Current profile control and stability studies in the tokamak physics experiment (TPX)

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

OSTI ID:7260936

Porkolab, M; Bonoli, P T; Ramos, J J ^[1]; Fenstermacher, M E ^[2]

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1. Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States)
2. Lawrence Livermore Nat. Lab., Livermore, California 94550 (United States)

Using the ACCOME and PEST II codes, noninductive current drive scenarios and their stability are studied in the proposed TPX experiment. The current drive techniques include neutral beams as well as lower hybrid and fast magnetosonic waves. The non-standard cases studied include inverted [ital q]([ital r]) profiles (reversed-shear scenario), reversed edge current profiles, and second-stable scenarios [[ital q](0)[gt]2]. The MHD stability of some of these scenarios has been assessed. The power requirements for TPX are established.

• DOE Contract Number: AC02-78ET51013; W-7405-ENG-48
• OSTI ID: 7260936
• 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
TOKAMAK DEVICES
BEAM PROFILES
STABILITY
BETA RATIO
BOOTSTRAP CURRENT
COMPUTER CODES
FAST MAGNETOACOUSTIC WAVES
ION CYCLOTRON-RESONANCE
LOWER HYBRID CURRENT DRIVE
PLASMA HEATING
CLOSED PLASMA DEVICES
CURRENTS
CYCLOTRON RESONANCE
ELECTRIC CURRENTS
HEATING
HYDROMAGNETIC WAVES
MAGNETOACOUSTIC WAVES
NON-INDUCTIVE CURRENT DRIVE
RESONANCE
THERMONUCLEAR DEVICES
700350* - Plasma Production
Heating
Current Drive
& Interactions- (1992-)
700340 - Plasma Waves
Oscillations
& Instabilities- (1992-)