVAL; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- SAND--90-2797; CONF-9009346--.