A system study on the engineering feasibility of D3He tokamak fusion power reactor

The engineering feasibility of a D³He fueled tokamak fusion power reactor is studied using a system code to obtain a consistent set of design variables and to optimize the reactor system. The study shows that the desirable ion temperature of the D³He core plasma is in the range of 50-65 keV to obtain a system with reasonable power density. The fusion energy of a core plasma is lost mainly by transport, bremsstrahlung and synchrotron radiation, of which shares are strongly dependent on the confinement characteristics, namely, on Lawson parameter. Considering physics and engineering constraints, we propose a reactor system with the double null divertor in which we expect to recover a large fraction of fusion power transported. Economical consideration suggests that the desirable minimum plasma beta is around 0.21 and thermal heat flux on the first wall and the divertor wall is larger than ~3 MW/m²