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Science and Technology of Nuclear Installations
Volume 2012, Article ID 625878, 10 pages
Research Article

Uncertainty and Sensitivity of Neutron Kinetic Parameters in the Dynamic Response of a PWR Rod Ejection Accident Coupled Simulation

1Institute for the Industrial, Radiophysical and Environmental Safety (ISIRYM), Universitat Politècnica de València, 46022 Valencia, Spain
2Applied Statistics, Operations Research and Quality Department, Universitat Politècnica de València (UPV), Cami de Vera, s/n, 46022 Valencia, Spain
3Lehrstuhl für Nukleartechnik, Technische Universität München (TUM), Boltzmannstraße 15, 85747 Garching, Germany

Received 21 August 2012; Revised 24 October 2012; Accepted 12 November 2012

Academic Editor: Oscar Cabellos

Copyright © 2012 C. Mesado et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. O. Roselló, Desarrollo de una metodología de generación de secciones eficaces para la simplificación del núcleo de reactores de agua ligera y aplicación en códigos acoplados neutrónicos termohidráulicos [Ph.D. thesis], Universitat Politècnica de València, 2004.
  2. V. Kreinovich and S. A. Ferson, “A new Cauchy-based black-box technique for uncertainty in risk analysis,” Reliability Engineering and System Safety, vol. 85, no. 1–3, pp. 267–279, 2004. View at Publisher · View at Google Scholar · View at Scopus
  3. J. Juanas, R. Macián, F. Ánchel, T. Barrachina, R. Miró, and G. Verdú, “Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermalhydraulic-neutronic simulations,” in International Conference on Nuclear Energy for New Europe, Portorož, Slovenia, September 2010.
  4. J. C. Helton and F. J. Davis, “Latin hypercube sampling and the propagation of uncertainty in analyses of complex systems,” Reliability Engineering and System Safety, vol. 81, no. 1, pp. 23–69, 2003. View at Publisher · View at Google Scholar · View at Scopus
  5. H. G. Glaeser, “Uncertainty evaluation of thermal-hydraulic code results,” in Proceedings of the International Meeting on Best Estimate Methods in Nuclear Installation Safety Analysis (BE '00), Washington, DC, USA, November 2000.
  6. S. S. Wilks, Mathematical Statistics, John Wiley & Sons, 1962.
  7. S. Hong, Oh, and Kim, “Generic application of Wilks tolerance limits evaluation approach to nuclear safety,” in OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations, Barcelona, Spain, 2011 November.
  8. R. L. Iman and W. J. Conover, “A distribution- free approach to inducing rank correlation among input variables,” Communications in Statistics B, vol. 11, no. 3, pp. 311–334, 1982. View at Google Scholar
  9. M. D. McKay, R. J. Beckman, and W. J. Conover, “A comparison of three methods for selecting values of input variables in the analysis of output from a computer code,” Technometrics, vol. 21, no. 2, pp. 239–245, 1979. View at Google Scholar · View at Scopus
  10. A User’s Guide to Sandia’s Latin Hypercube Sampling Software: LHS UNIX Library/Standalone Version.
  11. DAKOTA, A Multilevel Parallel Object-Oriented Framework for Design Optimization, Parameter Estimation, Uncertainty Quantification, and Sensitivity Analysis. Version 5.2 User’s Manual.
  12. DAKOTA Jaguar 2.1 User’s Manual.