SST-1
The focus of SST-1 research plan is to study plasma current drive through lower hybrid, including the active feedback control and plasma-wall interactions in steady-state plasmas.
Quoted verbatim from the IAEA World Survey of Fusion Devices, not paraphrased.
- Operator
- Institute for Plasma Research
- Type
- Fusion device
- Approach
- Tokamak
- Country
- IN
- Status
- Operating
- Built
- 2013
- Ownership
- public
Measurements
1.1 m Major radius claimed
0.2 m Minor radius claimed
0.1 MA Plasma current claimed
1.5 T On-axis magnetic field claimed
0.65 s Plasma duration claimed
nominal