Abstract
Fully non-inductive lower hybrid current drive (LHCD) plasmas have been achieved in TRIAM-1M and HT-7 superconducting tokamaks, but the current control in toroidal plasma was performed in different way during their steady-state operation (SSO). In HT-7, the plasma current was controlled mainly by the ohmic field, and partially by LHCD through ohmic transformer magnetic flux feedback control. In TRIAM-1M, the plasma current was controlled by lower hybrid wave (LHW) power directly according to a simple simulation model.
| Original language | English |
|---|---|
| Pages (from-to) | 211-214 |
| Number of pages | 4 |
| Journal | Fusion Engineering and Design |
| Volume | 83 |
| Issue number | 2-3 |
| DOIs | |
| Publication status | Published - Apr 2008 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- General Materials Science
- Mechanical Engineering
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