安全壳内置换料水箱子系统设计改进的PSA评价

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 I...

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Bibliographic Details
Published in核技术 Vol. 38; no. 9; pp. 89 - 94
Main Author 刘晶晶 王成章 徐志新
Format Journal Article
LanguageChinese
Published 2015
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ISSN0253-3219

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Summary: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%。
Bibliography:PSA, IRWST sub-system, CDF
31-1342/TL
LIU Jingjing, WANG Chengzhang, XU Zhixin (China Nuclear Power Design Company, Shanghai Branch, Shanghai 200241, China)
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
ISSN:0253-3219