Tokamak type of nuclear fusion power reactors has been conceptually designed in the Japan Atomic Energy Research Institute. The first wall is subjected to high heat flux and high energetic neutrons or particles from the plasma reacting nuclear fusion. Heat flux beyond 10MW/m^2 loads on a divertor plate locally. Therefor, some concepts of liquid wall are proposed as the first wall. A concept of liquid wall in the tokamak reactor was examined in terms of heat removal by simulations using the computational fluid dynamics (CFD) analysis codes. In the concepts, liquid such as the molten-salt Flibe is introduced to remove heat flux from the plasma. The CFD codes, STAR-CD and FLUENT based on the finite volume analysis method were used to model the flowing liquid wall. It was indicated that the STAR-CD and FLUENT tend to result in a lower value than the true heat flux, because the heat flux is applied to the free liquid surface via a gaseous layer.
