메뉴 건너뛰기




Volumn 83, Issue 2, 2004, Pages 265-274

Sample size bounding and context ranking as approaches to the HRA data problem

Author keywords

Data analysis; Error forcing context; Errors of commission; Gibbs sampling; Human reliability analysis; Operating experience

Indexed keywords

ACCIDENT PREVENTION; DATA REDUCTION; DATABASE SYSTEMS; ERROR ANALYSIS; INDUSTRIAL PLANTS; NUCLEAR POWER PLANTS; PLANT SHUTDOWNS; PROBABILITY; RELIABILITY THEORY;

EID: 0348042918     PISSN: 09518320     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.ress.2003.09.016     Document Type: Article
Times cited : (2)

References (32)
  • 1
    • 0347779925 scopus 로고    scopus 로고
    • Is probabilistic human reliability assessment possible?
    • Working material. Probabilistic safety analysis and human reliability analysis. November 1994. IAEA-PC-3580, App. 1, Topic 6. Reproduced by International Atomic Energy Agency, Vienna
    • Mosneron-Dupin F. Is probabilistic human reliability assessment possible? In: Working material. Probabilistic safety analysis and human reliability analysis. Proceedings of a Meeting Held in Paris; November 1994. IAEA-PC-3580, App. 1, Topic 6. Reproduced by International Atomic Energy Agency, Vienna; 1996.
    • (1996) Proceedings of a Meeting Held in Paris
    • Mosneron-Dupin, F.1
  • 2
    • 0027239088 scopus 로고
    • Context and human reliability analysis
    • Dougherty E.M. Jr. Context and human reliability analysis. Reliab Engng Syst Safety. 41:1993;25-47.
    • (1993) Reliab Engng Syst Safety , vol.41 , pp. 25-47
    • Dougherty Jr., E.M.1
  • 5
    • 0347149857 scopus 로고    scopus 로고
    • Technical basis and implementation for a technique for human event analysis (ATHEANA)
    • Washington, DC: US Nuclear Regulatory Commission
    • Technical basis and implementation for a technique for human event analysis (ATHEANA). NUREG-1624, Rev. 1. 2000;US Nuclear Regulatory Commission, Washington, DC.
    • (2000) NUREG-1624, Rev. 1
  • 8
    • 0347149856 scopus 로고    scopus 로고
    • Contribution from Finland. Framework for analyzing commission errors
    • NEA/CSNI/R(2000)17. OECD, Nuclear Energy Agency, Paris
    • Pyy P. Contribution from Finland. Framework for analyzing commission errors. In: Errors of Commission in Probabilistic Safety Assessment. NEA/CSNI/R(2000)17. OECD, Nuclear Energy Agency, Paris; 2000. p. 57-69.
    • (2000) Errors of Commission in Probabilistic Safety Assessment , pp. 57-69
    • Pyy, P.1
  • 9
    • 79952321680 scopus 로고    scopus 로고
    • Analysing errors of commission: Identification and first assessment for a Swiss plant
    • OECD NEA Workshop, Rockville, MD, USA, May 7-9. OECD, Nuclear Energy Agency, Paris
    • Dang VN, Reer B, Hirschberg S. Analysing errors of commission: identification and first assessment for a Swiss plant. In: Building the New HRA: errors of commission - from research to application, OECD NEA Workshop, Rockville, MD, USA, May 7-9. OECD, Nuclear Energy Agency, Paris; 2001.
    • (2001) Building the New HRA: Errors of Commission - From Research to Application
    • Dang, V.N.1    Reer, B.2    Hirschberg, S.3
  • 10
    • 0020269894 scopus 로고
    • Response times of nuclear power plant operations: Comparison of field and simulator data
    • EdwardR.E. Santa Monica, CA: Human Factors Society. Seattle Washington, October 25-29
    • Beare A.N., Dorris R.E., Kozinsky E.J. Response times of nuclear power plant operations: comparison of field and simulator data. Edward R.E. Proceedings of the Human Factors Society 26th Annual Meeting. Seattle Washington, October 25-29. 1982;Human Factors Society, Santa Monica, CA. p. 669-73.
    • (1982) Proceedings of the Human Factors Society 26th Annual Meeting , pp. 669-673
    • Beare, A.N.1    Dorris, R.E.2    Kozinsky, E.J.3
  • 11
    • 24444461109 scopus 로고    scopus 로고
    • Considerations of the elements of the quantification of human reliability
    • OECD Workshop, Building the New HRA: strengthening the link between experience and HRA. Munich, Germany, 28-30 January. OECD, Nuclear Energy Agency, Paris
    • Sträter O. Considerations of the elements of the quantification of human reliability. In: Proceedings of an Internat. OECD Workshop, Building the New HRA: strengthening the link between experience and HRA. Munich, Germany, 28-30 January. OECD, Nuclear Energy Agency, Paris; 2002.
    • (2002) Proceedings of an Internat
    • Sträter, O.1
  • 12
    • 0033079960 scopus 로고    scopus 로고
    • Assessment of human reliability based on evaluation of plant experience: Requirements and implementation
    • Sträter O., Bubb H. Assessment of human reliability based on evaluation of plant experience: requirements and implementation. Reliab Engng Syst Safety. 63:1999;199-219.
    • (1999) Reliab Engng Syst Safety , vol.63 , pp. 199-219
    • Sträter, O.1    Bubb, H.2
  • 13
    • 26744468732 scopus 로고    scopus 로고
    • Overview about the CAHR Method and its application in assessing errors of commission
    • OECD NEA Workshop, Rockville, MD, USA, May 7-9. OECD, Nuclear Energy Agency, Paris
    • Sträter O. Overview about the CAHR Method and its application in assessing errors of commission. In: Building the new HRA: errors of commission-from research to application, OECD NEA Workshop, Rockville, MD, USA, May 7-9. OECD, Nuclear Energy Agency, Paris; 2001.
    • (2001) Building the New HRA: Errors of Commission-from Research to Application
    • Sträter, O.1
  • 15
    • 0345888616 scopus 로고    scopus 로고
    • Bayesian treatment of uncertainty in classifying data
    • Conference on Probabilistic Safety Assessment and Management. Crete, Greece. London: Springer
    • Atwood C.L., Gentillon C.D. Bayesian treatment of uncertainty in classifying data. Proceedings of ESREL'96/PSAM-III Internat. Conference on Probabilistic Safety Assessment and Management. Crete, Greece. vol. 2:1996;Springer, London. p. 1283-8.
    • (1996) Proceedings of ESREL'96/PSAM-III Internat , vol.2 , pp. 1283-1288
    • Atwood, C.L.1    Gentillon, C.D.2
  • 16
    • 0025209648 scopus 로고
    • Monte Carlo method for parameter estimation in the presence of uncertain data
    • Siu N. Monte Carlo method for parameter estimation in the presence of uncertain data. Reliab Engng Syst Safety. 28:1990;59-98.
    • (1990) Reliab Engng Syst Safety , vol.28 , pp. 59-98
    • Siu, N.1
  • 17
    • 0020449096 scopus 로고
    • Events resulting in reactor shutdown and their causes
    • see also pages 214-5, 342, 458, 587-8, 721-2
    • Mays G.T., Gallaher R.B. Events resulting in reactor shutdown and their causes. Nucl Safety. 23:1982;85-86. see also pages 214-5, 342, 458, 587-8, 721-2.
    • (1982) Nucl Safety , vol.23 , pp. 85-86
    • Mays, G.T.1    Gallaher, R.B.2
  • 18
    • 0020600058 scopus 로고
    • Events resulting in reactor shutdown and their causes
    • see also pages 250-1, 389-90
    • Mays G.T., Gallaher R.B. Events resulting in reactor shutdown and their causes. Nucl Safety. 24:1983;102-103. see also pages 250-1, 389-90.
    • (1983) Nucl Safety , vol.24 , pp. 102-103
    • Mays, G.T.1    Gallaher, R.B.2
  • 19
    • 0020600058 scopus 로고
    • Events resulting in reactor shutdown and their causes
    • Mays G.T. Events resulting in reactor shutdown and their causes. Nucl Safety. 24:1983;538-539.
    • (1983) Nucl Safety , vol.24 , pp. 538-539
    • Mays, G.T.1
  • 20
    • 0020848697 scopus 로고
    • Events resulting in reactor shutdown
    • see also pages 851-2
    • Silver E.G., Clemons D. Events resulting in reactor shutdown. Nucl Safety. 24:1983;688. see also pages 851-2.
    • (1983) Nucl Safety , vol.24 , pp. 688
    • Silver, E.G.1    Clemons, D.2
  • 21
    • 0021393356 scopus 로고
    • Events resulting in reactor shutdown
    • see also pages 399, 556-7
    • Silver E.G., Clemons D. Events resulting in reactor shutdown. Nucl Safety. 25:1984;262-263. see also pages 399, 556-7.
    • (1984) Nucl Safety , vol.25 , pp. 262-263
    • Silver, E.G.1    Clemons, D.2
  • 22
    • 0346519470 scopus 로고
    • Operating experience
    • see also pages 198-223, 320-58, 451-71, 572-602, 702-36
    • Casto WR (ed.). Operating experience. Nuclear Safety 1982; 23: 72-96. (see also pages 198-223, 320-58, 451-71, 572-602, 702-36).
    • (1982) Nuclear Safety , vol.23 , pp. 72-96
    • Casto, W.R.1
  • 23
    • 0345888615 scopus 로고
    • Operating experience
    • see also pages 243-61, 383-404, 520-58, 678-707, 836-62
    • Casto WR (ed.). Operating experience. Nuclear Safety 1983; 24: 75-113 (see also pages 243-61, 383-404, 520-58, 678-707, 836-62).
    • (1983) Nuclear Safety , vol.24 , pp. 75-113
    • Casto, W.R.1
  • 24
    • 0346519471 scopus 로고
    • Operating experience
    • see also pages 255-80, 373-424, 547-74, 697-719, 830-51
    • Casto WR (ed.). Operating experience. Nuclear Safety 1984; 25: 88-127(see also pages 255-80, 373-424, 547-74, 697-719, 830-51).
    • (1984) Nuclear Safety , vol.25 , pp. 88-127
    • Casto, W.R.1
  • 26
    • 0041688937 scopus 로고
    • The application of cognitive models to the evaluation and prediction of human reliability
    • Knoxville, TN, 21-24 April 1986. American Nuclear Society, La Grange Park, Illinois
    • Embrey DE, Reason JT. The application of cognitive models to the evaluation and prediction of human reliability. In: Proceedings of the International Meeting on Advances in Human Factors in Nuclear Power Systems, Knoxville, TN, 21-24 April 1986. American Nuclear Society, La Grange Park, Illinois; 1986. p. 292-301.
    • (1986) Proceedings of the International Meeting on Advances in Human Factors in Nuclear Power Systems , pp. 292-301
    • Embrey, D.E.1    Reason, J.T.2
  • 27
    • 0039111359 scopus 로고
    • Engineering evaluation
    • AEOD/E95-01, Reactor Analysis Branch, Office for Analysis and Evaluation of Operational Data, US Nuclear Regulatory Commission, Washington, DC
    • Kauffman JV. Engineering evaluation. Operating events with inappropriate bypass or defeat of engineered safety features. AEOD/E95-01, Reactor Analysis Branch, Office for Analysis and Evaluation of Operational Data, US Nuclear Regulatory Commission, Washington, DC; 1995.
    • (1995) Operating Events with Inappropriate Bypass or Defeat of Engineered Safety Features
    • Kauffman, J.V.1
  • 28
    • 0031171062 scopus 로고    scopus 로고
    • Estimation from zero-failure data
    • Bailey R.T. Estimation from zero-failure data. Risk Anal. 17:(3):1997;375-380.
    • (1997) Risk Anal , vol.17 , Issue.3 , pp. 375-380
    • Bailey, R.T.1
  • 29
    • 0347149871 scopus 로고    scopus 로고
    • Deriving context-specific probabilities from incompletely specified data - Sub sample size bounding technique
    • OECD Workshop, Building the New HRA: Strengthening the Link Between Experience and HRA. Munich, Germany, 28-30 January. OECD, Nuclear Energy Agency, Paris
    • Reer B. Deriving context-specific probabilities from incompletely specified data - sub sample size bounding technique. In: Proceedings of an Internat. OECD Workshop, Building the New HRA: Strengthening the Link Between Experience and HRA. Munich, Germany, 28-30 January. OECD, Nuclear Energy Agency, Paris; 2002.
    • (2002) Proceedings of an Internat
    • Reer, B.1
  • 30
    • 0003053548 scopus 로고
    • Bayesian computation via the Gibbs sampler and related Markov chain Monte Carlo methods
    • Smith A.F., Roberts G.O. Bayesian computation via the Gibbs sampler and related Markov chain Monte Carlo methods. J R Stat Soc; B. 55:1993;3-23.
    • (1993) J R Stat Soc; B , vol.55 , pp. 3-23
    • Smith, A.F.1    Roberts, G.O.2
  • 32
    • 24444447320 scopus 로고    scopus 로고
    • A comparison of the application of the CAHR method to the evaluation of PWR- and BWR- events and implication for the methodological development of HRA
    • Washington DC, August 22-26. La Grange Park, IL: American Nuclear Society
    • Sträter O., Reer B. A comparison of the application of the CAHR method to the evaluation of PWR- and BWR- events and implication for the methodological development of HRA. Proceedings of the International Topical Meeting on Probabilistic Safety Assessment, PSA'99, Washington DC, August 22-26. vol. II:1999;American Nuclear Society, La Grange Park, IL. p. 869-6.
    • (1999) Proceedings of the International Topical Meeting on Probabilistic Safety Assessment, PSA'99 , vol.2 , pp. 869-6
    • Sträter, O.1    Reer, B.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.