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Science and Technology of Nuclear Installations
Volume 2013, Article ID 380284, 10 pages
Research Article

Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1

1Department of Nuclear Engineering, Universidad Politécnica de Madrid, C/José Gutiérrez Abascal 2, 28006 Madrid, Spain
2Institute of Nuclear Fusion, Universidad Politécnica de Madrid, C/José Gutiérrez Abascal 2, 28006 Madrid, Spain

Received 22 August 2012; Accepted 7 December 2012

Academic Editor: Kostadin Ivanov

Copyright © 2013 C. J. Díez 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. K. Ivanova, M. Avramova, S. Kamerow et al., Benchmark For Uncertainty Analysis in Modeling (UAM) For Design, Operation and Safety Analysis of LWRs, NEA/NSC/DOC, 2012.
  2. Oak Ridge National Laboratory, “SCALE: a comprehensive modeling and simulation suite for nuclear safety analysis and design,” ORNL/TM-2005/39, version 6.1, Radiation Safety Information Computational Center, Oak Ridge National Laboratory as CCC-785, 2011.
  3. D. B. Pelowitz, “MCNPX user's manual,” Tech. Rep. LA-CP-07-1473, Los Alamos National Laboratory, 2008. View at Google Scholar
  4. J. Favorite, “Eigenvalue sensitivity analysis using the MCNP5 perturbation capability,” in Proceedings of the Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance, pp. 245–255, American Nuclear Society, 2009.
  5. B. C. Kiedrowski and F. B. Brown, “Comparison of the Monte Carlo adjoint-weighted and di perturbation methods,” Progress in Nuclear Science and Technology, vol. 2, pp. 836–841, 2011. View at Google Scholar
  6. D. G. Cacuci, Sensitivity and Uncertainty Analysis, Chapman Hall/CRC, London, UK, 2003.
  7. Y. Nagaya and F. B. Brown, “Estimation of the change in k-effective due to perturbed fission source distribution in MCNP,” in Proceedings of the ANS Mathematics & Computation Topical Meeting (M&C '03), Gatlinburg, Tenn, USA, 2003.
  8. Y. Nagaya and F. B. Brown, “Implementation of a method to estimate change in eigenvalue due to perturbed fission source distribution into MCNP,” Tech. Rep. LA-UR-03-1387, Los Alamos National Laboratory, 2003. View at Google Scholar
  9. K. Raskach, “An improvement of the monte carlo generalized differential first- and second-order perturbations of fission source,” Nuclear Science and Engineering, vol. 162, no. 2, pp. 158–166, 2009. View at Google Scholar
  10. J. A. Favorite, “On the accuracy of the differential operator Monte Carlo perturbation method for eigenvalue problems,” Technical Report LA-UR-09-4207, Los Alamos National Laboratory, 2009. View at Google Scholar
  11. B. Rearden and R. Lefebvre, “Getting Started with VIBE as a DICE Plug-in Module,” Tech. Rep. ORNL/TM-2010/60, Oak Ridge National Laboratory, 2010. View at Google Scholar
  12. T. Viitanen and J. Leppanen, “ZZ SERPENT117-ACELIB, Continuous-energy X-sec lib., radioactive decay, fission yield data for SERPENT in ACE,” Tech. Rep. NEA-1854, 2010. View at Google Scholar
  13. G. Chiba, “ERRORJ—a code to process neutron-nuclide reaction cross section covariance, version 2.3,” JAEA-Data/Code 2007-007, Japan Atomic Energy Agency, 2007. View at Google Scholar
  14. R. L. Perel, “Sensitivities of keff calculated with Monte-Carlo methods: theory and first results,” Tech. Rep. JEF-DOC-1123, Nuclear Energy Agency, 2005. View at Google Scholar