60 MHz fast wave current drive experiments for DIII-D

Conference · Mon May 01 00:00:00 EDT 1989

DOI:https://doi.org/10.1063/1.38507· OSTI ID:6386910

Mayberry, M. J.; Chiu, S. C.; Porkolab, M.; Chan, V.; Freeman, R.; Harvey, R.; Pinsker, R.

Non-inductive current drive is an essential element of the ITER program because it enhances high fluence nuclear testing during the technology phase of operations. By using fast waves in the ion cyclotron range of frequencies (ICRF), current drive efficiencies comparable to lower-hybrid current drive can be obtained with good penetration of wave power to the high temperature plasma core. An additional advantage of the low frequency scheme is its technological simplicity due to the present availability of efficient, multi-megawatt rf sources in the ICRF. The DIII-D facility provides an excellent opportunity to test the feasibility of the low frequency FWCD approach. By combining with high power (2 MW) ECH injection at 60 GHz, it should be possible to generate plasmas with central electron temperatures of T/sub e0/ approx. = 4 keV, and by operating at a reduced toroidal field (B = 1T) to increase the electron ..beta.., strong single-pass absorption (/eta//sub abs/ greater than or equal to 0.3) can be achieved. The availability of a wide port recess (1m toroidal by 0.5m poloidal) will enable a travelling wave spectrum to be launched with N/sub parallel/ approx. = 5--7 at 60 MHz, which should be optimum for strong electron interaction. The resulting current drive efficiency should be sufficiently high to demonstrate FWCD at the /approximately/ 0.25--0.5 MA level at moderate densities (/bar n/ approx. = 1.3 /times/ 10/sup 19/ m/sup /minus/3/) using the existing 2 MW ICRF transmitter. 7 refs., 5 figs.

• Research Organization: General Atomics, San Diego, CA (USA)
• DOE Contract Number: AC03-89ER51114
• OSTI ID: 6386910
• Report Number(s): GA-A-19663; CONF-8905120-11; ON: DE89013307
• Resource Relation: Journal Volume: 190; Conference: 8. topical conference on radio frequency power in plasmas, Irvine, CA, USA, 1 May 1989; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DOUBLET REACTORS
CURRENT-DRIVE HEATING
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ELECTRON TEMPERATURE
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LANDAU DAMPING
NON-INDUCTIVE CURRENT DRIVE
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ELECTRIC HEATING
HEATING
HIGH-FREQUENCY HEATING
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THERMONUCLEAR REACTORS
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700101* - Fusion Energy- Plasma Research- Confinement
Heating
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