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 k eff , ρ 28 , δ 25 , δ 28 , 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-UO 2 -1, BAPL-UO 2 -2 & BAPL-UO 2 -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.
Highlights
A 3 MW TRIGA Mark-II research reactor has been operating in Bangladesh since 1986 at the Atomic Energy Research Establishment (AERE), Savar, Dhaka
The calculated neutron cross-section of 92-U-235 of TRX1, TRX-2, BAPL-UO2-1, BAPL-UO2-2 and BAPL-UO2-3 benchmark lattices for Japanese evaluated nuclear data library (JENDL)-4.0u and Joint Evaluated Fission and Fusion Data Library (JEFF)-3.1.2 are plotted in figure 2 to figure 6
Almost the integral parameters are closer to the standard values for JEFF-3.1.2 than JENDL-4.0u. This analysis deals with comparison of neutron crosssection of U-235& U-238 and integral parameters of TRX & BAPL benchmark lattices with the experimental values by Cross Section Evaluation Working Group (CSEWG) for evaluated nuclear data libraries JENDL-4.0u & JEFF-3.1.2 by using nuclear data processing code NJOY99.0 as well as reactor lattice code WIMSD-5B
Summary
A 3 MW TRIGA Mark-II research reactor has been operating in Bangladesh since 1986 at the Atomic Energy Research Establishment (AERE), Savar, Dhaka. The TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) is the first nuclear reactor in this country, which has been designed and constructed by the General Atomic of USA [1]. The reactor has been used in various fields of research and utilization; such as, neutron activation analysis (NAA), neutron radiography, neutron scattering, production of radioisotopes, training of manpower, academic research etc [2]. Through these activities the reactor meets the need of the people of Bangladesh to some extent. The ENDF-6 library is the latest recommended evaluated nuclear
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