메뉴 건너뛰기




Volumn 33, Issue 4, 2006, Pages 354-369

Including model uncertainty in risk-informed decision making

Author keywords

[No Author keywords available]

Indexed keywords

MATHEMATICAL MODELS; NUCLEAR REACTOR LICENSING; PARAMETER ESTIMATION; PROBABILITY; RISK ASSESSMENT;

EID: 32544431726     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2005.11.010     Document Type: Article
Times cited : (75)

References (30)
  • 1
    • 0342578829 scopus 로고
    • A commentary on model uncertainty
    • Mosleh, A., Siu, N., Smidts, C., Lui, C. (Eds.) Annapolis, MD, October 20-22 1993 Center for Reliability Engineering, University of Maryland, College Park, MD, 1993. Also published as Report NUREG/CP-0138, US Nuclear Regulatory Commission, Washington, DC
    • Apostolakis, G., 1993. A commentary on model uncertainty. In: Mosleh, A., Siu, N., Smidts, C., Lui, C. (Eds.), Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification, Annapolis, MD, October 20-22, 1993. Center for Reliability Engineering, University of Maryland, College Park, MD, 1993. Also published as Report NUREG/CP-0138, US Nuclear Regulatory Commission, Washington, DC.
    • (1993) Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification
    • Apostolakis, G.1
  • 2
    • 1842545562 scopus 로고    scopus 로고
    • ASME RA-S-2002, April 5, 2002. Addenda to ASME RA-S-2002, ASME RA-Sa-2003, December 5, 2003
    • American Society of Mechanical Engineers, 2002. Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME RA-S-2002, April 5, 2002. Addenda to ASME RA-S-2002, ASME RA-Sa-2003, December 5, 2003.
    • (2002) Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications
  • 3
    • 0024130396 scopus 로고
    • Light water reactor sequence timing: Its significance to probabilistic safety assessment modeling
    • D. Bley, D. Buttemer, and J. Stetkar Light water reactor sequence timing: its significance to probabilistic safety assessment modeling Reliability Engineering and System Safety 22 1988 27 60
    • (1988) Reliability Engineering and System Safety , vol.22 , pp. 27-60
    • Bley, D.1    Buttemer, D.2    Stetkar, J.3
  • 6
    • 32544458601 scopus 로고
    • A Bayesian approach to model uncertainty
    • Mosleh, A., Siu, N., Smidts, C., Lui, C. (Eds.) Annapolis, MD, October 20-22, 1993. Center for Reliability Engineering, University of Maryland, College Park, MD, 1993. Also published as Report NUREG/CP-0138, US Nuclear Regulatory Commission, Washington, DC
    • Buslik, A., 1993. A Bayesian approach to model uncertainty. In: Mosleh, A., Siu, N., Smidts, C., Lui, C. (Eds.), Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification, Annapolis, MD, October 20-22, 1993. Center for Reliability Engineering, University of Maryland, College Park, MD, 1993. Also published as Report NUREG/CP-0138, US Nuclear Regulatory Commission, Washington, DC.
    • (1993) Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification
    • Buslik, A.1
  • 8
    • 0027583016 scopus 로고
    • Aggregating point estimates: A flexible modeling approach
    • R. Clemen, and R. Winkler Aggregating point estimates: a flexible modeling approach Management Science 39 1993 501 515
    • (1993) Management Science , vol.39 , pp. 501-515
    • Clemen, R.1    Winkler, R.2
  • 9
    • 32544452344 scopus 로고    scopus 로고
    • Interviews conducted with the US Nuclear Regulatory Commission Research and Regulatory Staff
    • Interviews conducted with the US Nuclear Regulatory Commission Research and Regulatory Staff.
  • 11
    • 32544450094 scopus 로고    scopus 로고
    • Estimation of system failure probability uncertainty including model success criteria
    • Bonano, E.J. (Ed.) San Juan, Puerto Rico, 23-28 June, 2002, Elsevier Science Ltd., United Kingdom
    • Knudson, J., Smith, C., 2002. Estimation of system failure probability uncertainty including model success criteria. In: Bonano, E.J. (Ed.). Proceedings of the 6th International Conference on Probabilistic Safety Assessment and Management (PSAM 6), San Juan, Puerto Rico, 23-28 June, 2002, Elsevier Science Ltd., United Kingdom.
    • (2002) Proceedings of the 6th International Conference on Probabilistic Safety Assessment and Management (PSAM 6)
    • Knudson, J.1    Smith, C.2
  • 12
    • 32544453651 scopus 로고    scopus 로고
    • Letter from G.B. Wallis, Chairman, Advisory Committee on Reactor Safeguards, to N.J. Diaz, Chairman, US Nuclear Regulatory Commission, Subject: "Safety Evaluation of the Industry Guidelines Related to Pressurized Water Reactor Sump Performance," October 18
    • Letter from G.B. Wallis, Chairman, Advisory Committee on Reactor Safeguards, to N.J. Diaz, Chairman, US Nuclear Regulatory Commission, Subject: "Safety Evaluation of the Industry Guidelines Related to Pressurized Water Reactor Sump Performance," October 18, 2004. Available at: .
    • (2004)
  • 13
    • 32544458295 scopus 로고
    • Mosleh, A., Siu, N., Smidts, C., Lui, C. (Eds.) Annapolis, MD, October 20-22, 1993. Center for Reliability Engineering, University of Maryland, College Park, MD, 1993. Also published as Report NUREG/CP-0138, US Nuclear Regulatory Commission, Washington, DC
    • Mosleh, A., Siu, N., Smidts, C., Lui, C. (Eds.), 1993. Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification, Annapolis, MD, October 20-22, 1993. Center for Reliability Engineering, University of Maryland, College Park, MD, 1993. Also published as Report NUREG/CP-0138, US Nuclear Regulatory Commission, Washington, DC.
    • (1993) Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification
  • 15
    • 20144384887 scopus 로고    scopus 로고
    • Report NEI-00-02, Revision A3, Washington, DC, March 20, 2000
    • Nuclear Energy Institute, 2000. Probabilistic Risk Assessment Peer Review Process Guidance. Report NEI-00-02, Revision A3, Washington, DC, March 20, 2000.
    • (2000) Probabilistic Risk Assessment Peer Review Process Guidance
  • 21
    • 32544437634 scopus 로고
    • Report NUREG/CR-4550, Washington, DC, April 1990
    • US Nuclear Regulatory Commission, 1990. Analysis of CDF from Internal Events: Expert Judgment. Report NUREG/CR-4550, vol. 2, Washington, DC, April 1990.
    • (1990) Analysis of CDF from Internal Events: Expert Judgment , vol.2
  • 22
    • 0002906749 scopus 로고
    • Use of probabilistic risk assessment methods in nuclear activities: Final policy statement
    • (60 FR 42622), August 16, 1995
    • US Nuclear Regulatory Commission, 1995. Use of Probabilistic Risk Assessment Methods in Nuclear Activities: Final Policy Statement, Federal Register, vol. 60 (60 FR 42622), August 16, 1995, p. 42622.
    • (1995) Federal Register , vol.60 , pp. 42622
  • 23
    • 0003622696 scopus 로고    scopus 로고
    • Report NUREG/CR-6555 and NUREG/CR-6523, Washington, DC
    • US Nuclear Regulatory Commission and the Commission of European Communities, 1997. Probabilistic Accident Consequence Uncertainty Analysis. Report NUREG/CR-6555 and NUREG/CR-6523, Washington, DC.
    • (1997) Probabilistic Accident Consequence Uncertainty Analysis
  • 24
    • 32544436380 scopus 로고    scopus 로고
    • US Nuclear Regulatory Commission, CCF Parameter Estimations, 2001. Common-Cause Failure Database. Available from: .
    • (2001) Common-cause Failure Database
  • 25
    • 32544451417 scopus 로고    scopus 로고
    • An approach for using probabilistic risk assessment in risk-informed decisions on plant-specific changes to the licensing basis
    • Washington, DC, November 2002
    • US Nuclear Regulatory Commission, 2002. An Approach for Using Probabilistic Risk Assessment in Risk-informed Decisions on Plant-specific Changes to the Licensing Basis. Regulatory Guide 1.174 (RG 1.174), Revision 1, Washington, DC, November 2002.
    • (2002) Regulatory Guide 1.174 (RG 1.174), Revision 1
  • 26
    • 33745818410 scopus 로고    scopus 로고
    • An approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities
    • Washington, DC, February 2004
    • US Nuclear Regulatory Commission, 2004. An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-informed Activities. Regulatory Guide 1.200 (RG 1.200), Washington, DC, February 2004.
    • (2004) Regulatory Guide 1.200 (RG 1.200)
  • 28
    • 2642554265 scopus 로고
    • Model uncertainty: Probabilities for models?
    • Mosleh, A., Siu, N., Smidts, C., Lui, C. (Eds.) Annapolis, MD, October 20-22, 1993. Center for Reliability Engineering, University of Maryland, College Park, MD, 1993. Also published as Report NUREG/CP-0138, US Nuclear Regulatory Commission, Washington, DC
    • Winkler, R., 1993. Model uncertainty: probabilities for models? In: Mosleh, A., Siu, N., Smidts, C., Lui, C. (Eds.) Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification, Annapolis, MD, October 20-22, 1993. Center for Reliability Engineering, University of Maryland, College Park, MD, 1993. Also published as Report NUREG/CP-0138, US Nuclear Regulatory Commission, Washington, DC.
    • (1993) Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification
    • Winkler, R.1
  • 30
    • 0030287619 scopus 로고    scopus 로고
    • Two methods for the structured assessment of model uncertainty by experts in performance assessments of radioactive waste repositories
    • E. Zio, and G. Apostolakis Two methods for the structured assessment of model uncertainty by experts in performance assessments of radioactive waste repositories Reliability Engineering and System Safety 54 1996 225 241
    • (1996) Reliability Engineering and System Safety , vol.54 , pp. 225-241
    • Zio, E.1    Apostolakis, G.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.