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Volumn 58, Issue 2, 1997, Pages 145-156

An approach to the application of subjective probabilities in level 2 PSAs

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; CHEMICAL PLANTS; NUCLEAR POWER PLANTS; RISK ASSESSMENT;

EID: 0031268317     PISSN: 09518320     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0951-8320(96)00145-7     Document Type: Article
Times cited : (23)

References (15)
  • 1
    • 0028202673 scopus 로고
    • Insights from the comparison of the level-2 results of recent PSAs
    • Ljubljana, Slovenia, 17-20 April
    • Werner, W. F., Insights from the comparison of the level-2 results of recent PSAs. In International Meeting on PSA/PRA and Severe Accidents '94, Ljubljana, Slovenia, 17-20 April 1994.
    • (1994) International Meeting on PSA/PRA and Severe Accidents '94
    • Werner, W.F.1
  • 2
    • 30244478802 scopus 로고
    • Severe accident and accident management modelling in a PSA for a PWR
    • London, UK, 3-4 December
    • Ang, M. L., Severe accident and accident management modelling in a PSA for a PWR. In IBC Conference on PSA/PRA, Safety and Risk Assessment, London, UK, 3-4 December 1992.
    • (1992) IBC Conference on PSA/PRA, Safety and Risk Assessment
    • Ang, M.L.1
  • 4
    • 0345402492 scopus 로고
    • Aspects of risk assessment for hazardous pipelines containing flammable substances
    • Carter, D. A., Aspects of risk assessment for hazardous pipelines containing flammable substances. Journal of Loss Prevention Process Industry, 4 (1991) 68-72.
    • (1991) Journal of Loss Prevention Process Industry , vol.4 , pp. 68-72
    • Carter, D.A.1
  • 5
    • 43949152834 scopus 로고
    • Quantitative risk assessment applied to offshore process installation, challenges after Piper Alpha disaster
    • Ramsay, C. G., Bolsover, A. J., Jones, R. H. and Medland, W. G., Quantitative risk assessment applied to offshore process installation, challenges after Piper Alpha disaster. Journal of Loss Prevention Process Industry, 7 (1994) 317-330.
    • (1994) Journal of Loss Prevention Process Industry , vol.7 , pp. 317-330
    • Ramsay, C.G.1    Bolsover, A.J.2    Jones, R.H.3    Medland, W.G.4
  • 7
    • 9144223088 scopus 로고    scopus 로고
    • A benchmark exercise on expert judgement techniques in PSA level 2: Design criteria and general framework
    • Utah, USA, 29 September-3 October
    • Cojazzi, G., Pinola, L. and Sardella, R., A benchmark exercise on expert judgement techniques in PSA level 2: design criteria and general framework. In PSA 96, International Topical Meeting on Probabilistic Safety Assessment, Utah, USA, 29 September-3 October, 1996.
    • (1996) PSA 96, International Topical Meeting on Probabilistic Safety Assessment
    • Cojazzi, G.1    Pinola, L.2    Sardella, R.3
  • 10
    • 0027307691 scopus 로고
    • Arkansas nuclear one IPE: An implementation of the EPRI generic framework for IPE back end (level 2) analysis
    • San Francisco, 21-24 March
    • Mendoza, Z. T. and Lloyd, M., Arkansas Nuclear One IPE: an implementation of the EPRI generic framework for IPE back end (level 2) analysis. In 2nd ASME/JSME Nuclear Engineering Conference, San Francisco, 21-24 March 1993.
    • (1993) 2nd ASME/JSME Nuclear Engineering Conference
    • Mendoza, Z.T.1    Lloyd, M.2
  • 11
    • 84921242544 scopus 로고
    • Quantification of the probability of containment failure caused by an in-vessel steam explosion for the Sizewell 'B' PWR
    • Santa Barbara. USA, 5-8 January
    • Turland, B. D., Fletcher, D. F., Hodges, K. I. and Attwood, G. J., Quantification of the probability of containment failure caused by an in-vessel steam explosion for the Sizewell 'B' PWR. In CSNI Specialists Meeting on Fuel-Coolant Interactions, Santa Barbara. USA, 5-8 January 1993.
    • (1993) CSNI Specialists Meeting on Fuel-coolant Interactions
    • Turland, B.D.1    Fletcher, D.F.2    Hodges, K.I.3    Attwood, G.J.4
  • 13
    • 30244504270 scopus 로고
    • DCH-2: Results from the second experiment performed in the Surtsey direct heating test facility
    • NUREG, USA
    • Tarbell, W. W., Nichols, J. E., Brockman, J. E., Ross, J. W., Oliver, M. S. and Lucero, D. A., DCH-2: results from the second experiment performed in the Surtsey direct heating test facility. NUREG/CR-4917, NUREG, USA, 1988.
    • (1988) NUREG/CR-4917
    • Tarbell, W.W.1    Nichols, J.E.2    Brockman, J.E.3    Ross, J.W.4    Oliver, M.S.5    Lucero, D.A.6
  • 14
    • 30244559574 scopus 로고
    • Natural circulation experiments for PWR degraded core accidents
    • EPRI, USA
    • Natural circulation experiments for PWR degraded core accidents. EPRI NP-6324-L, EPRI, USA, 1989.
    • (1989) EPRI NP-6324-L
  • 15
    • 30244546924 scopus 로고
    • Reactor risk reference document
    • NUREG, USA
    • Reactor risk reference document. Volume 3 of NUREG-1150 (Draft for Comment), NUREG, USA, 1987.
    • (1987) NUREG-1150 (Draft for Comment) , vol.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.