Abstract
In a graphite-lined tokamak reactor, the interaction of the plasma with the graphite first wall will result in the formation of carbon deposits that are highly rich in tritium. This mechanism of tritium retention will be a major contributor to the in-vessel tritium inventory. In this paper, the glow-discharge technique is proposed for removing these films to reduce the inventory buildup. Glow-discharge runs were performed with feed gases of H2, He, N2, and O2. The results show that only oxygen glow discharges can remove carbon films at sufficiently large rates. The impact of this study on the Tokamak Fusion Test Reactor (TFTR) and the Compact Ignition Tokamak (CIT) is discussed. A recipe for effective glow-discharge operation on TFTR and CIT is also described.
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