铀浓缩厂人因失效分析研究
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摘要
铀浓缩厂的运行和维护,尤其是事故时的安全动作等需要大量人员操作。然而,人因事故研究几乎为空白。本文回顾了铀浓缩厂历史上几个典型的人因事故,并对国内铀浓缩厂进行了定量的人因失效分析。
The operation and maintenance of uranium enrichment plants, especially safety operations in case of accidents require a large number of personnel operation. However, the research about human factor accidents is almost vacant. This paper reviews several typical human cause accidents in the uranium enrichment plants in the history, and then executes quantitative analysis about human cause failure for domestic uranium enrichment plants.
The operation and maintenance of uranium enrichment plants, especially safety operations in case of accidents require a large number of personnel operation. However, the research about human factor accidents is almost vacant. This paper reviews several typical human cause accidents in the uranium enrichment plants in the history, and then executes quantitative analysis about human cause failure for domestic uranium enrichment plants.
引文
[1]焦远征.铀浓缩企业安全生产标准化建设研究[D].南华大学,2014.
[2]U.S.NRC.NUREG/CR-6410Nuclear Fuel Cycle Facility Accident Analysis Handbook[R].Washington,DC:U.S.NRC,1998.
[3]U.S.NRC.NUREG/CR-2300A Guide to the Performance of Probabilistic Risk Assessment for Nuclear Power Plants,Vol.1-Chapters 9-13[R].Washington DC:U.S.NRC,1983.
[4]荆永宇.某厂可能发生的辐射事故与应急措施[J].辐射防护通讯,1995(6):36-38.
[5]荆永宇,林华.兰州铀浓缩厂核事故应急准备与响应[J].原子能科学技术,2006(增40):196-199.
[6]中国核燃料有限公司,IAEA/NEA核燃料事件通告和分析系统(FINAS)经验反馈案例汇编[R].北京:中国核燃料有限公司,2017.
[7]张力.核电站人因失误分析与防止对策[J].核动力工程,1990,11(4):90-96.
[8]康肖琼,刘树林,杨丰寻.操作人员人因失效影响因素研究[J].工业工程与管理,2015,20(3):131-137.
[9]张力,黄曙东,杨洪,等.岭澳核电站人因可靠性分析[J].中国核科技报告,2000(00):1-20.
[10]张力.概率安全评价中人因可靠性分析技术[M].北京:原子能出版社,2006.
[11]黄卫刚,张力.大亚湾核电站人因事件分析与预防对策[J].核动力工程,1998,19(1):64-67.
[12]赵国志,曲鹏.铀浓缩系统事件/事故的思考与始发事件选取研究[J].核安全,2018(17):71-75.
[13]IAEA.Manual on Defining the Initiating Events for PSA Uses,IAEA-J4 CS 105[R].Vienna:IAEA,1989.
[14]IAEA.Safety of conversion facilities and uranium enrichment facilities[R].Vienna:IAEA,2010.
[15]IAEA.Survey of Ranges of Component Reliability data for use in Probabilistic Safety Assessment[R].Vienna:IAEA,1989.
[16]IAEA.IAEA-TECDOC-1267,Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities[R].Vienna:IAEA,2002.
[2]U.S.NRC.NUREG/CR-6410Nuclear Fuel Cycle Facility Accident Analysis Handbook[R].Washington,DC:U.S.NRC,1998.
[3]U.S.NRC.NUREG/CR-2300A Guide to the Performance of Probabilistic Risk Assessment for Nuclear Power Plants,Vol.1-Chapters 9-13[R].Washington DC:U.S.NRC,1983.
[4]荆永宇.某厂可能发生的辐射事故与应急措施[J].辐射防护通讯,1995(6):36-38.
[5]荆永宇,林华.兰州铀浓缩厂核事故应急准备与响应[J].原子能科学技术,2006(增40):196-199.
[6]中国核燃料有限公司,IAEA/NEA核燃料事件通告和分析系统(FINAS)经验反馈案例汇编[R].北京:中国核燃料有限公司,2017.
[7]张力.核电站人因失误分析与防止对策[J].核动力工程,1990,11(4):90-96.
[8]康肖琼,刘树林,杨丰寻.操作人员人因失效影响因素研究[J].工业工程与管理,2015,20(3):131-137.
[9]张力,黄曙东,杨洪,等.岭澳核电站人因可靠性分析[J].中国核科技报告,2000(00):1-20.
[10]张力.概率安全评价中人因可靠性分析技术[M].北京:原子能出版社,2006.
[11]黄卫刚,张力.大亚湾核电站人因事件分析与预防对策[J].核动力工程,1998,19(1):64-67.
[12]赵国志,曲鹏.铀浓缩系统事件/事故的思考与始发事件选取研究[J].核安全,2018(17):71-75.
[13]IAEA.Manual on Defining the Initiating Events for PSA Uses,IAEA-J4 CS 105[R].Vienna:IAEA,1989.
[14]IAEA.Safety of conversion facilities and uranium enrichment facilities[R].Vienna:IAEA,2010.
[15]IAEA.Survey of Ranges of Component Reliability data for use in Probabilistic Safety Assessment[R].Vienna:IAEA,1989.
[16]IAEA.IAEA-TECDOC-1267,Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities[R].Vienna:IAEA,2002.