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논문 기본 정보

자료유형
학술저널
저자정보
Muritala A. Amidu (Khalifa University of Science and Technology) Yacine Addad (Khalifa University of Science and Technology, P)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제54권 제4호
발행연도
2022.4
수록면
1,508 - 1,515 (8page)
DOI
https://doi.org/10.1016/j.net.2021.09.036

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초록· 키워드

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In the present study, the cavity module of the MELCOR code is used for the simulation of molten coriumconcrete interaction (MCCI) during the late phase of postulated large break loss of coolant (LB-LOCA)accident in the APR1400 reactor design. Using the molten corium composition data from previousMELCOR Simulation of APR1400 under LB-LOCA accident, the ex-vessel phases of the accident sequenceswith long-term MCCI are recalculated with stand-alone cavity package of the MELCOR code to investigatethe impact of water ingression and melt eruption models which were hitherto absent in MELCOR code. Significant changes in the MCCI behaviors in terms of the heat transfer rates, amount of gases released,and maximum cavity ablation depths are observed and reported in this study. Most especially, theincorporation of these models in the new release of MELCOR code has led to the reduction of themaximum ablation depth in radial and axial directions by ~38% and ~32%, respectively. These impacts aresubstantial enough to change the conclusions earlier reached by researchers who had used the olderversions of the MELCOR code for their studies. and it could also impact the estimated cost of the severeaccident mitigation system in the APR1400 reactor.

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