Thermohydraulic and mechanical design assessment of tube-panel first wall for tokamak fusion power reactor

A first wall structural concept cooled by high temperature and pressurized water has been proposed for the Tokamak Fusion Power Reactor (SPTR-P). Among a number of candidate design concepts, a tube-panel structure was selected for the first wall design. Stainless steel serves as the first wall structural material. The first wall is separated from the blanket wall and has a circular cross-section coolant channel since this shape is the most desirable for resisting the mechanical load due to the pressurized cooling water. Feasibility of the thermohydraulic and mechanical design has been established by analyses under steady-state operating conditions. The effect of the heat load during plasma disruptions on the thermomechanical characteristics of the first wall has been clarified. The mechanical strength of the first wall of power reactor is inadequate to withstand the thermal load expected during plasma disruption in an experimental reactor