Preliminary Thermal Safety Design of Research Reactor Mainly for Production of Fission ⁹⁹Mo

The reactor core general design of the research reactor mainly for production of fission ⁹⁹Mo was developed. The reactor’s thermal hydraulic parameters were calculated by using the COTH code based on the neutronics calculation result and the thermal hydraulic design limitation. The results show that the core general design satisfies the design requirement.