메뉴 건너뛰기




Volumn 238, Issue 12, 2008, Pages 3457-3467

Dynamic generation of accident progression event trees

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENTS; CODES (SYMBOLS); COMPUTER SOFTWARE; PRESSURIZED WATER REACTORS; PROBABILITY; SYSTEMS ANALYSIS;

EID: 55049108215     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2008.08.005     Document Type: Article
Times cited : (154)

References (28)
  • 1
    • 0027885377 scopus 로고    scopus 로고
    • Acosta, C., Siu, N., 1993. Dynamic event trees in accident sequence analysis: application to steam generator tube rupture. Reliability Engineering and System Safety 41, 135-154.
    • Acosta, C., Siu, N., 1993. Dynamic event trees in accident sequence analysis: application to steam generator tube rupture. Reliability Engineering and System Safety 41, 135-154.
  • 3
    • 34047188412 scopus 로고    scopus 로고
    • Incorporation of Markov reliability models for digital instrumentation and control systems into existing PRAs
    • American Nuclear Society, La Grange, Illinois
    • Bucci P., Mangan L.A., Kirschenbaum J., Mandelli D., Aldemir T., and Arndt S.A. Incorporation of Markov reliability models for digital instrumentation and control systems into existing PRAs. Proceedings of NPIC&HMIT 2006 (2006), American Nuclear Society, La Grange, Illinois
    • (2006) Proceedings of NPIC&HMIT 2006
    • Bucci, P.1    Mangan, L.A.2    Kirschenbaum, J.3    Mandelli, D.4    Aldemir, T.5    Arndt, S.A.6
  • 5
    • 0022766660 scopus 로고
    • Dynamic logical analytical methodology versus fault tree: the case of AFWS of a nuclear power plant
    • Cacciabue P.C., et al. Dynamic logical analytical methodology versus fault tree: the case of AFWS of a nuclear power plant. Nuclear Technology 74 (1986) 195-208
    • (1986) Nuclear Technology , vol.74 , pp. 195-208
    • Cacciabue, P.C.1
  • 6
    • 55049109348 scopus 로고    scopus 로고
    • Catalyurek, U., Rutt, B. et al., 2008. Development of a Code-Agnostic Computational Infrastructure for the Dynamic Generation of Accident Progression Even Trees. Technical Report OSUBMI_TR_2008_n03. The Ohio State University, Department of Biomedical Informatics.
    • Catalyurek, U., Rutt, B. et al., 2008. Development of a Code-Agnostic Computational Infrastructure for the Dynamic Generation of Accident Progression Even Trees. Technical Report OSUBMI_TR_2008_n03. The Ohio State University, Department of Biomedical Informatics.
  • 7
    • 55049084810 scopus 로고    scopus 로고
    • Cojazzi, G., Sardella, R., Trombetti, T., Vestrucci, P., 1994. Assessing DYLAM methodology in the frame of Monte Carlo simulation. In: Proc. Probabilistic Safety Assessment and Management. International Association for Probabilistic Safety and Management, pp. 011/13-18.
    • Cojazzi, G., Sardella, R., Trombetti, T., Vestrucci, P., 1994. Assessing DYLAM methodology in the frame of Monte Carlo simulation. In: Proc. Probabilistic Safety Assessment and Management. International Association for Probabilistic Safety and Management, pp. 011/13-18.
  • 8
    • 0030173437 scopus 로고    scopus 로고
    • The DYLAM approach to the dynamic reliability analysis of systems
    • Cojazzi G., et al. The DYLAM approach to the dynamic reliability analysis of systems. Reliability Engineering & System Safety 52 (1996) 279-296
    • (1996) Reliability Engineering & System Safety , vol.52 , pp. 279-296
    • Cojazzi, G.1
  • 9
    • 55049134550 scopus 로고    scopus 로고
    • Eide, S.A., et al., 2005. Reevaluation of the Station Blackout Risks at Nuclear Power Plants, Analysis of Loss of Offsite Power Events: 1986-2004. NUREG/CR-6890, vol. 1, U.S. Nuclear Regulatory Commission.
    • Eide, S.A., et al., 2005. Reevaluation of the Station Blackout Risks at Nuclear Power Plants, Analysis of Loss of Offsite Power Events: 1986-2004. NUREG/CR-6890, vol. 1, U.S. Nuclear Regulatory Commission.
  • 12
    • 0030173811 scopus 로고    scopus 로고
    • The development and application of the accident dynamic simulator for dynamic probabilistic risk assessment of nuclear power plants
    • Hsueh K.-S., and Mosleh A. The development and application of the accident dynamic simulator for dynamic probabilistic risk assessment of nuclear power plants. Reliability Engineering & System Safety 52 (1996) 297-314
    • (1996) Reliability Engineering & System Safety , vol.52 , pp. 297-314
    • Hsueh, K.-S.1    Mosleh, A.2
  • 13
    • 0033220777 scopus 로고    scopus 로고
    • Majumdar, S., 1999. Prediction of Structural Integrity of Steam Generator Tubes Under Severe Accident Conditions. Nuclear Engineering and Design, pp. 31-55.
    • Majumdar, S., 1999. Prediction of Structural Integrity of Steam Generator Tubes Under Severe Accident Conditions. Nuclear Engineering and Design, pp. 31-55.
  • 15
    • 55049114002 scopus 로고    scopus 로고
    • Munoz, R., et al., 1999. A Second Generation Scheduler for Dynamic Event Trees, Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications. Madrid, Spain, pp. 1358-1367.
    • Munoz, R., et al., 1999. A Second Generation Scheduler for Dynamic Event Trees, Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications. Madrid, Spain, pp. 1358-1367.
  • 16
    • 55049135726 scopus 로고    scopus 로고
    • DENDROS: a second generation scheduler for dynamic event trees, mathematics and computation, reactor physics and environmental analysis in nuclear applications
    • Madrid, Spain
    • Munoz R., Minguez E., Melendez E., Izquierdo J.M., and Sanchez-Perea M. DENDROS: a second generation scheduler for dynamic event trees, mathematics and computation, reactor physics and environmental analysis in nuclear applications. Conference Proceedings. Madrid, Spain (1999)
    • (1999) Conference Proceedings
    • Munoz, R.1    Minguez, E.2    Melendez, E.3    Izquierdo, J.M.4    Sanchez-Perea, M.5
  • 17
    • 55049108106 scopus 로고    scopus 로고
    • Pilch, M.M., et al., 1996. Resolution of the Direct Containment Heating Issue for All Westinghouse Plants with Large Dry Containments or Subatmospheric Containments, NUREG/CR-6338, SAND95-2381. Nuclear Regulatory Commission.
    • Pilch, M.M., et al., 1996. Resolution of the Direct Containment Heating Issue for All Westinghouse Plants with Large Dry Containments or Subatmospheric Containments, NUREG/CR-6338, SAND95-2381. Nuclear Regulatory Commission.
  • 18
    • 33845939372 scopus 로고    scopus 로고
    • Distributed dynamic event tree generation for reliability and risk assessment
    • Paris, France
    • Rutt B., Catalyurek U., et al. Distributed dynamic event tree generation for reliability and risk assessment. CLADE 2006 Workshop. Paris, France (2006)
    • (2006) CLADE 2006 Workshop
    • Rutt, B.1    Catalyurek, U.2
  • 20
    • 48149105083 scopus 로고    scopus 로고
    • Sharma, L., Aldemir, T., Parker, R., 2007. Uncertainty analysis using Taguchi methods with virtual experiments. Transactions of the American Nuclear Society 95, 427-429.
    • Sharma, L., Aldemir, T., Parker, R., 2007. Uncertainty analysis using Taguchi methods with virtual experiments. Transactions of the American Nuclear Society 95, 427-429.
  • 23
    • 55049139068 scopus 로고    scopus 로고
    • Summers, R.M., Cole, R.K., et al., 1981. MELCOR 1.8.0: A Computer Code for Nuclear Reactor Severe Accident Source Term and Risk Assessment Analyses.
    • Summers, R.M., Cole, R.K., et al., 1981. MELCOR 1.8.0: A Computer Code for Nuclear Reactor Severe Accident Source Term and Risk Assessment Analyses.
  • 24
    • 55049094381 scopus 로고    scopus 로고
    • US Nuclear Regulatory Commission (USNRC), 1975. Reactor Safety Study-An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, WASH-1400 (NUREG-75/014).
    • US Nuclear Regulatory Commission (USNRC), 1975. Reactor Safety Study-An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, WASH-1400 (NUREG-75/014).
  • 25
    • 55049137246 scopus 로고    scopus 로고
    • US Nuclear Regulatory Commission (USNRC), 1990. Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants, NUREG-1150.
    • US Nuclear Regulatory Commission (USNRC), 1990. Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants, NUREG-1150.
  • 26
    • 0025846462 scopus 로고
    • Incorporating aging effects into probabilistic risk analysis using a Taylor expansion approach
    • Vesely W.E. Incorporating aging effects into probabilistic risk analysis using a Taylor expansion approach. Reliability Engineering and System Safety 32 3 (1991) 315-337
    • (1991) Reliability Engineering and System Safety , vol.32 , Issue.3 , pp. 315-337
    • Vesely, W.E.1
  • 27
    • 55049098788 scopus 로고    scopus 로고
    • Vierow et al., "Task Order No. 12, MELCOR Assessment against SCDAP/RELAP5", Annual Report, January 1, 2002 through December 31, 2002, prepared for the U.S. Nuclear Regulatory Commission, Jan. 2003.
    • Vierow et al., "Task Order No. 12, MELCOR Assessment against SCDAP/RELAP5", Annual Report, January 1, 2002 through December 31, 2002, prepared for the U.S. Nuclear Regulatory Commission, Jan. 2003.
  • 28
    • 84876497470 scopus 로고    scopus 로고
    • Zhu, D., Chang, Y.H., Mosleh, A., 2008. The Use of Distributed Computing for Dynamic PRA: The ADS Approach. In: Proceedings of PSAM 9. CD-ROM Version, IAPSAM.
    • Zhu, D., Chang, Y.H., Mosleh, A., 2008. The Use of Distributed Computing for Dynamic PRA: The ADS Approach. In: Proceedings of PSAM 9. CD-ROM Version, IAPSAM.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.