The upgrade of the DIII-D 110 GHz ECH system to 6 MW
- Resource Type
- Conference
- Authors
- Cary, W.P.; Callis, R.W.; Lohr, J.M.; Ponce, D.; Legg, R.A.
- Source
- 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050) Fusion engineering Fusion Engineering, 1999. 18th Symposium on. :190-193 1999
- Subject
- Fields, Waves and Electromagnetics
Nuclear Engineering
Plasma sources
Gyrotrons
Plasma chemistry
Power generation
Chemical vapor deposition
Tokamaks
Power transmission lines
Helium
Particle beams
Plasma waves
- Language
ECH power has proven capabilities to both heat and drive current in energetic plasmas. Recent developments in high power sources have made the use of these capabilities in energetic plasmas feasible. For the second phase of ECH power on DIII-D, there will be three 1 MW sources added to the existing 3 MW for a total generated power of 6 MW. The upgrade is based on the use of single disc CVD (chemical vapor deposition) diamond windows on 1 MW gyrotrons developed by CPI. All gyrotrons are connected to the tokamak by low-loss-windowless evacuated transmission lines using a circular corrugated waveguide for propagation in the HE/sub 11/ mode. Each waveguide system incorporates a two-mirror launcher which can steer the rf beam poloidally from the center to the outer edge of the plasma and toroidally for either co- or counter-current drive. The total system overview and integration with existing systems will be discussed along with the new aspects of the upgrade from building modifications to the new launchers. Much of the upgrade is comprised of existing designs, which will need only slight modifications, while some components have required new designs because of longer pulse lengths.