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), 2024. Published by Science Publishing Group |
BAPL, JEFF-3.1.2, JENDL-4.0u, NJOY99.0, TRIGA MARK-II, TRX and WIMSD-5B
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APA Style
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
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
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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Download@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}
}
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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