ARIES-RS is one of the major magnetic fusion energy reactor designs that uses a blanket having vanadium alloy structure cooled
by lithium [
1,
2]. It is a deuterium–tritium (DT) fusion driven reactor, having a fusion power of 2170 MW [
1,
2]. This study presents the neutronic analysis of the ARIES-RS fusion reactor using heavy metal molten salts in which Li
2BeF
4 as the main constituent was mixed with increased mole fractions of heavy metal salt (ThF
4 or UF
4) starting by 2 mol.% up to 12 mol.%. Neutron transport calculations were carried out with the help of the SCALE 4.3 system
by solving the Boltzmann transport equation with the XSDRNPM code in 238 neutron groups and a
S
8–
P
3 approximation. According to the numerical results, tritium self-sufficiency was attained for the coolants, Flibe with 2%
UF
4 or ThF
4 and 4% UF
4. In addition, higher energy multiplication values were found for the salt with UF
4 compared to that with ThF
4. Furthermore, significant amount of high quality nuclear fuel was produced to be used in external reactors.
Keywords Heavy metal molten salt - Fissile fuel breeding - Tritium breeding