ICRF coil for the IDEAL plasma

Conference · Sat Oct 15 00:00:00 EDT 1994 · AIP Conference Proceedings (American Institute of Physics); (United States)

OSTI ID:6929562

Motley, R W; Majeski, R; Cohen, S A; Diesso, M; Wilson, J R ^[1]

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1. Princeton University, Princeton, New Jersey 08544 (United States)

We describe an ICRH coil to drive the plasma in the proposed IDEAL device, a linear plasma machine designed to study the physics and engineering problems of the ITER divertor. In initial operation, 2 MW of CW power at [similar to]40 MHz will be applied to a hydrogen plasma via four 0.75-m long multiple saddle coils that excite ICRF slow waves. The waves propagate to a 30 % magnetic beach, where they undergo cyclotron absorption. At full heating power the power flow out the ends of IDEAL is designed to equal that in the ITER divertor. Coil loading and the radial distribution of the E[sup +] and E[sup [minus]] RF fields have been calculated with the ANTENA Code.

• OSTI ID: 6929562
• Report Number(s): CONF-9304112-; CODEN: APCPCS
• Journal Information: AIP Conference Proceedings (American Institute of Physics); (United States), Vol. 289:1; Conference: 10. topical conference on radio frequency power in plasmas, Boston, MA (United States), 1-3 Apr 1993; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ICR HEATING
MAGNET COILS
MAGNETOACOUSTIC WAVES
ANTENNAS
COMPUTER CODES
DIVERTORS
ELECTRIC FIELDS
FREQUENCY DEPENDENCE
ITER TOKAMAK
PLASMA
CLOSED PLASMA DEVICES
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
HEATING
HIGH-FREQUENCY HEATING
HYDROMAGNETIC WAVES
PLASMA HEATING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700350* - Plasma Production
Heating
Current Drive
& Interactions- (1992-)