DISCHARGE CONTROL AND EVOLUTION IN TFTR.

D. Mueller, M. Bell, F. Boody, C. Bush, J. L. Cecchi, S. Davis, H. F. Dylla, P. C. Efthimion, R. J. Hawryluk, K. W. Hill, S. Kilpatrick, P. H. LaMarche, D. Manos, D. McCune, S. S. Medley

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The Tokamak Fusion Test Reactor (TFTR) was designed to explore plasma confinment and heating at reactor-like parameters. This paper describes the plasma control techniques employed on TFTR. The success in reaching the plasma current and toroidal field design parameters is encouraging. The techniques used for impurity control have permitted plasma with Z//e//f//f as low as 1. 4 to be produced. Fuelling by pellet injection has extended the density range. During the next run period, the expected parameter range will be substantially extended with the increase of beam power to 27MW and plasma current to 3. 0MA.

Original languageEnglish (US)
Title of host publicationEttore Majorana International Science Series
Subtitle of host publicationPhysical Sciences
PublisherPlenum Press
Pages143-157
Number of pages15
ISBN (Print)0306422360, 9780306422362
DOIs
StatePublished - 1986

Publication series

NameEttore Majorana International Science Series: Physical Sciences
Volume26
ISSN (Print)0270-188X

All Science Journal Classification (ASJC) codes

  • General Engineering

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