Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Severe accident analysis induced by secondary pipeline break in a small modular PWR

  • Xiaolong Bi (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, and Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University) ;
  • Jie Chen (Instrument and Control Design Institute, Beijing Nuclear Engineering Research and Design Institute, China Nuclear Power Engineering Co., Ltd.) ;
  • Peiwei Sun (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, and Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University) ;
  • Xinyu Wei (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, and Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University)
  • Received : 2023.11.12
  • Accepted : 2024.05.25
  • Published : 2024.10.25
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Abstract

The small modular PWR (SMPWR) usually adopts integral design. Under severe accident, the system responses are different from those large PWRs. It is necessary to study the severe accident behavior of the SMPWR. A MELCOR model is developed for SMPWR and its steady-state results are in good agreement with the design values. Severe accidents induced by secondary pipeline break accidents are simulated, and no pressure relief measures are taken to keep the primary loop under high pressure. The mitigation effects of passive containment air cooling system (PAS) and passive cavity injection system (PCIS) are evaluated under different cases. The results show that under high pressure conditions, PCIS can effectively cool the lower head. The earlier the PCIS operates, the more significant the mitigation effect can be. In addition, PAS can effectively reduce the peak pressure and temperature in the containment. This study can provide a reference for the formulation of severe accident management guidelines on SMPWRs.

Keywords

References

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