Study on Radioactive Source Term of Primary Coolant System in Fluoride Salt Cooled High Temperature Reactor

The radioactive source term of primary coolant in fluoride salt cooled high temperature reactor (FHR) was studied in normal operating conditions. The main contributions of primary coolant source term were theoretically analyzed. Neutron spectrum, fuel source term concentration and source term activation and diffusion in primary coolant were also studied using 3D Monte Carlo transport program KENOⅥ, burnup analysis program ORIGEN-S and scientific computing program Mathematica. The radioactive source term of primary coolant was quantitatively analyzed based on one kind of design scheme of FHR using this method. The results show that tritium source term in primary coolant is higher than that of other reactors, tritium production rate is 5.16×10¹⁴ Bq•GWth^-1•d^-1, and its release to the environment should be limited using effective method. The results can be used as reference for engineering design, radiation protection design, tritium control and waste treatment system design for FHR.