DocumentCode :
325025
Title :
Multi-megawatt 110 GHz ECH system for the DIII-D tokamak
Author :
Callis, R.W. ; Lohr, J. ; Neill, R. C O ; Ponce, D. ; Prater, R.
Author_Institution :
Gen. Atomics, San Diego, CA, USA
Volume :
1
fYear :
1997
fDate :
6-10 Oct 1997
Firstpage :
417
Abstract :
Two 110 GHz gyrotrons with nominal output power of 1 MW each have been installed on the DIII-D tokamak. The first 110 GHz gyrotron built by Gycom has a nominal rating of 1 MW and a 2 s pulse length, with the pulse length being determined by the maximum temperature allowed on the edge cooled boron nitride window. This gyrotron was first operated into the DIII-D tokamak in late 1996. The second gyrotron was built by Communications and Power Industries (CPI) was commissioned during the spring of 1997. The CPI gyrotron uses a double disc FC-75 cooled sapphire window which has a pulse length rating of 0.8 s at 1 MW, 2 s at 0.5 MW and 10 s at 0.2 MW. Both gyrotrons are connected to the tokamak by a low-loss-windowless evacuated transmission line using circular corrugated waveguide for propagation in the HE11 mode. Using short pulse lengths to avoid breakdown inside the air filled waveguide, the microwave beam has been measured inside the DIII-D vacuum vessel using a paper target and an IR camera. The resultant microwave beam was found to be well focused with a spot size of approximately 8 cm. The beam can be steered poloidially from the center to the outer edge of the plasma. The initial operation of the Gycom gyrotron with about 0.5 MW delivered to a low density plasma for 0.5 s showed good central electron heating, with peak temperature in excess of 10 keV. A third gyrotron being built by CPI will be installed later this year. Progress with the first CPI tube will also be discussed and future plans for the ECH installation and physics experiments will be presented
Keywords :
fusion reactor design; fusion reactor ignition; gyrotrons; infrared imaging; plasma diagnostics; plasma filled waveguides; plasma radiofrequency heating; plasma temperature; plasma toroidal confinement; 0.2 MW; 0.5 MW; 1 MW; 110 GHz; Al2O3; BN; DIII-D tokamak; ECH system; HE11 mode; IR camera; beam steering; central electron heating; circular corrugated waveguide; double disc FC-75 cooled sapphire window; electron cyclotron resonance heating; fusion reactors; gyrotrons; low-loss-windowless evacuated transmission line; microwave beam; paper target; peak temperature; vacuum vessel; Boron; Electromagnetic heating; Gyrotrons; Plasma density; Plasma measurements; Plasma temperature; Power generation; Pulse measurements; Tokamaks; Vacuum breakdown;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
Type :
conf
DOI :
10.1109/FUSION.1997.687068
Filename :
687068
Link To Document :
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