Moscow University Physics Bulletin

, Volume 72, Issue 6, pp 633–637 | Cite as

Validation Study of the Reactor Physics Lattice Transport Code DRAGON5 Based on DRAGLIB Libraries by TRX and BAPL Critical Experiments of Light Water Reactors for Neutronic Analysis of TRIGA MARK-II Research Reactor

  • O. Jaï
  • O. El Hajjaji
  • A. Hébert
  • J. Tajmouati
  • T. El Bardouni
  • A. Didi
Engineering Physics


The objective of this analysis is to present the validation study of the latest release of the reactor physics lattice transport code DRAGON5 by TRX and BAPL critical experiments of light water reactors for neutrons calculations of Moroccan 2 MW TRIGA MARK-II research reactor. This study is accomplished through the analysis of integral parameters of five light water reactor critical experiments TRX-1, TRX-2, BAPL-UO2-1, BAPL-UO2-2, and BAPL-UO2-3 based on the open-source Draglibs nuclear data libraries ENDF/B-VII.1 and JEFF-3.1.2. These experiments are being considered as standard benchmarks lattices for testing and validating the reactor physics lattice transport code DRAGON5 as well as nuclear data libraries. The integral parameters—keffρ28, δ25, δ28 and C* —of the said lattices are calculated using the reactor physics lattice transport code DRAGON5 at a room temperature and compared to measured values as well as the Monte Carlo values based on the Chinese evaluated nuclear data library CENDL-3.0. It was found that the results calculated show good agreement with the experiment and the MCNP results. Therefore, this study reflects the validation, the adequacy, and the accuracy of the reactor physics lattice transport code DRAGON5 based on the open-source Draglibs nuclear data libraries ENDF/B-VII.0.1 and JEFF 3.1.2 evaluation with SHEM-295 group-structure and can also be important to execute neutronic analysis of thermal reactor such as the Moroccan 2 MW TRIGA MARK-II research reactor at CENM, achieved initial criticality on May 2, 2007.


TRX-BAPL benchmark lattices integral parameters DRAGON5 code Draglibs SHEM-295 reactor physics TRIGA MARK-II 


Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.


  1. 1.
    J. R. Brown, D. R. Harris, F. S. Frantz, J. J. Volpe, J.C. Andrews, and B. H. Noordhoff, Report No. WAPD-176 (Bettis Atomic Power Laboratory, Pittsburgh, 1958).Google Scholar
  2. 2.
    Cross Section Evaluation Working Group Benchmark Specifications (Brookhaven National Laboratory, Upton, 1986).Google Scholar
  3. 3.
    D. E. Cullen, Nucl. Sci. Eng. 55, 387 (1974).CrossRefGoogle Scholar
  4. 4.
    J. Hardy, Jr., D. Klein, and J. J. Volpe, Nucl. Sci. Eng. 40, 101 (1970).CrossRefGoogle Scholar
  5. 5.
    J. Hardy, Jr., D. Klein, and J. J. Volpe, Report No. WAPD-TM-931 (Bettis Atomic Power Laboratory, Pittsburgh, 1970).Google Scholar
  6. 6.
    A. Hébert, Applied Reactor Physics (Presses Int. Polytechnique, Montreal, 2009).Google Scholar
  7. 7.
    A. Hébert, Nucl. Sci. Eng. 162, 56 (2009).CrossRefGoogle Scholar
  8. 8.
    A. Hébert and G. Mathonniere, Nucl. Sci. Eng. 115, 129 (1993).CrossRefGoogle Scholar
  9. 9.
    A. Hébert and H. Saygin, in Proc. Seminar on NJOY-91 and THEMIS for the Processing of Evaluated Nuclear Data Files, Saclay, France, 1992, p. 103.Google Scholar
  10. 10.
    R. L. Hellens and G. A. Price, in Reactor Technology: Selected Reviews (U.S. Atomic Energy Commission, 1964), p. 529.Google Scholar
  11. 11.
    Y. U. Hongwei, Present Status of CENDL Project (China Inst. of Atomic Energy, 2007).Google Scholar
  12. 12.
    J. D. Kim, J. T. Lee, C. S. Gil, et al., Nucl. Eng. Technol. 21, 245 (1989).Google Scholar
  13. 13.
    M. J. H. Khan, A. B. M. K. Alam, M. H. Ahsan, K. A. A. Mamun, and S. M. A. Islam, Ann. Nucl. Energy 85, 1014 (2015).CrossRefGoogle Scholar
  14. 14.
    R. E. MacFarlane and D. W. Muir, NJOY99.0: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Evaluated Nuclear Data (Los Alamos National Laboratory, Los Alamos, 2000).Google Scholar
  15. 15.
    G. Marleau, A. Hébert, and R. Roy, Report No. IGE-335 (École Polytechnique de Montréal, 2014).Google Scholar
  16. 16.
    N. Martin and A. Hébert, Nucl. Sci. Eng. 167, 1 (2011).CrossRefGoogle Scholar
  17. 17.
    P. Ribon and J. M. Maillard, Report No. CEA-N-2485 (CEA, 1986).Google Scholar
  18. 18.
    A. Santamarina, D. Bernard, and Y. Rugama, The JEFF-3.1.1 Nuclear Data Library. Validation Results from JEF-2.2 to JEFF-3.1.1 (Nuclear Energy Agency, 2009).Google Scholar
  19. 19.
    A. Santamarina, N. Hfaiedh, R. Letellier, et al., Nucl. Eng. Des. 238, 1965 (2008).CrossRefGoogle Scholar
  20. 20.
    R. Sher and S. Fiarman, Report No. EPRI NP-209 (Electric Power Research Inst., 1976).Google Scholar

Copyright information

© Allerton Press, Inc. 2017

Authors and Affiliations

  • O. Jaï
    • 1
    • 2
  • O. El Hajjaji
    • 1
    • 2
  • A. Hébert
    • 3
  • J. Tajmouati
    • 2
  • T. El Bardouni
    • 1
  • A. Didi
    • 2
  1. 1.ERSN-LMR, Department of PhysicsFaculty of SciencesTetouanMorocco
  2. 2.Groupe de Génie Nucléaire (GGN), Department of Physics, Faculty of SciencesFezMorocco
  3. 3.Institut de Génie NucléaireÉcole Polytechnique de MontréalMontréalCanada

Personalised recommendations