Published 1994 | Version v1
Report Open

Predictions of fast wave heating, current drive, and current drive antenna arrays for advanced tokamaks

Description

The objective of the advanced tokamak program is to optimize plasma performance leading to a compact tokamak reactor through active, steady state control of the current profile using non-inductive current drive and profile control. To achieve these objectives requires compatibility and flexibility in the use of available heating and current drive systems--ion cyclotron radio frequency (ICRF), neutral beams, and lower hybrid. For any advanced tokamak, the following are important challenges to effective use of fast waves in various roles of direct electron heating, minority ion heating, and current drive: (1) to employ the heating and current drive systems to give self-consistent pressure and current profiles leading to the desired advanced tokamak operating modes; (2) to minimize absorption of the fast waves by parasitic resonances, which limit current drive; (3) to optimize and control the spectrum of fast waves launched by the antenna array for the required mix of simultaneous heating and current drive. The authors have addressed these issues using theoretical and computational tools developed at a number of institutions by benchmarking the computations against available experimental data and applying them to the specific case of TPX

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE96005434; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
CONF-940933--48

Conference

Title
15. international conference on plasma physics and controlled nuclear fusion research.
Dates
26 Sep - 1 Oct 1994.
Place
Madrid (Spain).

INIS

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400
Funding organization
USDOE, Washington, DC (United States).