-
1
-
-
0347779925
-
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
-
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
-
3
-
-
38249013861
-
INTENT: A method for estimating human error probabilities for decision based errors
-
Gertman D.I., Blackmann H.S., Haney L.N., Seidler K.S., Hahn H.A. INTENT: A method for estimating human error probabilities for decision based errors. Reliab Engng Syst Safety. 35:1992;127-136.
-
(1992)
Reliab Engng Syst Safety
, vol.35
, pp. 127-136
-
-
Gertman, D.I.1
Blackmann, H.S.2
Haney, L.N.3
Seidler, K.S.4
Hahn, H.A.5
-
4
-
-
0031387895
-
Human-centered modeling in human reliability analysis: Some trends based on case studies
-
Mosneron-Dupin F., Reer B., Heslinga G., Sträter O., Gerdes V., Saliou G., Ullwer W. Human-centered modeling in human reliability analysis: some trends based on case studies. Reliab Engng Syst Safety. 58:1997;249-274.
-
(1997)
Reliab Engng Syst Safety
, vol.58
, pp. 249-274
-
-
Mosneron-Dupin, F.1
Reer, B.2
Heslinga, G.3
Sträter, O.4
Gerdes, V.5
Saliou, G.6
Ullwer, W.7
-
5
-
-
0347149857
-
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
-
-
-
7
-
-
0343018241
-
A second generation HRA method: What it does and doesn't do
-
Washington DC, August 22-26
-
Le Bot P., Cara F., Bieder C. A second generation HRA method: what it does and doesn't do. Proceedings of the International Topical Meeting on Probabilistic Safety Assessment, PSA'99, Washington DC, August 22-26. vol. II:1999;. p. 852-60.
-
(1999)
Proceedings of the International Topical Meeting on Probabilistic Safety Assessment, PSA'99
, vol.2
, pp. 852-860
-
-
Le Bot, P.1
Cara, F.2
Bieder, C.3
-
8
-
-
0347149856
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
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
-
25
-
-
84910375096
-
Precursors to potential severe core damage accidents: 1982-1983
-
NUREG/CR-4674. Washington, DC: US Nuclear Regulatory Commission
-
Forester J.A., Minarick J.W., Schriner H.K., Dolan B.W., Mitchell D.B., Whitehead D.W., Jensen J.J. Precursors to potential severe core damage accidents: 1982-1983. A status report. NUREG/CR-4674. vol. 24:1987;US Nuclear Regulatory Commission, Washington, DC.
-
(1987)
A Status Report
, vol.24
-
-
Forester, J.A.1
Minarick, J.W.2
Schriner, H.K.3
Dolan, B.W.4
Mitchell, D.B.5
Whitehead, D.W.6
Jensen, J.J.7
-
26
-
-
0041688937
-
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
-
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
-
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
-
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
-
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
-
31
-
-
14644407359
-
SLIM-MAUD: An approach to assessing human error probabilities using structured expert judgment
-
NUREG/CR-3518. US Nuclear Regulatory Commission, Washington, DC
-
Embrey DE, Humphreys P, Rosa EA, Kirwan B, Rea K. SLIM-MAUD: an approach to assessing human error probabilities using structured expert judgment. Vol. I: Overview of SLIM-MAUD. Vol. II: Detailed analyses of the technical issues. NUREG/CR-3518. US Nuclear Regulatory Commission, Washington, DC; 1984.
-
(1984)
Vol. I: Overview of SLIM-MAUD. Vol. II: Detailed Analyses of the Technical Issues
, vol.1-2
-
-
Embrey, D.E.1
Humphreys, P.2
Rosa, E.A.3
Kirwan, B.4
Rea, K.5
-
32
-
-
24444447320
-
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
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