Containment severe accident management strategies for PWR plants in Japan
Description
Five Japanese PWR utilities have conducted the joint studies on containment severe accident management for PWR plants in Japan. The utilities have discussed the severe accident management strategies for 4 typical PWR plants from the view of in-house safety activities. Knowledge obtained from the results of PSA and severe accident studies has been systematically investigated, and the event sequences leading to core damage or containment vessel (CV) failure were classified into several categories. Then, the accident management strategies against the dominant sequences were specified. The dominant physical events leading to CV failure were classified into 9 categories. Four candidates for accident element measures against those events were selected, and their effectiveness, feasibility and influences on existing safety functions have been identified: CV cooling by natural convection, water injection into CV, forced depressurization of primary system, controlled burning of hydrogen (applied only for the plants with ice condenser CV)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the specialist meeting on selected containment severe accident management strategies
- Imprint Pagination
- 358 p.
- Journal Page Range
- p. 85-92
- ISSN
- 1104-1374
- Report number
- NEA-CSNI-R--1995-3
Conference
- Title
- Specialist meeting on selected containment severe accident management strategies
- Dates
- 13-15 Jun 1994
- Place
- Stockholm (Sweden)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 42083651
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; CONTAINMENT; DEPRESSURIZATION; EMERGENCY PLANS; JAPAN; NATURAL CONVECTION; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; RADIATION PROTECTION; REACTOR ACCIDENTS; REACTOR OPERATION; REACTOR SAFETY; RECOMMENDATIONS; SAFETY ENGINEERING; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- ACCIDENTS; ASIA; CALCULATION METHODS; CONVECTION; DEVELOPED COUNTRIES; ENERGY TRANSFER; ENGINEERING; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MANAGEMENT; MASS TRANSFER; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 refs.
- Secondary number(s)
- SKI-R--95-34-SE