Waste Management of First Wall and Blanket Structural Materials for Tokamak Fusion Reactors

A comparison has been made of the induced radioactivities in the first wall and structural materials of the breeder blanket in the high flux region for two different fusion reactor types. One system is the STARFIRE, a tokamak reactor with PCA, a modified stainless steel, as a first wall and a LiAlO₂ breeder blanket; the other is a reactor based on the STARFIRE design with a vanadium alloy as the first wall and structural material, and circulating molten lithium as the breeder/coolant. The recycling or disposal of these structural materials is evaluated.