DocumentCode :
3128374
Title :
CW, high power, gyrotron development at 110 GHz for ECH applications
Author :
Chu, T.S. ; Borchard, P. ; Felch, K. ; Jory, H. ; Loring, C.M.
Author_Institution :
Communications & Power Ind., Palo Alto, CA, USA
fYear :
1996
fDate :
3-5 June 1996
Firstpage :
303
Abstract :
Summary form only given. Electron cyclotron heating (ECH) is the most promising plasma heating method to achieve fusion. High-power, long-pulse or CW gyrotrons are required in many present and Future ECH experiments. For example, the planned experiment at DIII-D, the experimental tokamak at General Atomics, will require 4 MW of RF power at 110 GHz for a pulse duration of 10 seconds. The RF requirement for the planned International Thermonuclear Experimental Reactor (ITER) is 50 MW at 170 GHz and CW operation [1]. To achieve the goal of 1 MW, CW operation, we have designed and begun fabrication of a new tube that has improved cooling to all tube parts which showed signs of overheating during the last experiment. In addition, we are looking at the possibility of using alternate output window designs to increase power handling capability. We will summarize the design of the new tube and present initial test data.
Keywords :
Tokamak devices; fusion reactor design; fusion reactors; gyrotrons; plasma radiofrequency heating; 1 MW; 10 s; 100 to 150 kW; 110 GHz; 4 MW; 50 MW; CW high power gyrotron; DIII-D; ECH applications; ITER; International Thermonuclear Experimental Reactor; RF requirement; cooling; electron cyclotron heating; fusion; plasma heating method; power handling; Cooling; Cyclotrons; Electrons; Fabrication; Gyrotrons; Heating; Inductors; Plasmas; Radio frequency; Tokamaks;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Plasma Science, 1996. IEEE Conference Record - Abstracts., 1996 IEEE International Conference on
Conference_Location :
Boston, MA, USA
ISSN :
0730-9244
Print_ISBN :
0-7803-3322-5
Type :
conf
DOI :
10.1109/PLASMA.1996.551678
Filename :
551678
Link To Document :
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