核电厂严重事故缓解进程中应急人员行为分析
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摘要
为了分析核电厂人员处理严重事故的行为特征,本文通过研究严重事故管理导则的特殊性,结合现场调研和操纵员、应急技术支持人员访谈,建立了严重事故缓解进程中的人员决策模型,识别了决策人员、执行人员的关键影响因子,为严重事故下的人因可靠性分析方法研究奠定基础。
In order to analyze the behavior characteristics of the nuclear power plant crew when dealing with severe accidents, focusing on the study for the particularity of Severe Accident Management Guideline, combined with field investigation and interviews with operator and emergency technical support personnel, this paper establishes a crew decision-making model in the process of severe accident mitigation, and identifies the key influence factors of decision makers and executors, which laid a firm foundation for the studies of human reliability analysis method in severe accidents.
In order to analyze the behavior characteristics of the nuclear power plant crew when dealing with severe accidents, focusing on the study for the particularity of Severe Accident Management Guideline, combined with field investigation and interviews with operator and emergency technical support personnel, this paper establishes a crew decision-making model in the process of severe accident mitigation, and identifies the key influence factors of decision makers and executors, which laid a firm foundation for the studies of human reliability analysis method in severe accidents.
引文
[1]杨志义,张佳佳,冯进军,等.核电厂严重事故管理指南(SAMG)实施阶段若干问题的思考与建议[J].Nuclear Science and Technology,2014,02(3):26-34.
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[3]Wang Y.The human reliability analysis in level 2 PSAusing SPAR-H method[J].Advanced Materials Research,2013,609:848-853.
[4]佟立丽.核反应堆严重事故机理研究[M].上海:上海交通大学出版社,2016:284.
[5]MacLeod D E,Parry G W,Sloan B D,et al.Simplified human reliability analysis process for emergency mitigation equipment(EME)deployment[C].Hawaii:Creat Space Independent Publishing Platform,2014.
[6]Sunarko,Su'Ud Z.Probabilistic assessment of severe accident consequence in west bangka[C].London:IOPPublishing,2017.
[7]种毅敏,陶书生,杨志义.核电厂应急运行规程与严重事故管理指南接口分析[J].核安全,2013(1):14-18.
[8]张力,青涛,戴立操,等.核电厂数字化SOP对人因失误的影响[J].核科学与工程,2017,37(3):427-433.
[9]Klein G.Sources of power:how people make decisions[M].USA:The MIT Press,1999:128.
[10]Klein G.The recognition-primed decision(RPD)model:Looking back,looking forward[M].USA:The MITPress,1997:285-292.
[11]顾传俊.浅析M310核电机组严重事故管理导则[J].科技创新与应用,2015(18):45-45.
[12]Norell M.EPRI/NRC-Res fire human reliability analysis guidelines,final report:NUREG-1921[R].Washington,DC:US Nuclear Regulatory Commission,2012.
[13]Rahni N,Raimond E,L?ffler H,et al.Guidance on the verification and improvement of SAM strategies with L2 PSA[R].Paris:Institute for Radiological Protection and Nuclear Safety,2016.
[14]Groth K M,Mosleh A.A data-informed PIF hierarchy for model-based Human Reliability Analysis[J].Reliability Engineering&System Safety,2012,108:154-174.
[15]Gertman D I,Blackman H S,Marble J L.The SPAR-Hhuman reliability analysis method:NUREG/CR-6883[R].Washington,DC:US Nuclear Regulatory Commission,2005.
[16]Hollnagel E.Cognitive reliability and error analysis method(CREAM)[M].Amsterdam:Elsevier,1998:107-115.
[17]Baumont G,Ménage F,Schneiter J R,et al.Quantifying human and organizational factors in accident management using decision trees:the HORAAMmethod[J].Reliability Engineering&System Safety,2000,70(2):113-124.
[18]Cooper Susan E,John Wreathall.How to explain post-core-damage operator actions for human reliability analysis(HRA):insights form level2 HRA/PRAapplication.ML15113A991[R].Washington,DC:USNuclear Regulatory Commission,2014.
[2]Raganelli L,Kirwan B.Can we quantify human reliability in Level 2 PSA[C].Hawaii:CreateSpace Independent Publishing Platform,2014.
[3]Wang Y.The human reliability analysis in level 2 PSAusing SPAR-H method[J].Advanced Materials Research,2013,609:848-853.
[4]佟立丽.核反应堆严重事故机理研究[M].上海:上海交通大学出版社,2016:284.
[5]MacLeod D E,Parry G W,Sloan B D,et al.Simplified human reliability analysis process for emergency mitigation equipment(EME)deployment[C].Hawaii:Creat Space Independent Publishing Platform,2014.
[6]Sunarko,Su'Ud Z.Probabilistic assessment of severe accident consequence in west bangka[C].London:IOPPublishing,2017.
[7]种毅敏,陶书生,杨志义.核电厂应急运行规程与严重事故管理指南接口分析[J].核安全,2013(1):14-18.
[8]张力,青涛,戴立操,等.核电厂数字化SOP对人因失误的影响[J].核科学与工程,2017,37(3):427-433.
[9]Klein G.Sources of power:how people make decisions[M].USA:The MIT Press,1999:128.
[10]Klein G.The recognition-primed decision(RPD)model:Looking back,looking forward[M].USA:The MITPress,1997:285-292.
[11]顾传俊.浅析M310核电机组严重事故管理导则[J].科技创新与应用,2015(18):45-45.
[12]Norell M.EPRI/NRC-Res fire human reliability analysis guidelines,final report:NUREG-1921[R].Washington,DC:US Nuclear Regulatory Commission,2012.
[13]Rahni N,Raimond E,L?ffler H,et al.Guidance on the verification and improvement of SAM strategies with L2 PSA[R].Paris:Institute for Radiological Protection and Nuclear Safety,2016.
[14]Groth K M,Mosleh A.A data-informed PIF hierarchy for model-based Human Reliability Analysis[J].Reliability Engineering&System Safety,2012,108:154-174.
[15]Gertman D I,Blackman H S,Marble J L.The SPAR-Hhuman reliability analysis method:NUREG/CR-6883[R].Washington,DC:US Nuclear Regulatory Commission,2005.
[16]Hollnagel E.Cognitive reliability and error analysis method(CREAM)[M].Amsterdam:Elsevier,1998:107-115.
[17]Baumont G,Ménage F,Schneiter J R,et al.Quantifying human and organizational factors in accident management using decision trees:the HORAAMmethod[J].Reliability Engineering&System Safety,2000,70(2):113-124.
[18]Cooper Susan E,John Wreathall.How to explain post-core-damage operator actions for human reliability analysis(HRA):insights form level2 HRA/PRAapplication.ML15113A991[R].Washington,DC:USNuclear Regulatory Commission,2014.