The in-vessel tritium inventory for the Compact Ignition Tokamak

This paper presents quantitative predictions for the tritium inventory in the plasma-facing components of the Compact Ignition Tokamak. These predictions are partially based on tritium retention experiments performed in the Tritium Plasma Experiment on graphites and carbon-carbon composites. Also considered were the results of measurements on co-deposition of carbon and deuterium performed in the Laser Assisted Material Plasma Experiment. In addition, measurements of deuterium retained in graphite tiles removed from the Tokamak Fusion Test Reactor provided input into the final tritium predictions