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(CT-7Rc) Maturing ECRF Technology for Plasma Control

R.W. Callis1), W.P. Cary1), S. Chu2), J.L. Doane1), R.A. Ellis3), K. Felch3), Y.A. Gorelov1), H.J. Grunloh1), J. Hosea, J. Lohr1), J.J. Peavy1), R.I. Pinsker1), D. Ponce1), R. Prater1), M. Shapiro4), R.J. Temkin4), J.F. Tooker1)
1) General Atomics, San Diego, USA
2) Communications and Power Industries, Palo Alto, California, USA
3) Princeton Plasma Physics Laboratory, Princeton, New Jersey, USA
4) Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts, USA

Abstract.  The availability of high power, long-pulse, gyrotrons has opened the opportunity for enhanced scientific results on magnetic confinement devices for fusion research worldwide. This has led to successful experiments on ECH, ECCD, non-inductive tokamak operation, energy transport measurements, and suppression of instabilities leading to enhanced performance. In addition, ancillary equipment for efficient microwave transmission over distances of hundreds of meters, polarization control, diagnostics and flexible launch geometry have all been developed. The 110 GHz (ECH) system installed on the DIII–D tokamak now comprises six gyrotrons. Three Gycom gyrotrons nominally produce 750 kW for 2 s pulses The other three gyrotrons, built by CPI, have a nominal output power of 1 MW for 10 s pulses. The CPI gyrotrons utilize a single disc CVD diamond window that employs edge water cooling. Calculation predict that the CVD diamond window should be capable of full 1 MW cw operation, which is supported by IR camera measurements, that show the window reaching equilibrium after 2.5 s. *Work supported by U.S. DOE Contracts DE-AC03-99ER54463, DE-AC02-76CH03073, DE-FC02-93ER54186.

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IAEA 2003