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中广核工程设计有限公司上海分公司,上海,200241
Published:10 September 2015
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LIU Jingjing, WANG Chengzhang, XU Zhixin. Probabilistic safety analysis of design improvement of IRWST sub-system[J]. Nuclear techniques, 2015, 38(9): 090605
LIU Jingjing, WANG Chengzhang, XU Zhixin. Probabilistic safety analysis of design improvement of IRWST sub-system[J]. Nuclear techniques, 2015, 38(9): 090605 DOI: 10.11889/j.0253-3219.2015.hjs.38.090605.
根据一级概率安全分析(Probabilistic Safety Analysis
PSA)的结果,安全壳内置换料水箱(In-containment Refueling Water Storage Tank
IRWST)子系统的初始设计导致安注管线破裂(Safety Injection Line Break
SI-LB)始发事件对堆芯损坏频率(Core Damage Frequency
CDF)有较大的贡献。本文提出了IRWST子系统的设计改进方案,将IRWST水箱内的滤网由两个(A/B)增加为三个(A/B/C),并通过管线实现滤网之间的相互连接。通过重新构建故障树对改进后的IRWST子系统进行建模分析,并对相应的事件树以及一级PSA模型进行详细的定量化计算。结果表明,IRWST子系统这一改进能够显著降低堆芯损坏风险。IRWST子系统的改进将SI-LB始发事件的CDF降低了53.5%,将整个一级PSA的CDF降低了21.5%。
Background: Probabilistic safety analysis (PSA) methodology is widely used to assess the risk of nuclear power plant (NPP). Based on the results of level 1 PSA
the vulnerability of In-containment Refueling Water Storage Tank (IRWST) sub-system makes the initiating event Safety Injection Line Break (SI-LB) contributing significantly to core damage frequency (CDF). Purpose: This study aims to find the vulnerability of IRWST design by PSA assessment
and provide design improvement suggestion to reduce the risk of NPP. Methods: PSA methodology is used to evaluate the design improvement of IRWST
which is implemented by adding a third strainer (strainer C)
and the three strainers are connected to each other. Fault trees of IRWST are rebuilt
and related event trees and level 1 PSA model are recalculated. Results: Quantitative result shows that the contribution of SI-LB initiating event to CDF is reduced by 53.5% and the total CDF is reduced by 21.5%. Conclusion: Design improvement of IRWST sub-system greatly reduced the core damage risk. Abstract
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