Abstract
Tritium retention and removal are critical issues for the success of ITER or any DT fusion reactor. The Tokamak Fusion Test Reactor, TFTR, is the first fusion facility to afford the opportunity to study the tritium retention and removal over an extended period. In TFTR, tritium accumulates on all surfaces with line of sight to the plasma by codeposition of tritium with carbon. Measurements of both deuterium and tritium retention fractions have yielded retention between 0.2 and 0.6 of the injected fuel in the torus. Tritium has been successfully removed from TFTR by glow discharge cleaning and by air purges. The in-vessel inventory was reduced by a factor of 2, facilitating machine maintenance. In TFTR, the amount of dust recovered from the TFTR vacuum vessel has varied from several grams to a few kilograms.
| Original language | English (US) |
|---|---|
| Pages | 279-282 |
| Number of pages | 4 |
| State | Published - 1998 |
| Event | Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) - San Diego, CA, USA Duration: Oct 6 1997 → Oct 10 1997 |
Other
| Other | Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) |
|---|---|
| City | San Diego, CA, USA |
| Period | 10/6/97 → 10/10/97 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering