典型核电厂双相停堆工况LOCA缓解措施对比研究

Comparison Study of LOCA Mitigation Under NS/SG Mode for Typical NPPs

  • 摘要: 本文选取VVER-1000堆型和二代国产两环路核电厂,采用RELAP5程序研究分析了双相停堆工况下等效直径为10~100 mm破口失水事故(LOCA)进程。计算结果表明,核电厂安全系列设置和整定信号等设计区别对操纵员不干预时间和有效缓解措施有较大影响。如借鉴VVER-1000相关设计理念对国产两环路核电厂做出适当调整,可增加两环路核电厂中、小LOCA的安全裕量。本文研究结果可为三代自主化核电厂研发和事故管理导则的研究工作提供参考,并为增强反应堆的安全性提供思路。

     

    Abstract: The different characteristics of VVER-1000 and Chinese typical two-loop NPPs in the case of LOCA between 10-100 mm under NS/SG mode were researched by using RELAP5 code. The computation result shows that the design differences, especially the safety features and trip signals could significantly influence the operator time windows and effective mitigation measures. The same sequence of Chinese typical two-loop NPPs with adjusted parameters according to the VVER-1000 design concept was calculated, and the results show that the safety margin could notably increase. Thus, this article indicates a practical way to enhance current NPP safety, and would be helpful for developing Chinese 3rd generation NPP and accident manage guidance.

     

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