In-vessel tritium measurements using beta decay in the Tokamak Fusion Test Reactor
- Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08543 (United States)
Tritium on the inside walls of the Tokamak Fusion Test Reactor was detected by configuring the vacuum vessel as an ionization chamber and measuring the secondary electron current from the tritium beta decay. The vessel was typically filled with {approx}5 Torr of dry nitrogen and the secondary electron current was collected by an internal electrode biased to about +15 V with respect to the vessel wall. The measured variations of the collected current with gas pressure, bias voltage, and applied magnetic fields are described, as well as an {ital in situ} calibration made by injecting a known amount of tritium gas. Improved versions of this diagnostic may be useful to track the in-vessel content of surface tritium in future fusion devices. {copyright} {ital 1999 American Institute of Physics.}
- OSTI ID:
- 295684
- Report Number(s):
- CONF-980605--
- Journal Information:
- Review of Scientific Instruments, Journal Name: Review of Scientific Instruments Journal Issue: 1 Vol. 70; ISSN 0034-6748; ISSN RSINAK
- Country of Publication:
- United States
- Language:
- English
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