Feasibility study of 99Mo radioisotope production using uranium molten salt target irradiation by 30 Mev proton Cyclotron

Fluoride Uranium-Thorium molten salts are widely used in the molten salt reactors in different compositions. The most important characteristic of the MSRs is high melting and boiling point. Therefore, the use of molten salt solution of uranium fluoride can eliminate the need for heat transfer in radioisotope production systems by accelerators. The initial study of the use of this molten salt as a target material in a cyclotron accelerator was carried out to generate various radioisotopes. We used MCNPX and ALICE/ASH. The results of this study show that the use of these molten salts can solve the problem of heat transfer and limit the application of proton beam flow on the target material. While also producing and harvesting various radioisotope products simultaneously.By optimizing the target geometry, we can increase the production rate of the different fission products in molten salt material. In addition, the use of accelerators can reduce the dependence of the production of radioisotopes used in medicine and industry to nuclear reactors.