Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1997.05a
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- Pages.464-470
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- 1997
Severe Accident Analysis for Wolsung Nuclear Power Plants
- Kwon, Jong-Jooh (Korea Electric Power Research Institute) ;
- Kim, Myung-Ki (Korea Electric Power Research Institute) ;
- Park, Byoung-Chul (Korea Electric Power Research Institute) ;
- Kim, Inn-Seock (Korea Electric Power Research Institute) ;
- Hong, Sung-Yull (Korea Electric Power Research Institute)
- Published : 1997.05.01
Abstract
Severe accident analysis has been performed for the Wolsung nuclear power plants in Korea to investigate severe accident phenomena of CANDU-600 reactors as a part of Level II PSA study. The accident sequence analyzed in this paper is loss of active heat sinks(LOAH) which is caused by loss of off-site power, diesel generators, and DC power. ISAAC (Integrated Severe Accident Analysis Code)computer code developed by KAERI (Korea Atomic Energy Research Institute) was used in this analysis. This paper describes the important thermal-hydraulics and source term behaviors in the primary system and inside containment, and the failure mechanism of calandria vessel and containment. In addition, some insights for accident management program(AMP) are also given.
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