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The Generation II reactors, represented by the Fangjiashan Unit 1&2 and Hainan Changjiang Unit 1&2, are currently among the main operating models in China, which is a typical pressurized water reactor (PWR) widely used worldwide, holding a significant position among modern nuclear plants. The plants are designed with multiple redundant safety systems and measures to prevent nuclear accidents. After the Fukushima Daiichi accident occurred, improvements were made to the operating reactors, including the addition of various mobile facilities. The presented paper employs Level 2 Probabilistic Safety Assessment (PSA) to analyze the accident mitigation capabilities under core meltdown scenarios within internal events. With the Severe Accident Management Guidelines (SAMG), the presented work models and analyzes the feasibility and effectiveness of various measures to be implemented in response to severe accidents. The impact of different accident scenarios on the plants are conducted to reveal the capabilities of accident management systems and mobile facilities for mitigating the consequences of severe accidents. By using Level 2 PSA, an in-depth evaluation of the plants’ abilities to respond to severe accidents are provided, offering important insights for improving nuclear plant safety and serving as a reference for the design and evaluation of future nuclear plants.

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Analysis of Severe Accident Risk of Gen II Nuclear Power Plants Based on Internal Event Level 2 Probabilistic Safety Assessment

  • 会议论文

  • 发表日期：

    2026年

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  • Shujie Guo,
  • Yun Yu,
  • Jingyi Liang,
  • Wenjing Li,
  • Wei Wei,
  • Xinli Yu

摘要

The Generation II reactors, represented by the Fangjiashan Unit 1&2 and Hainan Changjiang Unit 1&2, are currently among the main operating models in China, which is a typical pressurized water reactor (PWR) widely used worldwide, holding a significant position among modern nuclear plants. The plants are designed with multiple redundant safety systems and measures to prevent nuclear accidents. After the Fukushima Daiichi accident occurred, improvements were made to the operating reactors, including the addition of various mobile facilities. The presented paper employs Level 2 Probabilistic Safety Assessment (PSA) to analyze the accident mitigation capabilities under core meltdown scenarios within internal events. With the Severe Accident Management Guidelines (SAMG), the presented work models and analyzes the feasibility and effectiveness of various measures to be implemented in response to severe accidents. The impact of different accident scenarios on the plants are conducted to reveal the capabilities of accident management systems and mobile facilities for mitigating the consequences of severe accidents. By using Level 2 PSA, an in-depth evaluation of the plants’ abilities to respond to severe accidents are provided, offering important insights for improving nuclear plant safety and serving as a reference for the design and evaluation of future nuclear plants.