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核电厂HRA定性分析

HRA qualitative analysis on production safety in nuclear power plant
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摘要 人因可靠性分析 ( HRA)是核电厂概率安全评价 ( PSA)的重要组成部分 ,定性评价对核电厂庞大的数据进行筛选和分析 ,是 HRA的基础和出发点。本文介绍了核电厂 HRA定性分析的目的、原则、方法和程序 ,并以压水堆核电厂蒸汽发生器传热管破裂 ( SGTR) The present article aims to introduce the purpose, principles and procedures of the human reliability analysis (HRA) in a nuclear power plant, which serves actually as a very important part of PSA (production safety analysis). As is known, qualitative analysis is the foundation of HRA. The purpose of doing the qualitative analysis is to screen or sort out the human error data to restrict or reduce the liability of human factor events introduced into the model. To fulfill HRA successfully, the article introduces four important principles. The most important principle is to guarantee all the accidents involving 'material factors vs human factors' are to be identified. To this end, the article makes a detailed analysis on the detailed procedures likely to lead to the accidents by studying a typical example, i.e. the SGTR in a pressurized nuclear power plant. It is in the example that the author has elaborately analyzed the possible human factors in the course of dealing with the accident. In addition, a few subjects for analysis are also included at the end of the analysis to represent the overall human failures.
出处 《安全与环境学报》 CAS CSCD 2004年第3期38-41,共4页 Journal of Safety and Environment
基金 国家自然科学基金资助项目 ( 70 2 710 16) 国防科研计划资助项目 ( Z0 12 0 0 2 A0 0 1)
关键词 核安全 HRA 定性分析 程序 SGTR nuclear safety HRA qualitative analysis procedure SGTR
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