核电站风险指引设备分级的方法  

Risk-informed SSC categorization method in nuclear power plant

作　　者：赵军[1] 童节娟[1] 何旭洪[1] 

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《清华大学学报（自然科学版）》2007年第3期449-452,共4页Journal of Tsinghua University(Science and Technology)

摘　　要：该文通过大亚湾核电站的实例分析来探讨核电站构筑物、系统及设备(SSC)的风险指引分级方法的可操作性及在执行过程中需考虑的问题,并对实例分析的结果进行讨论,以推动此分级思想的发展。风险指引SSC分级通过定量化的概率风险分析(PSA)、纵深防御分析和敏感性分析3个步骤综合评估设备的安全重要性。实例是以大亚湾核电站辅助给水系统为对象,结果中有33%的“安全相关”设备被划分为低安全重要设备,64%的“非安全相关”设备被划分为高安全重要设备。实例研究表明,此分级方法是一个系统化的、全面的并具可操作性的流程。This paper illustrates the use of the risk-informed structure, system, and component categorizations based on a pilot study of the Chinese Daya Bay nuclear power plant. The risk-informed categorization method evaluates the risk significance of structure, system, and component using an integrated process. This process includes a probabilistic safety analysis assessment, a defense-in-depth assessment, and a risk sensitivity study. The auxiliary service water system was selected for this study. In the results, 33 % of the ＂safety related＂ components were re-categorized as having low safety significance, while 64% of the ＂non-safety related＂ components were re-categorized as having high safety significance. This study shows how risk-informed categorization provides a systematic, comprehensive, and practicable evaluation of safety systems.

关 键 词：设备分级 风险指引 概率风险分析(PSA) 

分 类 号：TL364.5[核科学技术—核技术及应用]