Steady thermal-hydraulic analysis for the core of a new concept Molten Salt Reactor

The Molten Salt Reactor (MSR) researched in this paper is one of the 'Generation IV International Forum' concepts. The DRAGON code was adopted to calculate its axial and radial percent of the core power firstly. By founding the fuel salt model and graphite model respectively, the steady thermal-hydraulic characteristics of this Molten Salt Reactor core was simulated by numerical method. The results show the detailed flow distribution in the core, the temperature of the fuel salt, inner and outer wall in the representative elements.