AbstractAqueous lithium salt blankets have some very attractive features which make them likely candidates for use in the next generation of fusion devices such as ITER and beyond. The main attraction derives from the fact that such a blanket can go from a non-tritium-breeding state to a tritium breeding state by the simple dissolution of a lithium salt into the cooling water. Such a blanket is also relatively simple to design and analyze, and is amenable to accommodating penetrations. On the other hand, the salt solution raises concern with respect to radiolysis, electrolysis and corrosion, as well as safety issues related to them. This paper describes the design of the US entry of an aqueous salt blanket for ITER.
Aqueous salt blanket tritium concentration control by water storage