Monte Carlo Calculations of Fast Neutron Transport in Chloride Salts

The purpose of this study is to provide data for optimization of an experimental campaign that is under preparation within the frame of the ADAR project (Accelerator Driven Advanced Reactor with molten chloride salt fuel coolant). This article presents results of theoretical investigation of fast neutron field behavior in chloride salt environment. Non-fueled salt coolant (NaCl, KCl, MgCl 2 ) as well as subcritical fuel-containing (PuCl 3 ) one were considered. As an external neutron source, the radio-isotope AmBe source was modelled. Monte Carlo calculations were performed using the MCNP6.2 code with the ENDF/B-VIII.0 and JEFF-3.3 nuclear data libraries.