Published 1995
| Version v1
Miscellaneous
Reliability analysis of emergency diesel generators of Kori Nuclear units 3 and 4
- 1. Korea Atomic Energy Research Inst., Integrated Nuclear Safety Assessment, Taejon (Korea, Republic of)
Description
This paper presents reliability analysis results and the insight gained for the emergency diesel generators (EDGs) of Kori Nuclear Power Units 3 and 4. Probabilistic safety assessment (PSA) for a nuclear power plant needs plant-specific data. In Kori Units 3 and 4 PSA, a station blackout sequence was judged to be the most dominant contributor to the core damage frequency. Therefore, there was an effort in plant-specific data collection and analysis on EDGs and Loss of Off-Site Power events. For the reliability analysis of EDG, the start failure probability, the repair time after start failure, and finally the maintenance unavailability are estimated based on the collected data. (author)
Additional details
Publishing Information
- Imprint Title
- ICONE-3: Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. Volume 3
- Imprint Pagination
- 534 p.
- Journal Page Range
- p. 1289-1293
Conference
- Title
- 3. JSME/ASME joint international conference on nuclear engineering
- Acronym
- ICONE-3
- Dates
- 23-27 Apr 1995
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 38022589
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AVAILABILITY; DATA ACQUISITION; DIESEL ENGINES; FAILURES; KORI-3 REACTOR; KORI-4 REACTOR; NUCLEAR POWER PLANTS; POWER LOSSES; PROBABILISTIC ESTIMATION; REACTOR CORE DISRUPTION; REACTOR MAINTENANCE; RELIABILITY; REPAIR; RISK ASSESSMENT; START-UP
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ENERGY LOSSES; ENGINES; ENRICHED URANIUM REACTORS; HEAT ENGINES; INTERNAL COMBUSTION ENGINES; LOSSES; MAINTENANCE; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs., 3 figs.