Verification of multi-group cross-section generation code ARES-MACXS with fusion neutron shielding benchmark OKTAVIAN-Fe

Abstract

Fusion devices are always characterized by complex geometries and high neutron energy, which pose great challenges in the transport calculations. The discrete ordinates method (SN) with the advantages of high precision, high efficiency and the adaptivity to deep penetration problems is applied to fusion neutron calculations. High accuracy multi-group cross-sections are essential foundation to solve transport equations in SN methods. Therefore, how to select appropriate corrections and parameters in processing multi-group cross-sections for different nuclear systems is an interesting theme. We independently developed a multi-group cross-section generation code ARES-MACXS based on the Bondarenko method, which deals with the MATXS format multi-group cross-section library to generate problem-dependent macro cross-section data. In this paper, multi-group cross-sections are obtained for the fusion neutron shielding calculation based on the recently released CENDL-3.2 nuclear data library by ARES-MACXS. Moreover, a series of cross-section parameters and corrections are applied to calculate and analyze the OKTAVIAN-Fe benchmark. Comparisons with the RMC results shows that the parameters and corrections have varying extent of impacts for the multi-group cross-sections and a suitable combination is found for OKTAVIAN-Fe benchmark, which provides a valuable reference for other similar fusion engineering shielding calculation.