Evaluation of the New ENDF/B-VIII.0 Nuclear Data Library on Neutronic Parameters Calculations for First Core RSG-GAS Reactor

The ENDF/B-VIII.0 nuclear data library has been developed with WIMSD-5B for our in-house research reactor depletion code, Batan-FUEL, to analyze the G. A. Siwabessy Multipurpose Reactor (RSG-GAS) reactor parameter. The neutronic parameters include excess reactivity, total control rod worth, power distribution, and fuel burnup. The calculated excess reactivity and total control rod worth were compared to the experimental data, while the power distribution and burnup calculations were compared to the Monte Carlo code Serpent 2. Compared with the experiments, the excess reactivity calculated by Batan-FUEL using the ENDF/B-VIII.0 data library showed a discrepancy of 4.2%, with the total control rod worth differing by up to 3.63%. The calculated excess reactivity with the ENDF/B-VII.1 data library showed a slight difference to the experiment of 0.35%, while the control rod worth was 5.07%. With the lack of experimental data for radial power distribution and fuel assembly burnup, these calculated parameters were compared to the Serpent 2 calculations, which agreed well with no significant difference. The generated macroscopic cross-section data utilizing WIMSD-5B for Batan-FUEL needs to be evaluated for further use.