适用于数字化主控室的核电厂HRA基础数据架构研究

Study on the Framework of the Generic HRA Database for Nuclear Power Plant with Digital Main Control Room

目前国内开展核电厂人员可靠性分析(HRA)采用的人员失误概率基础数据库年限较为久远,且缺乏对于数字化主控室环境下人员失误模式的考虑。本文基于多个HRA方法及国外典型人员可靠性数据库的设计,结合国内电厂的实际情况,搭建了核电厂HRA基础数据库的框架,对于其中的绩效影响因子(PSF)架构采用数据库概念设计阶段的自顶向下设计方法,结合数字化环境下新增的人员失误模式,给出可供采集的PSF数据项,完成可适用于数字化环境的核电厂HRA基础数据库中PSF架构的搭建,并针对核电厂HRA基础数据架构着手开发相应的数据库软件,为核电厂人员可靠性数据的采集、防人因失误工作的开展提供有效支持。

The generic human error probability database used for the human reliability analysis(HRA)in nuclear power plant has a long history,and it lacks consideration of the human error mode under the digital main control room circumstances.In order to construct the framework of the generic human reliability database applicable to the digital environment,which provides effective support for the extraction of human reliability data of nuclear power plant and the prevention of human error.Based on the widely used HRA methods and the design of other typical human reliability databases,combined with the actual situation of domestic nuclear power plants,this paper constructs the framework of the generic human reliability database for nuclear power plant.For the performance shaping factor(PSF)framework,the top-down design method in the conceptual design stage of the database is adopted,and the PSF data items that can be collected are given in combination with the newly added human error model in digital environment.Then,the framework of the generic human reliability database of nuclear power plant applicable to the digital environment could be constructed,and the corresponding software is developed.The generic HRA database of nuclear power plant has been developed to provide effective support for the HRA data collection as well as to sponsor practical ways of human error reduction.