两种安全级仪控系统拒动率计算方法的比较  

Reliability Modeling and Analysis of Digital Reactor Protection System in Nuclear Power Plant

作　　者：张蔚 张淑慧 徐冬苓 Zhang Wei;Zhang Shuhui;Xu Dongling(Shanghai Nuclear Engineering Research&Design Institute CO.,LTD.,Shanghai,200233,China)

机构地区：[1]上海核工程研究设计院有限公司,上海200233

出　　处：《仪器仪表用户》2021年第1期60-64,共5页Instrumentation

摘　　要：目前IEC61508中的原理与方法已经被国际上流程工业、机械工业、医药、交通等与安全相关的控制领域广泛接受,但是在核电仪控领域,相比较故障树、可靠性框图、马尔科夫等可靠性计算方法,IEC61508的应用并不广泛。因此,本文采用IEC61508第六部分对典型的核电厂反应堆保护系统可靠性进行计算,并与可靠性框图计算方法比较,验证IEC61508中的可靠性计算结果相比可靠性框图计算数量级一致且略微保守,可以在核电仪控领域推广使用。At present,the principles and methods of IEC61508 have been widely accepted in the international process industry,machinery industry,medicine,transportation and other safety related control fields.However,in the field of nuclear power I&C,compared with the reliability calculation methods such as fault tree,reliability block diagram and Markov,IEC61508 is not widely used.Therefore,in this paper,IEC61508 Part VI is used to calculate the reliability of typical nuclear power plant reactor protection system,and compared with the reliability block diagram calculation method,the reliability calculation results in IEC61508 are consistent in order of magnitude and slightly conservative,which can be widely used in the field of nuclear power I&C.

关 键 词：可靠性分析 可靠性模型 IEC61508 反应堆保护系统 不可用性 

分 类 号：TL36[核科学技术—核技术及应用]