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Plasma auxiliary heating and current drive

  • J. Jacquinot
  • , S. Putvinski
  • , G. Bosia
  • , A. Fukuyama
  • , R. Hemsworth
  • , S. Konovalov
  • , W. M. Nevins
  • , F. Perkins
  • , K. A. Rasumova
  • , F. Romanelli
  • , K. Tobita
  • , K. Ushigusa
  • , J. W. Van Dam
  • , V. Vdovin
  • , S. Zweben
  • , M. Makowski
  • , R. Koch
  • , J. G. Wégrowe
  • , V. V. Alikaev
  • , B. Beaumont
  • A. Bécoulet, S. Bernabei, V. P. Bhatnagar, S. Brémond, M. D. Carter, C. D. Challis, A. Côté, D. A. D'Ippolito, F. Engelmann, L. G. Eriksson, N. Fujisawa, G. Giruzzi, C. Gormezano, R. Harvey, J. Heikkinen, T. Hellsten, Y. Ikeda, T. T.C. Jones, H. Kimura, B. Lloyd, T. Luce, D. Moreau, O. Naito, F. Nguyen, J. M. Noterdaeme, W. Ott, C. C. Petty, A. Polevoi, R. Prater, J. Rogers, F. Santini, F. X. Söldner, D. Stork, E. Thompson, G. Tonon, A. Tuccillo, E. Westerhof, H. Zohm, F. W. Perkins, D. E. Post, N. A. Uckan, M. Azumi, D. J. Campbell, N. Ivanov, N. Sauthoff, M. Wakatani, E. Righi
  • ITER EDA
  • Okayama U.
  • Commissariat à l'Énergie Atomique (CEA)
  • Lawrence Livermore National Laboratory
  • ENEA Centro Ricerche Frascati
  • Japan Atomic Energy Agency
  • Univ. Texas
  • Princeton Plasma Physics Laboratory
  • Centre Canadien de Fusion Magnetique
  • Lodestar Corp.-Boulder
  • NET
  • CompX
  • VTT Technical Research Centre of Finland
  • EURATOM-UKAEA Association Culham Science Centre
  • FOM-Instituut voor Plasmafysica 'Rijnhuizen'
  • Kyoto University

Résultats de recherche: Contribution à un journalArticleRevue par des pairs

178 Citations (Scopus)

Résumé

Heating and current drive systems must fulfil several roles in ITER operating scenarios: heating through the H-mode transition and to ignition; plasma burn control; current drive and current profile control in steady state scenarios; and control of MHD instabilities. They must also perform ancillary functions, such as assisting plasma start-up and wall conditioning. It is recognized that no one system can satisfy all of these requirements with the degree of flexibility that ITER will require. Four heating and current drive systems are therefore under consideration for ITER: electron cyclotron waves at a principal frequency of 170 GHz; fast waves operating in the range 40-70 MHz (ion cyclotron waves); lower hybrid waves at 5 GHz; and neutral beam injection using negative ion beam technology for operation at 1 MeV energy. It is likely that several of these systems will be employed in parallel. The systems have been chosen on the basis of the maturity of physics understanding and operating experience in current experiments and on the feasibility of applying the relevant technology to ITER. Here, the fundamental physics describing the interaction of these heating systems with the plasma is reviewed, the relevant experimental results in the exploitation of the heating and current drive capabilities of each system are discussed, key aspects of their application to ITER are outlined, and the major technological developments required in each area are summarized.

langue originaleAnglais
Pages (de - à)2495-2539
Nombre de pages45
journalNuclear Fusion
Volume39
Numéro de publication12
Les DOIs
étatPublié - déc. 1999

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