REMOVAL OF TRITIUM FROM TFTR

Operation of the Tokamak Fusion Test Reactor (TFTR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and other internal h ardware. The use of discharge cleaning techniques and venting to remov e the tritium was investigated. The tritium was introduced into TFTR b y neutral beam injection and by gas puffing. The graphite limiter is s ubject to erosion and codeposition. While short term retention was hig h, the retention averaged over the 1993-1995 D-T campaign was 52 % +/- 15 %. The tritium removal techniques resulted in lowering the in-vess el inventory from 16.4 kCi at the end of 1995 operation to 7.2 kCi at the start of the 1996 experimental program.