-
1
-
-
43249125920
-
Development of a method for consideration of dependency between human failure events
-
Soares C.G., and Zio E. (Eds)
-
Čepin M., and He X. Development of a method for consideration of dependency between human failure events. In: Soares C.G., and Zio E. (Eds). Proceedings of ESREL2006: safety and reliability for managing risk (2006) 285-291
-
(2006)
Proceedings of ESREL2006: safety and reliability for managing risk
, pp. 285-291
-
-
Čepin, M.1
He, X.2
-
2
-
-
43149106702
-
-
Čepin M. Importance of human contribution within the human reliability analysis (IJS-HRA). J Loss Prevent Process Ind 2007 〈http://dx.doi.org/10.1016/j.jlp.2007.04.012〉.
-
Čepin M. Importance of human contribution within the human reliability analysis (IJS-HRA). J Loss Prevent Process Ind 2007 〈http://dx.doi.org/10.1016/j.jlp.2007.04.012〉.
-
-
-
-
3
-
-
0028207691
-
Advances in HRA, methodology. Part I: frameworks, models, and data
-
Moieni P., Spurgin J.A., and Singh A. Advances in HRA, methodology. Part I: frameworks, models, and data. Reliab Eng Syst Saf 44 (1994) 27-55
-
(1994)
Reliab Eng Syst Saf
, vol.44
, pp. 27-55
-
-
Moieni, P.1
Spurgin, J.A.2
Singh, A.3
-
4
-
-
84975789642
-
Thematic network for a Phebus FPT-1 International Standard Problem (THENPHEBISP)
-
Clément B., and Leskovar M. Thematic network for a Phebus FPT-1 International Standard Problem (THENPHEBISP). Nucl Eng Design 235 (2005) 347-357
-
(2005)
Nucl Eng Design
, vol.235
, pp. 347-357
-
-
Clément, B.1
Leskovar, M.2
-
5
-
-
43249113794
-
-
NUREG/CR-1278 (SAND80-0200). Handbook for human reliability analysis with emphasis on nuclear power plants application. US NRC, August 1983.
-
NUREG/CR-1278 (SAND80-0200). Handbook for human reliability analysis with emphasis on nuclear power plants application. US NRC, August 1983.
-
-
-
-
6
-
-
43249112922
-
-
NUREG/CR-2254 (SAND81-1655). A procedure for conducting a human reliability analysis for nuclear power plants. US NRC, May 1983.
-
NUREG/CR-2254 (SAND81-1655). A procedure for conducting a human reliability analysis for nuclear power plants. US NRC, May 1983.
-
-
-
-
7
-
-
43249095129
-
-
NUREG/CR-4772. Accident sequence evaluation program: human reliability analysis procedure. US NRC, February 1987.
-
NUREG/CR-4772. Accident sequence evaluation program: human reliability analysis procedure. US NRC, February 1987.
-
-
-
-
8
-
-
33745805493
-
-
Grobbelaar JF, Julius JA, Rahn F. Analysis of dependent human failure events using the EPRI HRA calculator. In: PSA05 Proceedings, 2005. p. 499-501.
-
Grobbelaar JF, Julius JA, Rahn F. Analysis of dependent human failure events using the EPRI HRA calculator. In: PSA05 Proceedings, 2005. p. 499-501.
-
-
-
-
9
-
-
43249112178
-
-
NUREG/CR-6883. The SPAR-H human reliability analysis method. NRC, 2005.
-
NUREG/CR-6883. The SPAR-H human reliability analysis method. NRC, 2005.
-
-
-
-
10
-
-
33745813130
-
-
Shen S. HRA methodology applied in Surry power station. In: PSA05 Proceedings, 2005. p. 615-8.
-
Shen S. HRA methodology applied in Surry power station. In: PSA05 Proceedings, 2005. p. 615-8.
-
-
-
-
11
-
-
0348042916
-
Model-based human reliability analysis: prospects and requirements
-
Mosleh A., and Chang Y.H. Model-based human reliability analysis: prospects and requirements. Reliab Eng Syst Saf 83 (2004) 241-253
-
(2004)
Reliab Eng Syst Saf
, vol.83
, pp. 241-253
-
-
Mosleh, A.1
Chang, Y.H.2
-
12
-
-
0348252364
-
Human reliability data, human error and accident models-illustration through the three mile island accident analysis
-
Le Bot P. Human reliability data, human error and accident models-illustration through the three mile island accident analysis. Reliab Eng Syst Saf 83 (2004) 153-167
-
(2004)
Reliab Eng Syst Saf
, vol.83
, pp. 153-167
-
-
Le Bot, P.1
-
14
-
-
43249121532
-
-
NUREG-1624. Technical basis and implementation guidelines for a technique for human event analysis (ATHEANA), Rev. 1, 2000.
-
NUREG-1624. Technical basis and implementation guidelines for a technique for human event analysis (ATHEANA), Rev. 1, 2000.
-
-
-
-
15
-
-
0346991647
-
Expert elicitation approach for performing ATHEANA quantification
-
Forester J., Bley D., Cooper S., Lois E., Siu N., Kolaczkowski A., et al. Expert elicitation approach for performing ATHEANA quantification. Reliab Eng Syst Saf 83 (2004) 207-220
-
(2004)
Reliab Eng Syst Saf
, vol.83
, pp. 207-220
-
-
Forester, J.1
Bley, D.2
Cooper, S.3
Lois, E.4
Siu, N.5
Kolaczkowski, A.6
-
16
-
-
0347412039
-
The CESA method and its applications in a plant-specific pilot study on errors of commission
-
Reer B., Dang V.N., and Hirschberg S. The CESA method and its applications in a plant-specific pilot study on errors of commission. Reliab Eng Syst Saf 83 (2004) 187-205
-
(2004)
Reliab Eng Syst Saf
, vol.83
, pp. 187-205
-
-
Reer, B.1
Dang, V.N.2
Hirschberg, S.3
-
17
-
-
43249109763
-
-
Good practices for implementing human reliability analysis (HRA), NUREG-1792. Final report, US NRC, 2005.
-
Good practices for implementing human reliability analysis (HRA), NUREG-1792. Final report, US NRC, 2005.
-
-
-
-
18
-
-
33750337517
-
The simulator experimental study on the operator reliability of Qinshan nuclear power plant
-
Zhang L., He X., Dai L., and Huang X. The simulator experimental study on the operator reliability of Qinshan nuclear power plant. Reliab Eng Syst Saf 92 2 (2007) 252-259
-
(2007)
Reliab Eng Syst Saf
, vol.92
, Issue.2
, pp. 252-259
-
-
Zhang, L.1
He, X.2
Dai, L.3
Huang, X.4
-
19
-
-
43249109250
-
-
IAEA-TECDOC-499. Models and data requirements for human reliability analysis. Vienna: IAEA; 1989.
-
IAEA-TECDOC-499. Models and data requirements for human reliability analysis. Vienna: IAEA; 1989.
-
-
-
-
20
-
-
43249097186
-
-
Safety Series No. 50-P-10. Human reliability analysis in probabilistic safety assessment for nuclear power plants. Vienna: IAEA; 1995.
-
Safety Series No. 50-P-10. Human reliability analysis in probabilistic safety assessment for nuclear power plants. Vienna: IAEA; 1995.
-
-
-
-
21
-
-
0346151206
-
Some insights from recent applications of HRA methods in PSA effort and plant operation feedback in Czech Republic
-
Holy J. Some insights from recent applications of HRA methods in PSA effort and plant operation feedback in Czech Republic. Reliab Eng Syst Saf 83 2 (2004) 169-177
-
(2004)
Reliab Eng Syst Saf
, vol.83
, Issue.2
, pp. 169-177
-
-
Holy, J.1
-
22
-
-
43249117078
-
-
ASME RA-S-2002. Standard for probabilistic risk assessment for nuclear power plant applications. The American Society of Mechanical Engineers, 2002.
-
ASME RA-S-2002. Standard for probabilistic risk assessment for nuclear power plant applications. The American Society of Mechanical Engineers, 2002.
-
-
-
-
23
-
-
43249085414
-
-
Regulatory Guide 1200. An approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities. US NRC, 2004.
-
Regulatory Guide 1200. An approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities. US NRC, 2004.
-
-
-
-
24
-
-
43249117324
-
-
NUREG/CR-2300. PRA procedures guide. ANS-IEEE-US NRC, January 1983.
-
NUREG/CR-2300. PRA procedures guide. ANS-IEEE-US NRC, January 1983.
-
-
-
-
25
-
-
43249104939
-
-
US NRC Regulatory Guide 1.174. An approach for using probabilistic risk assessment in risk-informed decisions on plant-specific changes to the licensing basis, Revision 1. US NRC, 2002.
-
US NRC Regulatory Guide 1.174. An approach for using probabilistic risk assessment in risk-informed decisions on plant-specific changes to the licensing basis, Revision 1. US NRC, 2002.
-
-
-
-
27
-
-
0031119917
-
Probabilistic safety assessment improves surveillance requirements in technical specifications
-
Čepin M., and Mavko B. Probabilistic safety assessment improves surveillance requirements in technical specifications. Reliab Eng Syst Saf 56 (1997) 69-77
-
(1997)
Reliab Eng Syst Saf
, vol.56
, pp. 69-77
-
-
Čepin, M.1
Mavko, B.2
-
28
-
-
0030650227
-
Comparison of testing strategies
-
(in Slovenian)
-
Mavko B., and Čepin M. Comparison of testing strategies. Electrotech Rev 64 2/3 (1997) 142-147 (in Slovenian)
-
(1997)
Electrotech Rev
, vol.64
, Issue.2-3
, pp. 142-147
-
-
Mavko, B.1
Čepin, M.2
-
29
-
-
0036645880
-
Optimization of safety equipment outages improves safety
-
Čepin M. Optimization of safety equipment outages improves safety. Reliab Eng Syst Saf 77 (2002) 71-80
-
(2002)
Reliab Eng Syst Saf
, vol.77
, pp. 71-80
-
-
Čepin, M.1
-
30
-
-
0037903790
-
Optimisation of scheduling of safety equipment testing and maintenance based on minimal risk
-
Čepin M. Optimisation of scheduling of safety equipment testing and maintenance based on minimal risk. Electrotech Rev 70 1-2 (2003) 22-26
-
(2003)
Electrotech Rev
, vol.70
, Issue.1-2
, pp. 22-26
-
-
Čepin, M.1
-
31
-
-
9444277204
-
Analysis of truncation limit in probabilistic safety assessment
-
Čepin M. Analysis of truncation limit in probabilistic safety assessment. Reliab Eng Syst Saf 87 3 (2005) 395-403
-
(2005)
Reliab Eng Syst Saf
, vol.87
, Issue.3
, pp. 395-403
-
-
Čepin, M.1
-
32
-
-
0035254824
-
Modelling and quantification of dependent repeatable human errors in system analysis in risk assessment
-
Vaurio J.K. Modelling and quantification of dependent repeatable human errors in system analysis in risk assessment. Reliab Eng Syst Saf 71 (2001) 179-188
-
(2001)
Reliab Eng Syst Saf
, vol.71
, pp. 179-188
-
-
Vaurio, J.K.1
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