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This study analyzes accident progression under different decay heat power levels during a loss of residual heat removal system (RHR) accident in the mid-loop operation of a CPR1000 pressurized water reactor (PWR) nuclear power plant (NPP) using the CATHARE v1.3 code. Key parameters, including core boiling time, upper plenum water level, and core uncovery time, are calculated for decay heat power levels corresponding to different post-shutdown times (2–10 days). The results demonstrate that decay heat power significantly affects core uncovery time. Safety injection is evaluated as a mitigation measure to prevent core melting, and sensitivity analysis of injection timing under varying decay heat levels reveals that the latest allowable injection time is closely related to decay heat magnitude.

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Study on the Effect of Different Decay Heat Levels on Accident Progression During Mid-loop Operation of CPR1000

  • 会议论文

  • 发表日期：

    2026年

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  • Xiaofeng Ju,
  • Yongxiang Wang,
  • Yong Zhang,
  • Liangwang Xu,
  • Jian Zhang,
  • Xu Yang,
  • Jun Wei,
  • Dingfang Xu

摘要

This study analyzes accident progression under different decay heat power levels during a loss of residual heat removal system (RHR) accident in the mid-loop operation of a CPR1000 pressurized water reactor (PWR) nuclear power plant (NPP) using the CATHARE v1.3 code. Key parameters, including core boiling time, upper plenum water level, and core uncovery time, are calculated for decay heat power levels corresponding to different post-shutdown times (2–10 days). The results demonstrate that decay heat power significantly affects core uncovery time. Safety injection is evaluated as a mitigation measure to prevent core melting, and sensitivity analysis of injection timing under varying decay heat levels reveals that the latest allowable injection time is closely related to decay heat magnitude.