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Plasma-wall interaction and plasma performance in textor - A review

  • Team TEXTOR Team
  • , H. L. Bay
  • , G. Bertschinger
  • , W. Bieger
  • , P. Bogen
  • , G. A. Campbell
  • , Y. Chad
  • , H. A. Claassen
  • , R. W. Conn
  • , H. G. Esser
  • , K. H. Finken
  • , G. Fuchs
  • , H. Gerhauser
  • , B. Giesen
  • , D. M. Goebel
  • , R. Graffmann
  • , H. Hartwig
  • , E. Hintz
  • , F. Hoenen
  • , K. Höthker
  • A. Kaleck, H. Kever, L. Könen, W. K. Leung, L. Li, Y. T. Lie, A. E. Pontau, A. Pospieszczyk, D. Reiter, A. Rogister, G. Ross, D. Rusbüldt, U. Samm, B. Schweer, J. Schluter, H. Soltwisch, W. Stodiek, G. Thomas, F. Waelbroeck, G. Waidmann, P. Wienhold, J. Winter, G. H. Wolf, R. Yamauchi, T. Delvigne, P. Descamps, F. Durodié, M. Jadoul, R. Koch, D. Lebeau, A. M. Messiaen, D. I.C. Pearson, P. E. Vandenplas, R. Van Nieuwenhove, G. Van Oost, G. Van Wassenhove, R. R. Weynants
  • FORSCHUNGSZENTRUM JULICH GMBH
  • Royal Military Academy

Publikation: Beitrag in FachzeitschriftArtikelBegutachtung

34 Zitate (Scopus)

Abstract

TEXTOR, a tokamak primarily devoted to plasma-wall interaction studies, has been operated during the last 2-3 years under a wide variety of discharge conditions. Discharges with Ohmic heating only and with additional ICR heating in the MW-range were produced over an extended range of plasma parameters. Different limiter materials were used - Inconel, stainless steel, graphite, TiC coated graphite. The surface of the first wall (liner) consisted either of Inconel or of a carbon layer deposited upon the Inconel. Characteristic features of the discharge have been modified by making use of the modular pump limiter ALT-I and by applying a localized perturbation coil for "ergodization" of the magnetic field structure in the boundary. The characteristics of plasma-wall interaction under these conditions and their influence on the global performance of the TEXTOR plasma are described and discussed. Use has been made of novel diagnostics specifically developed for edge plasma investigation.

OriginalspracheEnglisch
Seiten (von - bis)3-14
Seitenumfang12
FachzeitschriftJournal of Nuclear Materials
Jahrgang145-147
AusgabenummerC
DOIs
PublikationsstatusVeröffentlicht - 2 Feb. 1987

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