抄録
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.
| 本文言語 | 英語 |
|---|---|
| ページ(範囲) | 211-214 |
| ページ数 | 4 |
| ジャーナル | Fusion Engineering and Design |
| 巻 | 83 |
| 号 | 2-3 |
| DOI | |
| 出版ステータス | 出版済み - 4月 2008 |
!!!All Science Journal Classification (ASJC) codes
- 土木構造工学
- 原子力エネルギーおよび原子力工学
- 材料科学一般
- 機械工学
フィンガープリント
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