References
- Individual Plant Examination: Submittal Guidance, NUREG-1335, Final Report (August 1989)
- U.S. Nuclear Regulatory Commission, Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants, Vols. 1 & 2, NUREG-1150, Washington, DC (December 1990)
- A. Torri, P.P. Bieniarz, and D. Haschke, 'Experiences and Insights from Level 2 PSAs', Intl. Meeting on PSA/PRA and Severe Accidents '94, Ljubljana, Slovenia, (April 17-20, 1994)
- A.S. Kuritzky, R. Vijaykumar, and M. Khatib-Rahbar, 'Observations from Review of Several IPE Back-End Submittals and Other Level 2 PRA Studies,' Intl. Meeting on PSA/PRA and Severe Accidents '94, Ljubljana, Slovenia (April 17-20 1994)
- K.I. Ahn, Y.H. Jin, D.H. Kim, and C.K. Park, 'A Comparative Assessment of the Current Containment Event Tree Methodologies,' Journal of the Korean Nuclear Society, Vol. 26 (4), pp.611-626 (December 1994)
- SARRP Review Committee, A Review of the Severe Accident Risk Reduction Program (SARRP) Containment Event Trees, Prepared for U.S. Nuclear Regulatory Commission, NUREG/CR-4569 (May 1986)
- B.J. Breeding, J.C. Helton, W.B. Murfin, and L.N. Smith, Evaluation of Severe Accident Risks: Surry Unit 1 Appendices, NUREG/CR-4551, Vol.3, Rev.1, Part 2, Prepared for U.S. NRC, Sandia National Laboratories, Albuquerque, NM (October 1990)
- K.I. Ahn, D.H. Kim, and J.E. Yang, 'Methodologies for Uncertainty Analysis in the Level 2 PSA and Their Implementation Procedures, KAERI/TR-2151/2002, Korea Atomic Energy Research Institute, (April 2002)
- G. Apostolakis, 'The Concept of Probability in Safety Assessments of Technological Systems,' Science, Vol.250, pp.1359-1364 (1990) https://doi.org/10.1126/science.2255906
- R.L. Winkler, 'Uncertainty in Probabilistic Risk Assessment,' Reliability Engineering and System Safety, Vol.54, pp.127-132 (1996) https://doi.org/10.1016/S0951-8320(96)00070-1
- K.I. Ahn and J.E. Yang, 'The Explicit Treatment of Model Uncertainties in the Presence of Aleatory and Epistemic Parameter Uncertainties in Risk and Reliability Analysis,' Journal of the Korean Nuclear Society, Vol.35 (1), pp.64-79 (February 2003)
- S. Kaplan, 'Matrix Theory Formalism for Event Tree Analysis Application to Nuclear-Risk Analysis', Risk Analysis, Vol. 2, pp.9-18 (1981) https://doi.org/10.1111/j.1539-6924.1982.tb01398.x
- A. Torri, 'A Consistent Probabilistic Methodology for the Seabrook Station Containment Event Tree Analysis,' ANS/ENS Intl. Topical Meeting on Probabilistic Safety Methods and Applications, San Francisco, CA (February 24-March 1, 1985)
- D.Y. Hsia, J.S. Chung, Y.C. Chou, R. Sherry, J. Fulford, and G. Parry, 'Containment Event Tree Analysis for the Kuosheng BWR 6/Mark III Plant,' ANS/ENS Intl. Topical Meeting on Probabilistic Safety Methods and Applications, San Francisco, CA (February 24-March 1 1985)
- SAIC, Generic Framework for IPE Back-End (Level 2) Analysis, Volume 2: PWR Implementation Guidelines, NSAC-159, Volume 2 (October 1991)
- K.I. Ahn and Y. Jin, 'A Formal Approach for Quantitative Treatment of Modeling Uncertainties in Safety Analysis,' Nuclear Technology, Vol. 116 (2), pp.146-159 (1996)
- M.L. Corradini, D.V. Swenson, and R.L. Woodfin, 'Analysis of Containment Failure Due to a Steam Explosion Following a Postulated Core Melt Down in a Light-Water Reactor,' Nuclear Safety, Vol.23 (1), pp.21-31 (January-February 1982)
- E. Hofer, 'When to separate uncertainties and when not to separate,' Reliability Engineering and System Safety, 54, pp.113-118 (1996) https://doi.org/10.1016/S0951-8320(96)00068-3
- A.S. Benjamin, G.R. Boyd, W.B. Murfin, and D.M. Kunsman, 'Evaluation of Uncertainties in Risk Estimating from A number of Severe Accident Issues,' Nuclear Engineering and Design, Vol.104, pp.249-266 (1987) https://doi.org/10.1016/0029-5493(87)90203-2
- KEPCO, Korean Standard Power Plant Ulchin Units 3&4: Final Probabilistic Safety Assessment Report (1996)
- A. Mosleh and V.M. Bier, 'Uncertainty about Probability: a Reconciliation with the Subjective Viewpoint,' IEEE Trans. on Systems, Man, and Cybernetics - Part A: Systems and Humans, Vol.26 (3), pp.303-310 (May 1996) https://doi.org/10.1109/3468.487956
- R. Hummel and L. Manevitz, 'A Statistical Approach to the Representation of Uncertainty in Beliefs using Spread of Opinions,' IEEE Trans. on Systems, Man, and Cybernetics-Part A: Systems and Humans, Vol.26 (3), pp.378-384 (1996) https://doi.org/10.1109/3468.487962
- K.I. Ahn, J.E. Yang, and J.J. Ha, 'The Plant-specific Impact of Different Pressurization Rates in the Probabilistic Estimation of Containment Failure Modes,' Journal of the Korean Nuclear Society, Vol.35 (2), pp.154-164 (April 2003)
- K.I. Ahn and Y.H. Jin, CONPAS 1.0 (CONtainment Performance Analysis System) Code Package Users' Manual, KAERI Technical Report (in Korean), KAERI/TR651/96 April (1996)