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秦山核电厂操纵员可靠性模拟机实验研究
引用本文:张 力,黄祥瑞,赵炳全,王 遥. 秦山核电厂操纵员可靠性模拟机实验研究[J]. 中国工程科学, 2005, 7(2): 41-46
作者姓名:张 力  黄祥瑞  赵炳全  王 遥
作者单位:1. 南华大学,湖南,衡阳,421001
2. 清华大学,北京,100084
基金项目:国家自然科学基金资助项目(70271016);国防军工技术基础计划项目(Z012002A001)
摘    要:数据匮乏与可用性差是长期困扰人因可靠性分析(HRA)的一大难题。在秦山核电厂HRA过程中用秦山核电厂全尺寸模拟机实施了操纵员可靠性实验。该项实验选择包含技能型、规则型和知识型3种认知类型以及对电厂运行安全有重大影响的23个异常事件(55个HIs界面),对38名操纵员事件响应状况和时间进行录像和记录,取得764个数据点,经数据处理和分析后获得适合秦山核电厂系统与人员特性的HRA/HCR模型基本参数。介绍了该实验的背景、理论、方法、过程、结果及与国外数据的比较。

关 键 词:人因可靠性分析(HRA);模拟机;可靠性模型(HCR)
文章编号:1009-1742(2005)02-0041-06
收稿时间:2004-04-05
修稿时间:2004-04-05

The Operator Reliability Experiment at Qinshan Nuclear Power Plant by the Simulator
zhangli,huangxiangrui,zhaobingquan and wangyao. The Operator Reliability Experiment at Qinshan Nuclear Power Plant by the Simulator[J]. Engineering Science, 2005, 7(2): 41-46
Authors:zhangli  huangxiangrui  zhaobingquan  wangyao
Abstract:The lack of data and availability is a major problem that embarras se s human reliability analysis (HRA) for a long time. In the course of Qinshan HRA , a full-size simulator was used to conduct an experiment on the operator's rel i ability. It involves 3 cognition patterns including those of the skill-based, r ule-based and knowledge-based and 23 abnormal events (55 HIs) which affect gre at ly the safety of power plant. The response time and conditions of 38 operators w ere recorded and kinescoped. 764 data points were resulted. All the data were an alyzed and processed to develope HRA/HCR basic model parameter which matches wit h the features of Qinshan Nuclear Power Plant system and personnels. This paper introduces the background , theory, method, course, conclusion and their compari son with data obtained abroad.
Keywords:human reliability analysis (HRA)  simulator   experiment  human co gnition reliability (HCR)
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