Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2013 (2013), Article ID 573697, 11 pages
Research Article

SCALE Modeling of Selected Neutronics Test Problems within the OECD UAM LWR’s Benchmark

1Karlsruhe Institute of Technology (KIT), Campus Nord, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany
2The Pennsylvania State University (PSU), 206 Reber Building, University Park, PA 16803, USA

Received 20 July 2012; Accepted 20 December 2012

Academic Editor: Oscar Cabellos

Copyright © 2013 Luigi Mercatali 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. Ivanov et al., “Benchmark for Uncertainy Analysis in Modeling (UAM) for Design, Operation and Safety Analysis of LWRs,” NEA/NSC/DOC, 2012.
  2. J. Solis, K. Ivanov, B. Sarikaya, A. Olson, and K. Hunt, “BWR TT Benchmark. Volume I: Final Specifications,” NEA/NSC/DOC, 2001.
  3. K. Ivanov, T. Beam, A. Baratta, A. Irani, and N. Trikouros, “PWR MSLB Benchmark. Volume 1: Final Specifications,” NEA/NSC/DOC(99), 1999.
  4. B. Ivanov, K. Ivanov, P. Groudev, M. Pavlova, and V. Hadjiev, “VVER-1000 Coolant Transient Benchmark (V1000-CT). Phase 1—Final Specification,” NEA/NSC/DOC, 2002.
  5. “Benchmark on the KRITZ-2 LEU and MOX Critical Experiments—Final Report,” NEA/NSC/DOC, 2005.
  6. C. Vaglio and A. Santamarina, “Assembly and core specification of generation 3 PWR,” CEA Report, 2010. View at Google Scholar
  7. B. Rearden, C. M. Hopper, K. R. Elam et al., “Applications of the TSUNAMI sensitivity and uncertainty analysis methodology,” in Proceedings of the 7th International Conference on Nuclear Criticality Safety (ICNC '03), Tokai-mura, Japan, October 2003.
  8. G. Palmiotti and M. Salvatores, “Developments in sensitivity methodologies and the validation of reactor physics calculations,” Science and Technology of Nuclear Installations, vol. 2012, Article ID 529623, 14 pages, 2012. View at Publisher · View at Google Scholar
  9. H. Brooks, “Perturbation Theory for Boltzmann Equation,” KAPL-304, 1950.
  10. G. Aliberti, L. Mercatali, G. Palmiotti, and M. Salvatores, “A systematic approach to nuclear data uncertainties and their impact on transmutation strategies,” in Proceedings of the International Workshops on Nuclear Data for Transmutation, Darmstadt, Germany, September 2003.
  11. A. Gandini, “Uncertainty analysis and experimental data transposition methods based on perturbation theory,” in Uncertainty Analysis, Y. Ronen, Ed., CRC Press, Boca Raton, Fla, USA, 1988. View at Google Scholar
  12. E. Greenspan, “Developments in perturbation theory,” in Advances in Nuclear Science and Technology, J. Lewins and A. Becker, Eds., vol. 14, Plenum Press, 1982. View at Google Scholar
  13. M. L. Williams, B. L. Broadhead, and C. V. Parks, “Eigenvalue sensitivity theory for resonance-shielded cross sections,” Nuclear Science and Engineering, vol. 138, no. 2, pp. 177–191, 2001. View at Google Scholar · View at Scopus
  14. “SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design,” ORNL/TM-2005/39, Version 6.1. Oak Ridge National Laboratory. Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-785, 2011.
  15. M. B. Chadwick, P. Obložinský, M. Herman et al., “ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology,” Nuclear Data Sheets, vol. 107, pp. 2931–3060, 2006. View at Google Scholar
  16. B. T. Rearden, M. L. Williams, M. A. Jessee, D. E. Mueller, and D. A. Wiarda, “Sensitivity and uncertainty analysis capabilities and data in SCALE,” Nuclear Technology, vol. 174, no. 2, pp. 236–288, 2011. View at Google Scholar · View at Scopus
  17. M. L. Williams, “Resonance self-shielding methodologies,” Nuclear Technology, vol. 174, pp. 149–168, 2011. View at Google Scholar
  18. N. M. Greene, L. M. Petrie, and M. L. Williams, “XSDRNPM: A One-Dimensional Discrete-Ordinates Code for Transport Analysis,” ORNL/TM-2005/39, 2011.
  19. B. T. Rearden, L. M. Petrie, M. A. Jessee, and M. L. Williams, “SAMS: Sensitivity Analysis Module for SCALE,” ORNL/TM-2005/39, 2011.
  20. M. L. Williams, D. Wiarda, G. Arbanas, and B. L. Broadhead, “SCALE Nuclear Data Covariance library,” ORNL/TM-2005/39, 2011.
  21. A. Trkov, G. L. Molnár, Z. Révay et al., “Revisiting the 238U thermal capture cross section and gamma-ray emission probabilities from 239Np decay,” Nuclear Science and Engineering, vol. 150, no. 3, pp. 336–348, 2005. View at Google Scholar · View at Scopus
  22. J. Leppänen, Development of a new Monte Carlo reactor physics code [D. Sc. Thesis], Helsinki University of Technology, 2007.
  23. E. Fridman and J. Leppänen, “On the use of the Serpent Monte Carlo code for few-group cross section generation,” Annals of Nuclear Energy, vol. 38, no. 6, pp. 1399–1405, 2011. View at Publisher · View at Google Scholar · View at Scopus
  24. “The JEFF-3.1.1 Nuclear Data Library,” NEA JEFF Report 22, OECD, 2009.
  25. X-5 Monte Carlo Team, “MCNP—A General Monte Carlo N-Particle Transport Code (Version 5),” Los Alamos National Laboratory. LA-CP-03-0245, 2003.