Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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The influence of the water ingression and melt eruption model on the MELCOR code prediction of molten corium-concrete interaction in the APR-1400 reactor cavity

  • Amidu, Muritala A. (Emirates Nuclear Technology Center (ENTC), Department of Nuclear Engineering, Khalifa University of Science and Technology) ;
  • Addad, Yacine (Emirates Nuclear Technology Center (ENTC), Department of Nuclear Engineering, Khalifa University of Science and Technology)
  • Received : 2021.04.26
  • Accepted : 2021.09.29
  • Published : 2022.04.25
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Abstract

In the present study, the cavity module of the MELCOR code is used for the simulation of molten corium concrete 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 previous MELCOR Simulation of APR1400 under LB-LOCA accident, the ex-vessel phases of the accident sequences with long-term MCCI are recalculated with stand-alone cavity package of the MELCOR code to investigate the 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, the incorporation of these models in the new release of MELCOR code has led to the reduction of the maximum ablation depth in radial and axial directions by ~38% and ~32%, respectively. These impacts are substantial enough to change the conclusions earlier reached by researchers who had used the older versions of the MELCOR code for their studies. and it could also impact the estimated cost of the severe accident mitigation system in the APR1400 reactor.

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References

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