A Combined Procedure of RSM and LHS for Uncertainty Analyses of CsI Release Fraction Under a Hypothetical Severe Accident Sequence of Station Blackout at Younggwang Nuclear Power Plant Using MAAP3.0B Code

  • Han, Seok-Jung (Korea Advanced Institute of Science and Technology Department of Nuclear Engineering) ;
  • Tak, Nam-Il (Korea Advanced Institute of Science and Technology Department of Nuclear Engineering) ;
  • Chun, Moon-Hyun (Korea Advanced Institute of Science and Technology Department of Nuclear Engineering)
  • Published : 1996.12.01

Abstract

Quantification of uncertainties in the source term estimations by a large computer code, such as MELCOR and MAAP, is an essential process of the current Probabilistic safety assessment. The main objective of the present study is to investigate the applicability of a combined procedure of the response surface method (RSM) based on input determined from a statistical design and the Latin hypercube sampling (LHS) technique for the uncertainty analysis of CsI release fractions under a Hypothetical severe accident sequence of a station blackout at Younggwang nuclear power plant using MAAP3. OB code as a benchmark problem. On the basis of the results obtained in the present work, the RSM is recommended to be used as a principal tool for an overall uncertainty analysis in source term quantifications, while using the LHS in the calculations of standardized regression coefficients (SRC) and standardized rank regression coefficient (SRRC) to determine the subset of the most important input parameters in the final screening step and to check the cumulative distribution functions obtained by RSM. Verification of the response surface model for its sufficient accuracy is a prerequisite for the reliability of the final results that can be obtained by the combined procedure proposed in the present work.

Keywords

References

  1. 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
  2. MAAP 3.0B-Modular Accident Analysis Program for LWR Power Plants v.1;2 Fauske & Associates
  3. Nuclear Technology v.49 The Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input D.H. Nguyen
  4. 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
  5. Risk Analysis v.1 no.4 Methods for Uncertainty Analysis : A Comparative Survey D.C. Cox;P. Baybutt
  6. 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
  7. Nuclear Science and Engineering v.64 Comparison of Two Uncertainty Analysis Methods Neil D. Cox
  8. Communications in Statistics v.B11 no.3 A Distribution Free Approach to Inducing Rank Correlation Among Input Variables R.L. Iman;W.J. Conover
  9. Risk Analysis v.8 no.1 An Investigation of Uncertainty and Sensitivity Analysis Techniques for Computer Models R.L. Iman;J.C. Helton
  10. Ph. D Thesis, KAIST A Study on the Uncertainty Propagation of Design and Operational Parameters of Nuclear Power Plant Tae Woon Kim
  11. 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
  12. 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
  13. 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
  14. 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
  15. 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
  16. 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
  17. 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
  18. 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
  19. Preliminary Probabilistic Safety Assessment Report : Younggwang Unit 3&4
  20. Recommended Sensitivity Analysis for an Individual Plant Examination Using MAAP 3.0B Gabor, Kenton & Associates, Inc
  21. 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