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核电厂HRA定性分析 被引量:3

HRA qualitative analysis in a 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 SGTR 为具体实例进行说明。 Human reliability analysis (HRA) is a very important part of probability safety assessment (PSA) in a nuclear power plant. Qualitative analysis is the basis and starting point of HRA. The purpose, the principle, the method and the procedure of qualitative HRA are introduced. SGTR, a pressurized nuclear power plant as an example, is used to illustrate it.
机构地区 南华大学人因所
出处 《核技术》 CAS CSCD 北大核心 2004年第10期792-795,共4页 Nuclear Techniques
基金 国家自然科学基金资助项目(70271016) 国防科研计划资助项目(Z012002A001)
关键词 HRA 定性分析 程序 HRA, Qualitative analysis, Procedure
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参考文献4

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共引文献70

同被引文献33

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