MEASUREMENTS OF TRITIUM RETENTION AND REMOVAL ON THE TOKAMAK FUSION TEST REACTOR

Recent experiments on the Tokamak Fusion Test Reactor have afforded an opportunity to measure the retention of tritium in a graphite limiter that is subject to erosion, codeposition, and high neutron flux. The tritium was injected by both gas puff and neutral beams. The isotopic mix of hydrogenic recycling was measured spectroscopically and the tri tium fraction T/(H+D+T) transiently increased to as high as 75%. Some tritium was pumped out during the experimental run and some removed in a subsequent campaign using various clean-up techniques. While the sh ort term retention of tritium was high, various conditioning technique s were successful in removing approximate to 8000 Ci and restoring the tritium inventory to a level well below the administrative limit. (C) 1996 American Vacuum Society.