References
- NUREG/CR-5331,SAND90-0364 MELCOR 1.8.0 : A Computer Code for Severe Nuclear Reactor Accident Source Term and Risk Assessment Analyses R.M. Summers;R.K. Cole;Jr.;E.A. Boucheron;M.K. Carmel;S.E. Dingman;J.E. Kelly
- MAAP 3.0B-Modular Accident Analysis Program for LWR Power Plants v.1;2 Fauske & Associates
- Nuclear Technology v.49 The Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input D.H. Nguyen
- Nuclear Science and Engineering v.102 Probabilistic Approach to Quantifying Uncertainties in the Progression of Severe Accidents M. Khatib-Rahbar;E. Cazzoli;M. Lee;H. Nourbakhsh;R. Davis;E. Schmidt
- Risk Analysis v.1 no.4 Methods for Uncertainty Analysis : A Comparative Survey D.C. Cox;P. Baybutt
- Technometrics v.27 no.2 An Examination of Response-Surface Methodologies for Uncertainty Analysis in Assessment Models D.J. Downing;R. H. Gardner;F. O. Hoffman
- Nuclear Science and Engineering v.64 Comparison of Two Uncertainty Analysis Methods Neil D. Cox
- Communications in Statistics v.B11 no.3 A Distribution Free Approach to Inducing Rank Correlation Among Input Variables R.L. Iman;W.J. Conover
- Risk Analysis v.8 no.1 An Investigation of Uncertainty and Sensitivity Analysis Techniques for Computer Models R.L. Iman;J.C. Helton
- Ph. D Thesis, KAIST A Study on the Uncertainty Propagation of Design and Operational Parameters of Nuclear Power Plant Tae Woon Kim
- Journal of the Korean Nuclear Society v.18 no.1 A Procedure for Statistical Thermal Margin Analysis Using Response Surface Method and Monte Carlo Technique Hyun Koon Kim;Young Whan Lee;Tae Woon Kim;Soon Heung Chang
- Journal of the Kroean Nuclear Society v.19 no.4 Development of Statistical Package for Uncertainty and Sensitivity Analysis(SPUSA) and Application to High Level Waste Repostitory System Tae Woon Kim;Won Jin Cho;Soon Heung Chang;Hyung Ho Lee
- Risk Analysis v.8 no.3 A Methodology for More Efficient Tail Area Sampling with Discrete Probability Distributions Sang Ryeol Park;Tae Woon Kim;Byung Ho Lee
- Journal of the Korean Nuclear Society v.22 no.3 Development of Statistical Core Thermal Design Methodology Using a Modified Latin Hypercube Sampling Method Seung Hyuk Lee;Hyun Koon Kim;Soon Ok Park;Byung Joon Koh;Sang Ryeol Park;Soon Heung Chang
- Nuclear Engineering and Design v.135 Development of an Uncertainty Quantification Method of the Best Esimate Large LOCA Analysis Sang-Ryeol Park;Won-Pil Baek;Soon-Heung Chang;Byung-Ho Lee
- Reliability Engineering and System Safety v.37 Assessment of the Potential Applicability of Fuzzy Set Theory to Accident Progression Event Trees with Phenomenolohical Uncertainties Moon-Hyun Chun;Kwal-Il Ahn
- Transactions of the American Nuclear Society v.72 Uncertainty Analysis for Source Term Using MAAP3. 0B Moon-Hyun Chun;Nam-IL Tak;Seok-Jung Han;C. K. Park;Y. H. Jin
- Proceedings of the Korean Nucear Society Spring Meeting v.1 Assessment of Two Uncertainty Quantification Methods for Source Term Analysis Nam-IL Tak;Seok-Jung Han;Moon-Hyun Chun;Chang K. Park
- Preliminary Probabilistic Safety Assessment Report : Younggwang Unit 3&4
- Recommended Sensitivity Analysis for an Individual Plant Examination Using MAAP 3.0B Gabor, Kenton & Associates, Inc
- Research Projent Report Sponsored by Korea Atomic Energy Research Institute Preliminary Uncertainty Study for Ul-Chin Units 3&4 Source Term Analysis Moon-Hyun Chun;Soon-Heong Chang;Chang-Kyung Sung;Seok-Jeong Park;Seok-Jung Han;Nam-IL Tak;Joon-Won Park