The Tokamak Fusion Test Reactor (TFTR) has 4 years of experience with tritium operation. This includes 23,000 discharges of which 750 had tritium neutral beam injection (NBI). About 100 g of tritium were processed through the tritium systems and about 5 g of tritium were injected into TFTR either by NBI or gas puffing during this period. About 1/2 of the injected tritium was retained in the vacuum vessel and associated hardware during normal operation. Based upon past measurements of deuterium retention, it is expected that about equal amounts of the retained tritium would reside in codeposited carbon layers on the limiter and on the walls far from the plasma contact points. A variety of techniques, including He glow discharge cleaning (GDC), D2 GDC, He-O2 GDC, pulse discharge cleaning (PDC), baking to 150 C in both vacuum and air, and N2 and air vents, were used to remove tritium from the torus. The effectiveness of these techniques will be compared. Dust samples have been removed from the torus and are being analyzed for particle size as well as tritium content. In the next few months, several of the graphite bumper limiter tiles will be removed for ex-situ analysis of the tritium content. The results of this experience and the tritium retention and removal will be discussed and compared to past deuterium retention measurements.

*Work supported by U.S. DOE Contract No. DE-AC02-76-CHO3073.