Experiments on TFTR supershot plasmas

Strachan, J D; Bell, M; Janos, A; Kaye, S; Kilpatrick, S; Manos, D; Mansfield, D; Mueller, D; Owens, K; Timberlake, J.; Pitcher, C. S.; Snipes, J. A.

doi:10.2172/10141725

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Tritium Injection and Removal During L-mode Experiments1

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1996

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“…The amount of tritium puffed into the torus by gas injection system in September was 10 600 Ci, much higher than the 203 Ci puffed in the earlier tritium transport experiments. 26 This incorporated high power neutral beam heated discharges followed by discharges with lithium pellet injection 27 to reduce the edge influx. The isotopic mix of hydrogenic isotopes recycled from the limiter is measured spectroscopically by measurements of the H ␣ , D ␣ , and T ␣ emission lines.…”

Section: Tritium Injection and Removal During L-mode Experimentsmentioning

confidence: 99%

Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor

Skinner

Blanchard

Kamperschroer

et al. 1996

Journal of Vacuum Science &Amp; Technology A: Vacuum, Surfaces, and Films

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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%. 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 ≊8000 Ci and restoring the tritium inventory to a level well below the administrative limit.

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Section: Tritium Injection and Removal During L-mode Experimentsmentioning

confidence: 99%