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Reliability Assessment by the Scoring Model for the Advanced Pressurized water Reactor 1400MWe Project Selection under Uncertainty  

강영식 (세명대 안전공학과)
Publication Information
Journal of Korean Society of Industrial and Systems Engineering / v.25, no.6, 2002 , pp. 23-35 More about this Journal
Abstract
The problem of system reliability is very important issue in the digitalized nuclear power plant, because the failure of its system brings about extravagant economic loss, environment destruction, and fatal damage of human. Therefore the purpose of this study has developed the reliability evaluation model through the scoring model by the quantitative and qualitative factors in order to justify the evaluation considering the advanced safety factors in the Advanced Pressurized water Reactor 1400MWe(APR 1400MWe) under uncertainty. Especially, the qualitative factors considering the human, information control, and quality factors for the systematic and rational justification have been closely analyzed. The proposed model can be simply applied in real fields in order to minimize the industrial accidents in the digitalized nuclear power plant.
Keywords
APR 1400MWe; human factors; information control factors; quality factors;
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1 강영식 외 4인, 시스템안전공학(개정, 증보판), pp. 10-248, 태성, 2000
2 강영식 외 2인, 설비신뢰성공학, pp. 1-186, 동화기술, 2000
3 과학기술부, '원전 특별안전점검 결과', 과학기술부 공보실, 2002
4 한국전력연구원 신형원전개발센타, '종합사업현황 및 계획(APR 기술개발Ⅱ)', 한국전력연구원, pp. 1-16, 2000
5 강영식, '원자력발전소에서 정성적 요인을 고려한 신뢰성 평가', 한국산업경영시스템학회지, 23(54): 167-177, 2000
6 강영식 외 5인, 인간공학, pp. 38-130, 신광, 2001
7 강영식, '신형경수로 1400을 위한 신뢰성 평가', 한국산업안전학회지, 16(3): 125-134, 2001
8 이장수 외 5인, '차세대 원자로 디지털 계측제어 소프트웨어 안전성 계획 평가절차서', 한국원자력연구소, pp. 1-71, 2000. 5
9 N. D., Moisidis and M. D., Ratiu; 'Pump and Valve Fastener Serviceability in PWR Nuclear Facilities,' Transactions of the ASME, 118: 38-41, 1996   DOI
10 USNRC; 'PRA Procedures Guide, A Guide to the Performance of Probabilistic Risk Assessment for Nuclear Power Plants,' NUREG/CR-2300, 1983. 1
11 Bird, F.; Management Guide to Loss Control, Institute Press, Atlanta, 1974
12 R. Parasurman; 'Human-Computer Monitoring,' The Human Factors Society, 29(6): 695-706. 1987   DOI
13 김장렬 외 5인, '차세대 원자로 디지털 계측제어 안전소프트웨어 품질보증 계획 평가절차서', 한국원자력연구소, pp. 1-92, 2000. 3
14 B., Kaufer and J. A., Murphy; 'OECD nuclear energy agency activities in risk assesment,' Safety and Reliability(Rotterdam), 2; 1493-1498, 1999
15 김시달 외 4인, '원자력발전소의 정량적인 안전 해석을 위한 사건수목 기법의 응용', 산업안전학회지, 15(2): 126-135, 2000
16 B. H. Kantowitz; 'Selecting Measures for Human Factors Research,' The Human Factors Society, 34(4): 387-398, 1992   DOI
17 Rasmussen, N., and Levine, S.; 'An Assessment of Accident Risks in US Commercial Nuclear Power Plant,' WASH-1400(Nureg-74/014), Washingtons : US Regulatory Commission, 1975. 10
18 정원대 외 2인, '원자력발전소 오류분석을 위한 직무분석 방법의 개발 및 직무유형 분류', 한국산업안전학회지, 16(4): 168-174, 2001