| 核电站风险指引设备分级的方法 | |
| 赵军 ; 童节娟 ; 何旭洪 ; ZHAO Jun ; TONG Jiejuan ; HE Xuhong | |
| 2010-06-04 ; 2010-06-04 | |
| 关键词 | 设备分级 风险指引 概率风险分析(PSA) categorization risk-informed probabilistic safety analysis (PSA) TM623 |
| 其他题名 | Risk-informed SSC categorization method in nuclear power plant |
| 中文摘要 | 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. |
| 语种 | 中文 ; 中文 |
| 内容类型 | 期刊论文 |
| 源URL | [http://hdl.handle.net/123456789/36098]  |
| 专题 | 清华大学 |
| 推荐引用方式 GB/T 7714 | 赵军,童节娟,何旭洪,等. 核电站风险指引设备分级的方法[J],2010, 2010. |
| APA | 赵军,童节娟,何旭洪,ZHAO Jun,TONG Jiejuan,&HE Xuhong.(2010).核电站风险指引设备分级的方法.. |
| MLA | 赵军,et al."核电站风险指引设备分级的方法".(2010). |
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