Abstract
Princeton Plasma Physics Laboratory and the Massachusetts Institute of Technology are preparing an experiment of current profile control using lower hybrid waves to produce and sustain advanced tokamak regimes in steady-state conditions in Alcator C-Mod. Unlike the Joint European Torus, ToreSupra, and JT60 couplers, the C-Mod lower hybrid coupler does not employ the now conventional multijunction design but will have similar characteristics, compactness, and internal power division while retaining full control of the antenna element phasing. This is achieved by using 3-dB vertical power splitters and a stack of laminated plates with the waveguides milled in them. Construction is simplified and allows easy control and maintenance of all parts. Many precautions are taken to avoid arcing. Special care is also taken to avoid the recycling of reflected power, which could affect the coupling and the launched n∥ spectrum. The results from C-Mod should allow further simplification in the designs of the coupler planned for KSTAR and ITER.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 145-152 |
| Number of pages | 8 |
| Journal | Fusion Science and Technology |
| Volume | 43 |
| Issue number | 2 |
| DOIs | |
| State | Published - Mar 2003 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- General Materials Science
- Mechanical Engineering
Keywords
- C-mod tokamak
- Lower hybrid current drive
- Lower hybrid technology