船用核动力内部事件一级概率安全分析

Level 1 probabilistic safety analysis of internal event in marine nuclear power plants

    摘要
  • 摘要:
      目的  旨在采用概率安全分析方法来全面审查船用核动力装置的安全性。
      方法  为此，建立船用核动力装置内部事件功率工况的一级概率安全分析（PSA）模型，针对可能引起反应堆堆芯损伤的17组始发事件，建立17棵事件树；针对8个前沿/支持系统，建立42棵故障树，进而对船用核动力装置进行一级PSA分析。
      结果  计算结果表明：堆芯损伤频率（CDF）为4.38×10–6/堆年，并确定了各始发事件组对CDF的贡献；根据重要度分析结果，人误事件和电力系统故障是对CDF贡献最大的2个因素；根据敏感性分析结果，接入第3台柴油发电机可以显著降低堆芯损伤的概率。
      结论  研究成果可为船用核动力装置的安全性设计提供参考。

     

    Abstract:
      Objectives  This paper uses the probabilistic safety analysis method to review the safety of marine nuclear power plants (MNPPs).
      Methods  The relevant data of nuclear power plant systems and equipment is referenced to establish a Level 1 probabilistic safety analysis (PSA) model of the internal event power conditions of MNPPs. For the 17 groups of initial events that may cause reactor core damage, 17 event trees are established, along with 42 fault trees for the eight front/support systems, and then conduct a Level 1 PSA analysis.
      Results  The core damage frequency (CDF) is calculated as 4.38×10–6/(reactor year), and the contribution of each initial event group to the CDF is determined. According to importance analysis, human error events and power system faults are the two factors that contribute the most to the CDF of MNPPs. Sensitivity analysis finds that connecting a third diesel generator can considerably reduce the CDF.
      Conclusions  The results of this study can provide references for the safety design of MNPPs.

     

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