HRA qualitative analysis in a nuclear power plant

DAI Licao ZHANG Li HUANG Shudong

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HRA qualitative analysis in a nuclear power plant

更新时间：2021-03-12

- HRA qualitative analysis in a nuclear power plant
- NUCLEAR TECHNIQUES Issue 10, (2004)
- 作者机构：
  
  1. 南华大学人因所
  2. 南华大学人因所,衡阳,421001
- 作者简介：
- 基金信息：
  
  国家自然科学基金资助项目(70271016);国防科研计划资助项目(Z012002A001)
- DOI：
  CLC： TL364
- Published：01 October 2004
- 稿件说明：
移动端阅览
[1]戴立操,张力,黄曙东.核电厂HRA定性分析[J].核技术,2004(10):792-795.

DAI Licao ZHANG Li HUANG Shudong. HRA qualitative analysis in a nuclear power plant[J]. Nuclear techniques, 2004, (10): 792-795.
[1]戴立操,张力,黄曙东.核电厂HRA定性分析[J].核技术,2004(10):792-795. DOI：

DAI Licao ZHANG Li HUANG Shudong. HRA qualitative analysis in a nuclear power plant[J]. Nuclear techniques, 2004, (10): 792-795. DOI：

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。

Abstract

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.

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