Abstract
Advanced tokamak (AT) research in DIII-D was carried out to provide a scientific basis for steady-state high performance operation in plasma devices. The regimes required high toroidal beta to maximize fusion output and high poloidal beta to maximize the self-driven bootstrap current. Resistive wall mode stabilization by plasma rotation and active feedback with non-axisymmetric coils allowed routine operation above the no-wall beta limit. Close coupling approach resulted in fully non-inductively driven plasmas, which was sustained up to 1 s, and approximately equal to one current relaxation time.
| Original language | English (US) |
|---|---|
| Pages (from-to) | B213-B233 |
| Journal | Plasma Physics and Controlled Fusion |
| Volume | 46 |
| Issue number | 12 B |
| DOIs | |
| State | Published - Dec 2004 |
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Condensed Matter Physics