Thermal‐hydraulic analysis of gas‐cooled space nuclear reactor power system with closed Brayton cycle

Integrated dynamic models for all the components of the space nuclear reactor power system (SNRPS), as well as various control and auxiliary models are developed and assembled into a system analysis code SAC‐SPACE. The safety characteristics of the SNRPS during normal and abnormal operating conditions are investigated. Useful theoretical supports are provided for the design and safety analysis of the gas‐cooled SNRPS with closed Brayton cycle.