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. BeaumontA. 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

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Abstract

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.
Original languageEnglish
Pages (from-to)2495 - 2539
Number of pages45
JournalNuclear Fusion
Volume39
Issue number12
DOIs
Publication statusPublished - Dec 1999
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Condensed Matter Physics

Cite this

Jacquinot, J., Putvinski, S., Bosia, G., Fukuyama, A., Hemsworth, R., Konovalov, S., Nevins, W. M., Perkins, F., Rasumova, K. A., Romanelli, F., Tobita, K., Ushigusa, K., Van Dam, J. W., Vdovin, V., Zweben, S., Makowski, M., Koch, R., Wégrowe, J-G., Alikaev, V. V., ... Righi, E. (1999). Plasma auxiliary heating and current drive. Nuclear Fusion, 39(12), 2495 - 2539. https://doi.org/10.1088/0029-5515/39/12/306