基于PSA分析结果的AP1000系统设计改进建议

发布时间：2018-05-14 12:20

  本文选题：概率安全评价 + 正常余热排出系统　； 参考：《核科学与工程》2015年04期

【摘要】：基于对AP1000一级概率安全分析(PSA)的结果,发现正常余热排出系统(RNS)的设计不足可能会导致安注管线破裂(SI-LB)始发事件对堆芯损坏频率(CDF)贡献较高。对正常余热排出系统进行适当的系统改进,采用概率安全分析的方法重新构建了改进后的RNS系统故障树及相关事件树模型,对RNS系统可靠性进行分析,并对改进后核电厂CDF、进行了计算,结果表明,RNS系统改进后可大大减少安注管破裂始发事件导致的堆芯损坏,改进后电厂堆芯损坏频率(CDF)降低29.1%。
[Abstract]:Based on the results of the first-order probabilistic safety analysis (AP1000), it is found that the inadequate design of the normal residual heat discharge system may lead to a higher contribution of the SI-LB incident to the core damage frequency. The improved RNS system fault tree and related event tree model are constructed by using probabilistic safety analysis method. The reliability of RNS system is analyzed. The results show that the improved RNS system can greatly reduce the core damage caused by the rupture of the injection pipe, and the core damage frequency of the improved power plant can be reduced by 29.1.
【作者单位】： 中广核工程设计有限公司上海分公司;
【分类号】：TM623
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本文编号：1887822