Results of the back-end analysis for the YGN 3 and 4 units
Creators
- 1. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)
Description
The back-end analysis for the internal events of the Yonggwang nuclear units 3 and 4 (YGN 3 and 4) was done as a part of individual plant examination (IPE) in Korea. To quantify the PDSs, CETs, and source term categories, the NUCAP+ computer code was used. The MAAP computer code was used to analyze the physico-chemical phenomena in the containment. The core damage frequency (CDF) for the internal events is 7.58x10-6/year and the containment failure (CF) probability is 1.66x10-6/year. The early containment failure contributes least (0.7%) and its probability is 5.31x10-8/year. The bypass sequence, whose contribution is about 10%, is the major failure mode. Nineteen source term categories were defined to analyze the source term release characteristics. (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. 1393-1397
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
- 38008920
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONTAINMENT; DAMAGE; FAILURE MODE ANALYSIS; FAILURES; FREQUENCY ANALYSIS; PROBABILITY; REACTOR CORES; SOURCE TERMS; YONGGWANG-3 REACTOR; YONGGWANG-4 REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 1 fig., 4 tabs.