Assessment of Various Candidate Salts Properties for Molten Salt Reactor Application by MCNP Software

Abstract

In the study, the model of Molten Salt Reactor was developed for Monte Carlo N-Particle Transport [1] computational code analysis. In the course of work, two main tasks were fulfilled, which are simulation of target material behavior as a neutron convertor (producer) under 800 MeV energy proton beam and criticality calculation of the designed reactor. As a result of analysis through the MCNP software, neutron flux and energy distributions obtained, as well as the value of $k_{eff}$ multiplication factor of Molten Salt Reactor for a number of different molten salts compositions assessed.