Applicability Study on Human Reliability Analysis for Severe Accidents in Nuclear Power Plants

Mingsha Zhao, Shuai Chen, Jie Xu, Jianzhang Zhou, Tao Qing
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Abstract

Three severe nuclear power accidents (Fukushima accident, Chernobyl accident and Three Mile Island accident) have proved that human errors in the mitigation of severe accidents will exacerbate the deterioration of accidents and cause immeasurable consequences. Therefore, there is an urgent need for finding human reliability analysis methods to effectively analyze and predict possible human errors in severe accident mitigation.In order to compare the applicability of the Human Reliability Analysis (HRA) method under the severe accident in the nuclear power plant, this paper put forward four criteria, qualitative analysis, quantitative analysis, traceability and availability, based on the characteristics of the personnel in the process of severe accident mitigation. Several commonly used HRA methods were compared and analyzed. The results show that the common HRA methods which applied to the analysis have shortcomings, so it is necessary to establish a new HRA method, or to improve the original methods to solve the issues under severe accident conditions and the IDAC model and Phoenix HRA methodology are considered better choice. Combined with computer programs,the IDAC model can simulate the process of accident and the dynamic response of personnel, which helps to explain the dynamic interaction characteristics of human behavior and environment, but the model still has some limitations in the aspects of uncertainty analysis and simulation data availability. While Phoenix method provides some Performance influencing factors and crew failure modes that can reflect the response characteristics of emergency personnel. This applicability study can provide guidance for the establishment of HRA method in severe accidents.
核电厂重大事故人的可靠性分析的适用性研究
三起严重的核电事故(福岛核事故、切尔诺贝利核事故和三里岛核事故)证明,人为失误在缓解严重事故时,会加剧事故的恶化,造成不可估量的后果。因此,迫切需要寻找人的可靠性分析方法,以有效地分析和预测严重事故缓解中可能出现的人为错误。为了比较人类可靠性分析(HRA)方法在核电厂严重事故下的适用性,本文根据严重事故缓解过程中人员的特点,提出了定性分析、定量分析、可追溯性和可获得性四个标准。比较分析了几种常用的HRA方法。结果表明,用于分析的常用HRA方法存在不足,有必要建立一种新的HRA方法,或对原有方法进行改进,以解决严重事故条件下的问题,IDAC模型和Phoenix HRA方法被认为是较好的选择。结合计算机程序,IDAC模型可以模拟事故过程和人员的动态响应,有助于解释人的行为与环境的动态交互特性,但该模型在不确定性分析和仿真数据可用性方面仍存在一定的局限性。而Phoenix方法提供了一些性能影响因素和机组失效模式,可以反映应急人员的响应特征。该适用性研究可为重大事故中HRA方法的建立提供指导。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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