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Comparison of JEFF-3.1.2 and JENDL-4.0u for TRIGA MARK-II Calculation Through the Benchmarking of Integral Parameter of TRX and BAPL Lattices of Thermal Reactor

Received: 24 February 2017     Accepted: 24 March 2017     Published: 11 April 2017
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Abstract

The objective of this paper is to select an inimitable nuclear data library from JEFF-3.1.2 & JENDL-4.0u which are valid for theoretical safety analysis of TRIGA MARK-II research reactor. In this work the integral parameter (such as keff, ρ28, δ25, δ28, C) of TRX and BAPL benchmark lattices of thermal reactors are compared with the experimental result by Cross Section Evaluation Working Group (CSEWG), USA. The nuclear data processing code NJOY99.0 is used to generate 69-group cross-section library from the basic evaluated nuclear data files JEFF-3.1.2 & JENDL-4.0u. TRX and BAPL benchmark lattices are modeled with optimized inputs, which are suggested in the final report of the WIMS Library Update Project Stage-I (WLUP). The integral parameters of five uranium-fuel thermal assemblies: TRX-1 and TRX-2 and BAPL-UO2-1, BAPL-UO2-2 & BAPL-UO2-3 are calculated with the help of reactor lattice code WIMSD-5B based on the generated 69-group cross-section library. Form the comparison of the integral parameters with the experimental values it is found that the obtained results between the two libraries is nearly alike with some uncertainties. But the degrees of uncertainties for the values of integral parameters of JEFF-3.1.2 library are comparatively less. JEFF-3.1.2 is the better library and could be selected for the neutronic calculation of TRIGA Mark-II research reactor at AERE, Savar, Dhaka, Bangladesh.

Published in International Journal of Energy and Power Engineering (Volume 6, Issue 2)
DOI 10.11648/j.ijepe.20170602.11
Page(s) 6-12
Creative Commons

This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.

Copyright

Copyright © The Author(s), 2017. Published by Science Publishing Group

Keywords

BAPL, JEFF-3.1.2, JENDL-4.0u, NJOY99.0, TRIGA MARK-II, TRX and WIMSD-5B

References
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[3] O. Allaoui, et all., “Validation of ENDF/B-VII.0 nuclear data library for shielding calculations using the Monte Carlo method”, International Journal of Advanced Research, Vol. 2, pp. 55-62, 2014.
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[6] K. Shibata, et all., “JENDL-4.0: A new library for nuclear science and engineering”, Journal of Nuclear Science and Technology, Vol. 48, pp. 1-30, 2011.
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[14] M. M. Islam, M. M. Haque and S. M. A. Islam “Validation of data files of JENDL-4.0u for neutronic calculation of TRIGA Mark-II reactor through the investigation of integral parameter of benchmark lattices TRX and BAPL”, IOSR Journal of Journal of Applied Physics, Vol. 8, pp. 18-24, 2016.
[15] R. E. MacFarlane and D. W. Muir, “NJOY99.0: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross sections from ENDF/B”, RSICC Code Package PSR-480. Los Alamos National Laboratory, Los Alamos, New Mexico, USA, 1999.
[16] J. R. Askew, F. J. Fayers, P. B. Kemshell, “A general description of the lattice code WIMS”, Journal of the British Nuclear Energy Society, Vol. 5, pp. 564, 1966.
[17] T. Kulikowska, “WIMSD-5B: A neutronic code for standard lattice physics analysis”, Distributed by NEA Data Bank. Saclay, France, 1996.
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[19] M. Halder and S. M. T. Islam, “Comparative study of generated wimsd-5b multigroup constants library based on JENDL-3.2 with JEFF-3.1.1, CENDL-3.0 and original WIMS and validation of generated library through some benchmark experiments analysis”, IOSR Journal of Applied Physics, Vol. 8, pp. 39-43, 2016.
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[23] J. R Brown, D. R. Harris, F. S. Frantz, J. J Volpe, J. C. Andrews and B. H. Noordhoff, Kinetics and buckling measurements in lattices of slightly enriched U or UO2 rods in H2O. WAPD-176, January, 1958.
[24] S. Rana et. al., “Analysis of structural intigrity on the renovated primary cooling system of the 3MW TRIGA Mark-II research reactor”, Proceeding of the International Conferance on Mechanical Engineering & 14th Annual Paper Meet (6IMEC&14APM), Dhaka, Bangladesh, 28-29 September, 2012.
[25] M. N. Uddin, M. M. Sarker, M. J. H. Khan, S. M. A. Islam, “Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors”, Annals of Nuclear Energy, Vol. 36, pp. 1521-1526, 2009.
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[27] R. Sher, S. Fiarman, “Studies of Thermal Reactor Benchmark Data Interpretation: Experimental Corrections”, EPRI NP-209, US, October 1976.
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    Md. Mominul Islam, Md. Mahbubul Haque, S. M. Azharul Islam. (2017). Comparison of JEFF-3.1.2 and JENDL-4.0u for TRIGA MARK-II Calculation Through the Benchmarking of Integral Parameter of TRX and BAPL Lattices of Thermal Reactor. International Journal of Energy and Power Engineering, 6(2), 6-12. https://doi.org/10.11648/j.ijepe.20170602.11

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    ACS Style

    Md. Mominul Islam; Md. Mahbubul Haque; S. M. Azharul Islam. Comparison of JEFF-3.1.2 and JENDL-4.0u for TRIGA MARK-II Calculation Through the Benchmarking of Integral Parameter of TRX and BAPL Lattices of Thermal Reactor. Int. J. Energy Power Eng. 2017, 6(2), 6-12. doi: 10.11648/j.ijepe.20170602.11

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    AMA Style

    Md. Mominul Islam, Md. Mahbubul Haque, S. M. Azharul Islam. Comparison of JEFF-3.1.2 and JENDL-4.0u for TRIGA MARK-II Calculation Through the Benchmarking of Integral Parameter of TRX and BAPL Lattices of Thermal Reactor. Int J Energy Power Eng. 2017;6(2):6-12. doi: 10.11648/j.ijepe.20170602.11

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  • @article{10.11648/j.ijepe.20170602.11,
      author = {Md. Mominul Islam and Md. Mahbubul Haque and S. M. Azharul Islam},
      title = {Comparison of JEFF-3.1.2 and JENDL-4.0u for TRIGA MARK-II Calculation Through the Benchmarking of Integral Parameter of TRX and BAPL Lattices of Thermal Reactor},
      journal = {International Journal of Energy and Power Engineering},
      volume = {6},
      number = {2},
      pages = {6-12},
      doi = {10.11648/j.ijepe.20170602.11},
      url = {https://doi.org/10.11648/j.ijepe.20170602.11},
      eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijepe.20170602.11},
      abstract = {The objective of this paper is to select an inimitable nuclear data library from JEFF-3.1.2 & JENDL-4.0u which are valid for theoretical safety analysis of TRIGA MARK-II research reactor. In this work the integral parameter (such as keff, ρ28, δ25, δ28, C∗) of TRX and BAPL benchmark lattices of thermal reactors are compared with the experimental result by Cross Section Evaluation Working Group (CSEWG), USA. The nuclear data processing code NJOY99.0 is used to generate 69-group cross-section library from the basic evaluated nuclear data files JEFF-3.1.2 & JENDL-4.0u. TRX and BAPL benchmark lattices are modeled with optimized inputs, which are suggested in the final report of the WIMS Library Update Project Stage-I (WLUP). The integral parameters of five uranium-fuel thermal assemblies: TRX-1 and TRX-2 and BAPL-UO2-1, BAPL-UO2-2 & BAPL-UO2-3 are calculated with the help of reactor lattice code WIMSD-5B based on the generated 69-group cross-section library. Form the comparison of the integral parameters with the experimental values it is found that the obtained results between the two libraries is nearly alike with some uncertainties. But the degrees of uncertainties for the values of integral parameters of JEFF-3.1.2 library are comparatively less. JEFF-3.1.2 is the better library and could be selected for the neutronic calculation of TRIGA Mark-II research reactor at AERE, Savar, Dhaka, Bangladesh.},
     year = {2017}
    }
    

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  • TY  - JOUR
    T1  - Comparison of JEFF-3.1.2 and JENDL-4.0u for TRIGA MARK-II Calculation Through the Benchmarking of Integral Parameter of TRX and BAPL Lattices of Thermal Reactor
    AU  - Md. Mominul Islam
    AU  - Md. Mahbubul Haque
    AU  - S. M. Azharul Islam
    Y1  - 2017/04/11
    PY  - 2017
    N1  - https://doi.org/10.11648/j.ijepe.20170602.11
    DO  - 10.11648/j.ijepe.20170602.11
    T2  - International Journal of Energy and Power Engineering
    JF  - International Journal of Energy and Power Engineering
    JO  - International Journal of Energy and Power Engineering
    SP  - 6
    EP  - 12
    PB  - Science Publishing Group
    SN  - 2326-960X
    UR  - https://doi.org/10.11648/j.ijepe.20170602.11
    AB  - The objective of this paper is to select an inimitable nuclear data library from JEFF-3.1.2 & JENDL-4.0u which are valid for theoretical safety analysis of TRIGA MARK-II research reactor. In this work the integral parameter (such as keff, ρ28, δ25, δ28, C∗) of TRX and BAPL benchmark lattices of thermal reactors are compared with the experimental result by Cross Section Evaluation Working Group (CSEWG), USA. The nuclear data processing code NJOY99.0 is used to generate 69-group cross-section library from the basic evaluated nuclear data files JEFF-3.1.2 & JENDL-4.0u. TRX and BAPL benchmark lattices are modeled with optimized inputs, which are suggested in the final report of the WIMS Library Update Project Stage-I (WLUP). The integral parameters of five uranium-fuel thermal assemblies: TRX-1 and TRX-2 and BAPL-UO2-1, BAPL-UO2-2 & BAPL-UO2-3 are calculated with the help of reactor lattice code WIMSD-5B based on the generated 69-group cross-section library. Form the comparison of the integral parameters with the experimental values it is found that the obtained results between the two libraries is nearly alike with some uncertainties. But the degrees of uncertainties for the values of integral parameters of JEFF-3.1.2 library are comparatively less. JEFF-3.1.2 is the better library and could be selected for the neutronic calculation of TRIGA Mark-II research reactor at AERE, Savar, Dhaka, Bangladesh.
    VL  - 6
    IS  - 2
    ER  - 

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Author Information
  • Department of Physics, Hajee Mohammad Danesh Science & Technology University, Dinajpur, Bangladesh

  • Materials Science Division, Atomic Energy Centre Dhaka, Bangladesh Atomic Energy Commission, Dhaka, Bangladesh

  • Department of Physics, Jahangirnagar University, Savar, Dhaka, Bangladesh

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