TRITIUM REMOVAL FROM TFTR

Continued operation of the tokamak fusion test reactor (TFFR) with a m ixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and to inv estigate the use of discharge cleaning techniques and venting to remov e the tritium. The tritium was introduced into TFTR by neutral beam in jection and by gas puffing. The limiter is subject to erosion and code position. While short term retention was high, the retention averaged over the 1993-1995 D-T campaign was 52 +/- 15%. The tritium removal te chniques resulted in lowering the in-vessel inventory from 16.4 kCi (1 Ci = 2.076 X 10(19) tritium atoms and 10 kCi = 1.04 g) at the end of 1995 operation to 7.2 kCi at the start of the 1996 experimental progra m.