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원자력발전소의 정량적인 안전 해석을 위한 사건수목 기법의 응용
Application of Event Tree Technique for Quantification of Nuclear Power Plant Safety
김시달(See Darl Kim),진영호(Young Ho Jin),김동하(Dong Ha Kim),박수용(Soo Yong Park),박종화(Jong Hwa Park)
UCI I410-ECN-0102-2009-530-005993125
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Probabilistic Safety Assessment (PSA) is an engineering analysis method to identify possible contributors to the risk from a nuclear power plant and now it has become a standard tool in safety evaluation of nuclear power plants. PSA consists of three phases named as Level 1, 2 and 3. Level 2 PSA, mainly focused in this paper, uses a step-wise approach. At first, plant damage states (PDSs) are defined from the Level 1 PSA results and they are quantified. Containment event tree (CET) is then constructed considering the physico-chemical phenomena in the containment. The quantification of CET can be assisted by a decomposition event tree (DET). Finally, source terms are quantitatively characterized by the containment failure mode. As the main benefit of PSA is to provide insights into plant design, performance and environmental impacts, including the identification of the dominant risk contributors and the comparison of options for reducing risk, this technique is expected to be applied to the industrial safety area.

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