Published January 1999 | Version v1
Journal article

In-vessel tritium measurements using beta decay in the Tokamak Fusion Test Reactor

  • 1. Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08543 (United States)

Description

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 ∼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 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 1999 American Institute of Physics

Additional details

Publishing Information

Journal Title
Review of Scientific Instruments
Journal Volume
70
Journal Issue
1
Journal Page Range
p. 1119-1122
ISSN
0034-6748
CODEN
RSINAK

Conference

Title
12. topical conference on high-temperature plasma diagnostics
Dates
7-11 Jun 1998
Place
Princeton, NJ (United States)

Optional Information

Secondary number(s)
CONF-980605--