T-11M
The main purpose of T-11M is to conduct research on lithium plasma facing components protection and lithium injection into scrape-off-layer plasma.
Quoted verbatim from the IAEA World Survey of Fusion Devices, not paraphrased.
- Type
- Fusion device
- Approach
- Tokamak
- Country
- RU
- Status
- Operating
- Built
- 1985
- Ownership
- public
Measurements
0.7 m Major radius claimed
0.2 m Minor radius claimed
0.1 MA Plasma current claimed
1 T On-axis magnetic field claimed
0.25 s Plasma duration claimed
nominal