Applicability analysis of multi-group cross sections processing code ARES-MACXS for shielding calculation

BackgroundDeterministic method is widely used in shielding calculation for fusion and fission devices. The data accuracy of multi-group cross section has significant influence on the deterministic calculation results.PurposeThis study aims to obtain a multi-group cross-section library suitable for various shielding problems by developing a multi-group cross-section processing code ARES-MACXS based on Bondarenko resonance processing method with functionalities of resonance processing, temperature interpolation, transport correction, up-scattering processing, collapse group, and so on, and uses the exponential interpolation method to obtain more accurate multi-group cross sections.MethodFirst of all, KASHIL_E70 library and FENDLL-3.1d library were respectively processed by ARES-MACXS for single nuclide calculation to verify the correctness of the code, and the results were compared with continuous energy Monte Carlo code. Then, the ill-Fe, OKTAVIAN-Al and other benchmarks were calculated to verify the applicability of the code to different nuclides, and the results were compared with the continuous energy Monte Carlo code. Finally, the ill-Fe, OKTAVIAN-Al and other benchmarks calculated by ARES-MACXS were compared with experimental measurements.ResultsThe error between the deterministic transport calculation result and the Monte Carlo calculation result is less than 1%, the error between the deterministic transport calculation result and experimental measurement values is less than 20%.ConclusionsThe results show that the multi-group cross sections calculated by ARES-MACXS have reliable accuracy and can be applied to the verification of benchmarks, hence can be applied to the calculation of engineering problems.