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System analysis (MELCOR/MAAP/CINEMA)
System analysis (MELCOR/MAAP/CINEMA)
introduction
introduction
원자력발전소 안전성 증진을 위한 중대사고 연구
Comprehensive Analysis of Severe Accidents to Enhance Nuclear Power Plant Safety
2011년 후쿠시마 원자력발전소 사고 이후, 원전 중대사고 해석에 대한 중요성이 강조되어 왔음.
이러한 중대사고 연구의 일환으로, 국내 가동원전 혹은 신규개발원전에 대한 발전소 입력모델을 개발하고, 노형별 중대사고 시나리오를 다양한 중대사고종합해석코드를 통해 분석함. 사고의 진행을 가장 효율적으로 완화할 수 있는 사고관리전략 조합을 도출.
In the aftermath of the Fukushima nuclear power plant incident in 2011, the imperative of comprehensively understanding severe accidents within the domain of nuclear power plants has been unequivocally underscored.
As part of this serious accident study, we have analyzed a severe accident scenarios for various nuclear power plants such as OPR1000, ATOM, i-SMR through various comprehensive serious accident analysis codes. Especially, a domestic analysis code, CINEMA code, has been under development in Korea, and our laboratory has been contributing on improvement of the code conducting various uncertainty analysis. The ultimate goal of these severe accident analyses is to derive the most effective accident management strategies for mitigating the accident progression.
papers
papers
1) Efficacy analysis of hydrogen mitigation measures of CANDU containment under LOCA scenario
Published article (2018)
2) Numerical analysis on in-core ignition and subsequent flame propagation to containment in OPR1000 under loss of coolant accident.
Published article (2022)
3) Assessment of corium concrete interaction and impact of water ingression mechanism using top flooding strategy for a small PWR with MELCOR 2.2.
Published article (2023)
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