Post-accident Human Reliability Analysis in a Chinese Nuclear Power Plant

摘要：

Human Reliability Analysis (HRA)is an important part of Probabilistic Safety Assessment (PSA)in a nuclear power plant (NPP). It can evaluate and quantify the behaviors of the operators in a main control room (MCR)to provide a safety assessment. MCR operator actions mostly fall into category C (post-accident)human factor events. The paper analyzes the post-accident operators behaviors in a quantity way and makes a classification and divides them into groups on the basis of an actual HRA analysis of a pressurized water reactor (PWR) of a certain domestic NPP in China. The basic human errors involved in NPP events and their criticality are ranked in sequence to obtain the criticality rank of operator actions to be as a basis to improve the performance of the operators including the rectification of emergency operating procedures (EOPs)and the improvement of management and training.

关键词： Post-accident HRA Basic Human Error Probability and Criticality Operators Performance

作者: Dai Licao ZhangLi

作者单位: Human Factor Institute, Nanhua University, Hengyang City, 421001, China Information Physics Engineer Human Factor Institute, Nanhua University, Hengyang City, 421001, China

会议类型: 国际会议

会议名称: ISSNP2008、CSEPC、ISOFIC2008(第二届21世纪和谐核电系统国际会议、第四届电厂控制中认知系统工程方法国际会议暨第三届未来核电厂仪表与控制国际会议)

会议地点: 哈尔滨

会议语种:英文

页码: 420-426

在线出版日期: 2008-09-08（万方平台首次上网日期，不代表论文的发表时间）