The validation of neutron transport in chlorine in LR-0 reference field

Abstract

Nuclear energy is one of the promising ways of reaching carbon neutrality, but this goal requires the development of new reactor types. One such concept is the molten salt reactor system, which uses chlorine-based fuel salts. Developing this system needs reliable neutronic data for all materials used, with particular emphasis on core components. While uranium cross-sections remain well-studied, sufficient experimental data for chlorine is lacking, particularly for validations of current data evaluations. This paper presents new, precise integral experiments to validate various chlorine cross-section evaluations. Notably, compared with experimental results, the currently available data sets exhibit significant discrepancies, suggesting that simulations based on current nuclear data evaluations may be unreliable.