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Volumn 1, Issue , 2006, Pages 285-291

Development of a method for consideration of dependence between human failure events

Author keywords

[No Author keywords available]

Indexed keywords

FAILURE ANALYSIS; PEELING; QUALITY ASSURANCE; RELIABILITY ANALYSIS; RISK MANAGEMENT;

EID: 43249125920     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (10)

References (20)
  • 1
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    • ASME RA-S-2002, 2002, Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME.
    • ASME RA-S-2002, 2002, Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME.
  • 2
    • 0036645880 scopus 로고    scopus 로고
    • Optimization of Safety Equipment Outages Improves Safety
    • Čepin M., 2002, Optimization of Safety Equipment Outages Improves Safety, Reliability Engineering and System Safety, Vol. 77, pp. 71-80.
    • (2002) Reliability Engineering and System Safety , vol.77 , pp. 71-80
    • Čepin, M.1
  • 3
    • 9444277204 scopus 로고    scopus 로고
    • Analysis of Truncation Limit in Probabilistic Safety Assessment
    • Čepin M., 2005a, Analysis of Truncation Limit in Probabilistic Safety Assessment, Reliability Engineering and System Safety, Vol. 87 (3), pp. 395-403.
    • (2005) Reliability Engineering and System Safety , vol.87 , Issue.3 , pp. 395-403
    • Čepin, M.1
  • 4
    • 84863415696 scopus 로고    scopus 로고
    • Human Reliability Analysis - Methods and Applications, Problems and Solutions
    • Internal Report, IJS
    • Čepin M., 2005b, Human Reliability Analysis - Methods and Applications, Problems and Solutions, Internal Report, IJS.
    • (2005)
    • Čepin, M.1
  • 5
    • 0031119917 scopus 로고    scopus 로고
    • Probabilistic Safety Assessment Improves Surveillance Requirements in Technical Specifications
    • Čepin M. & Mavko, B. 1997, Probabilistic Safety Assessment Improves Surveillance Requirements in Technical Specifications, Reliability Engineering and Systems Safety, Vol. 56, pp. 69-77.
    • (1997) Reliability Engineering and Systems Safety , vol.56 , pp. 69-77
    • Čepin, M.1    Mavko, B.2
  • 8
    • 0036891162 scopus 로고    scopus 로고
    • Evaluation of Allowed Outage Time Considering a Set of Plant Configurations
    • Čepin M. & Martorell, S. 2002, Evaluation of Allowed Outage Time Considering a Set of Plant Configurations, Reliability Engineering and System Safety, Vol. 78, No. 3, pp. 259-266.
    • (2002) Reliability Engineering and System Safety , vol.78 , Issue.3 , pp. 259-266
    • Čepin, M.1    Martorell, S.2
  • 9
    • 33745805493 scopus 로고    scopus 로고
    • Analysis of Dependent Human Failure Events Using the EPRI HRA Calculator
    • Grobbelaar J. F., Julius J. A. & Rahn, F. 2005, Analysis of Dependent Human Failure Events Using the EPRI HRA Calculator, PSA05, Proceedings.
    • (2005) PSA05, Proceedings
    • Grobbelaar, J.F.1    Julius, J.A.2    Rahn, F.3
  • 10
    • 56249090979 scopus 로고    scopus 로고
    • The review of Tianwang NPP and Qinshan 1 NPP HRA
    • He X. 2005, The review of Tianwang NPP and Qinshan 1 NPP HRA. Report for NNSA.
    • (2005) Report for NNSA
    • He, X.1
  • 11
    • 56249091999 scopus 로고    scopus 로고
    • He X. & Tong, J. 2004, Human Reliability Analysis Practices in China for Nuclear Power Plant. The 8th Korea-Japan PSA Workshop, 2004. 11.1-2, Tokyo.
    • He X. & Tong, J. 2004, Human Reliability Analysis Practices in China for Nuclear Power Plant. The 8th Korea-Japan PSA Workshop, 2004. 11.1-2, Tokyo.
  • 13
    • 56249103028 scopus 로고    scopus 로고
    • NUREG/CR-1278, 1983, Handbook for Human Reliability Analysis with emphasis on Nuclear Power Plants Application, US NRC.
    • NUREG/CR-1278, 1983, Handbook for Human Reliability Analysis with emphasis on Nuclear Power Plants Application, US NRC.
  • 14
    • 56249090617 scopus 로고    scopus 로고
    • NUREG/CR-4772, 1987,Accident Sequence Evaluation Program: Human Reliability Analysis Procedure, US NRC.
    • NUREG/CR-4772, 1987,Accident Sequence Evaluation Program: Human Reliability Analysis Procedure, US NRC.
  • 15
    • 56249135143 scopus 로고    scopus 로고
    • NUREG/CR-6883, 2005, The SPAR-H Human Reliability Analysis Method, NRC.
    • NUREG/CR-6883, 2005, The SPAR-H Human Reliability Analysis Method, NRC.
  • 16
    • 56249117245 scopus 로고    scopus 로고
    • NUREG-1624, 1999, Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA), Rev. 1, US NRC.
    • NUREG-1624, 1999, Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA), Rev. 1, US NRC.
  • 17
    • 56249114401 scopus 로고    scopus 로고
    • NUREG-1792, 2005, Good Practices for Implementing Human Reliability Analysis (HRA), Final Report, US NRC.
    • NUREG-1792, 2005, Good Practices for Implementing Human Reliability Analysis (HRA), Final Report, US NRC.
  • 19
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    • HRA Methodology Applied in Surry Power Station
    • Shen S., 2005, HRA Methodology Applied in Surry Power Station, PSA05, Proceedings.
    • (2005) PSA05, Proceedings
    • Shen, S.1
  • 20
    • 27844433567 scopus 로고    scopus 로고
    • Some Lessons Learned From the Development and Updating Progresses of the PSA of DAYA BAY NPP
    • Tong J. & He X. 2006, Some Lessons Learned From the Development and Updating Progresses of the PSA of DAYA BAY NPP. Progress in Nuclear Energy, Vol 48, pp. 85-90.
    • (2006) Progress in Nuclear Energy , vol.48 , pp. 85-90
    • Tong, J.1    He, X.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.