HRA方法对核电厂数字化事故规程的适用性研究  

Applicability of Methods for Human Reliability Analysis for Computerized Procedures in Nuclear Power Plants

作　　者：青涛[1] 张力[1,2] 戴立操[1] Qing Tao Zhang Li Dai Licao(College of Nuclear Science anti Technology, University of South China, Hengyang, Hunan, 421001,China Hunan Institute of Technology, Hengyang, Hunan, 421002, China)

机构地区：[1]南华大学核科学技术学院,湖南衡阳421001 [2]湖南工学院,湖南衡阳421002

出　　处：《核动力工程》2017年第3期94-98,共5页Nuclear Power Engineering

基　　金：国家自然科学基金资助项目(71071051;71371070);岭东核电有限公司科研项目(KR70543)

摘　　要：分析数字化规程与纸质规程在人因工程学上的差异,认为事故规程数字化后需新考虑的行为形成因子。据此对几种常用的人因可靠性分析(HRA)方法进行比较分析。除人因失误分析技术(ATHEANA)外,常用的HRA方法用于数字化事故规程都存在比较明显的问题。ATHEANA由于其未划分具体的行为类型和行为形成因子(PSFs),在对基于数字化规程的HRA分析中有一定灵活性,相对能作为较理想的备选方法。HRA分析的最大困难是基础数据的获取,考虑数字化规程下操纵员行为特征的HRA方法的数据获取也应当成为接下来主要的研究内容。This paper analyzed the differences of digital procedure and papery procedure from the perspective of human factor engineering, and put forward the additional performance shape factors the digitized accident procedure need to consider. Several commonly used human reliability analysis （HRA） methods are comparatively analyzed. In addition to A Technique for Human Error Analysis （ATHEANA）, the common HRA method used in the digital procedure has obvious problems. ATHEANA is with a certain flexibility and can be used as an alternative method for HRA analysis based on the digital procedure because it is not divided into specific behavior types and PSFs. The biggest difficulty of HRA analysis is to obtain the basic data. The data acquisition of I-IRA method considering the behavior characteristics of the operator under the digital procedure should also be the main research direction.

关 键 词：人因可靠性分析(HRA) 数字化 事故规程 先进主控室 

分 类 号：TL364.5[核科学技术—核技术及应用]