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核电厂HRA定性评价及应用 被引量:2

HRA Qualitative Evaluation and Its Application in a Nuclear Power Plant
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摘要 核电厂人的可靠性分析(HRA:Human Reliability Analysis)定性评价的目的是在定性分析的基础上,确定HRA边界条件和引入HRA模型的人因事件的数量,使得HRA的量化分析得以实施。定性评价的基本原则是确定边界假设条件,辨识出所有对安全和运行具有显著影响的人因事件序列。本文以某压水堆核电厂蒸汽传热管破裂(SGTR)为具体实例,详细分析了HRA定性评价过程,确定了分析始发事件题头的基本方法,为核电厂HRA的具体实施提供了理论指导和实践说明。 The purpose of qualitative evaluation in human reliability analysis (HRA) is to conduct screening and analysis upon the tremendous human factor data, to limit the introduction of human factor events into HRA model and to make the pertinent HRA quantitative analysis feasible. Its basic principle is to establish a presumed plant condition and to identify all the human factor event sequences which have a substantial influence on the safety and operation of a nuclear power plant. The author of the paper taking SGTR of a domestic nuclear power plant as an example sets forward a detailed procedure for qualitative evaluation and establishes a basic method to analyze initial event subjects. This paper is to present a theoretical guide and practical illustration on qualitative analysis in a nuclear power plant.
出处 《工业工程与管理》 2005年第1期17-20,24,共5页 Industrial Engineering and Management
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(ZO12002A001)秦山核电厂PSA资助项目
关键词 人的可靠性分析 定性评价 人因事件 SGTR human reliability analysis qualitative evaluation human factor events SGTR
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  • 1戴立操,张力,黄曙东.复杂工业系统中人因失误根本原因分析[J].中国安全科学学报,2003,13(11):13-16. 被引量:15
  • 2Wilmart P,Grant A.Nuclear Energy Agency.Critical Operator Actions:Human Reliability Modeling and Data Issues[R].France,Issy-les-Moulineaux:OECD Nuclear Energy Agency,1998.
  • 3Swain A D,Guttmann H E.Handbook of human reliability analysis with emphasis on nuclear power plant applications[R].NUREG/CR-1278.Albuquerque:Sandia National Laboratories,1983.
  • 4Human Reliability Analysis in Probabilistic Safety Assessment for Nuclear Power Plants[R].A Safety Practice,Safety Series No.50-P-10,Vienna:INTERNATIONAL ATOMIC ENERGY AGENCY.,1995.
  • 5Hannaman G W.Human Cognitive Reliability Model for PRA Analysis[R].American:EPRI,1984.
  • 6Wilson J R,Koubek R J,Salvendy G,Sharit J,Karwowski W.Human factors in advanced manufacturing:a review and reappraisal[A].Karwowski W,Salvendy G.Organization and management of advanced manufacturing[C].New York:Wiley,1994.
  • 7Slack N,Chambers S,Johnston R.Operations management(third ed)[M].Harlow:Financial Times Prentice Hall,2001.
  • 8M.Paz Barroso,Wilson J R.Human error and disturbance occurrence in manufacturing systems:a framework and a toolkit for practical analysis[J].Cognition,Technology & Work,2000,2:51-61.
  • 9Jarvinen J,Karwowski W.Analysis of self-reported accidents attributed to advanced manufacturing systems[J].International Journal of Human Factors in Manufacturing,1995,5(3):251-266.
  • 10Kuivanen R.The impact of safety disturbances in flexible manufacturing systems[A].Karwowski W,Rahimi M.Ergonomics of hybrid automated systems Ⅱ[M].Elsevier,Amsterdam,1990:951-956.

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