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A Study on the Applicability of MELCOR to Molten Core-Concrete Interaction Under Severe Accidents
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  • A Study on the Applicability of MELCOR to Molten Core-Concrete Interaction Under Severe Accidents
  • A Study on the Applicability of MELCOR to Molten Core-Concrete Interaction Under Severe Accidents
저자명
Kim. Ju-Youl,Chung. Chang-Hyun,Lee. Byung-Chul
간행물명
Journal of the Korean Nuclear Society
권/호정보
2000년|32권 5호|pp.425-432 (8 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

It has been an essential part for the safety assessment of nuclear power plants to understand various phenomena associated with the molten core-concrete interaction(MCCI) under severe accidents. In this study, the severe accident analysis code MELCOR was used to simulate the MCCI experiments such as SWISS and SURC test series which had been performed in Sandia National Laboratories(SNL). The calculation results were compared with corresponding experimental data such as melt temperature, concrete ablation distance, gas generation rate, and aerosol release rate. Good agreements were observed between MELCOR calculation and experimental data. The melt pool was sustained within the range of high temperature and the concrete ablation occurred continuously. The gas generation and aerosol release were under the influence of melt temperature and overlying water pool, respectively.