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 tritium fraction T/(H+D+T) transiently increased to as high as 75{percent}. Some tritium was pumped out during the experimental run and some removed in a subsequent campaign using various clean-up techniques. While the short term retention of tritium was high, various conditioning techniques were successful in removing {approx_equal}8000 Ci and restoring the tritium inventory to a level well below the administrative limit. {copyright} {ital 1996 American Vacuum Society}
- Research Organization:
- Princeton Plasma Physics Laboratory
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 392052
- Journal Information:
- Journal of Vacuum Science and Technology, A, Journal Name: Journal of Vacuum Science and Technology, A Journal Issue: 6 Vol. 14; ISSN 0734-2101; ISSN JVTAD6
- Country of Publication:
- United States
- Language:
- English
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