Abstract
The Tokamak Fusion Test Reactor (TFTR) has been operating safely and routinely with deuterium-tritium fuel for more than two years. In this time, TFTR has produced a number of record breaking results including core fusion power, ∼ 2 MW/m3, comparable to that expected for ITER. Advances in wall conditioning via lithium pellet injection have played an essential role in achieving these results. Deuterium-tritium operation has also provided a special opportunity to address the issues of tritium recycling and retention. Tritium retention over two years of operation was approximately 40%. Recently the in-torus tritium inventory was reduced by half through a combination of glow discharge cleaning, moist-air soaks, and plasma discharge cleaning. The tritium inventory is not a constraint in continued operations. Recent results from TFTR in the context of plasma wall interactions and deuterium-tritium issues are presented.
Original language | English (US) |
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Pages (from-to) | 214-226 |
Number of pages | 13 |
Journal | Journal of Nuclear Materials |
Volume | 241-243 |
DOIs | |
State | Published - Feb 11 1997 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- General Materials Science
- Nuclear Energy and Engineering
Keywords
- Helium exhaust and control
- TFTR
- Tritium inventory and economy
- Wall conditioning
- Wall particle retention