ICRF heating and wave generation in the ATC tokamak
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ICRF heating and wave generation in the ATC tokamak

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Published by Dept. of Energy, Plasma Physics Laboratory, for sale by the National Technical Information Service] in Princeton, N. J, [Springfield, Va .
Written in English

Subjects:

  • Cyclotron waves,
  • Tokamaks

Book details:

Edition Notes

Statementby H. Takahashi, Plasma Physics Laboratory, Princeton University
SeriesPPPL ; 1545
ContributionsUnited States. Dept. of Energy, Princeton University. Plasma Physics Laboratory
The Physical Object
Paginationv. :
ID Numbers
Open LibraryOL14882531M

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ICRF heating experiments have been carried out in the Alcator C‐Mod tokamak at power levels up to MW. Features of Alcator C‐Mod include high density operation, molybdenum plasma facing components, and a closed divertor configuration. The heating is accomplished with two two‐strap antennas each run with dipole phasing at 80 MHz in deuterium plasmas with a hydrogen minority resonant at Cited by: 5. The ion cyclotron range of frequency (ICRF) waves have been used in a tokamak as a main heating tool 1 or a control tool of MHD phenomena 2 (e.g., sawtooth) and turbulent transport. 3, 4 In many. Integrated Full-Wave Modeling of ICRF Heating in Tokamak Plasmas A. Fukuyama, S. Murakami, T. Yamamoto, H. Nuga Department of Nuclear Engineering, Kyoto University, Kyoto , Japan 1. Introduction 2. Integrated tokamak modeling code: TASk 3. Modification of velocity distribution function 4. Integral formulation of full wave analysis 5.   ICRF COUPLING AND HEATING STUDIES FOR LARGE TOKAMAKS H. Romero, R. Sund, and J. Scharer* Electrical and Computer Engineering Departments The University of Wisconsin -- Madison, Wisconsin , USA Abstract ICRF coupling, wave propagation and heating studies are presented for large tokamaks.

Fast ion generation and bulk plasma heating with three-ion ICRF scenarios AIP Conf. Proc. , (); / Effect of ICRF waves on energetic ion dynamics in a tokamak plasma AIP Conf. Proc. , (); / Fast wave ICRF minority heating experiments on the Alcator C tokamak. The ICRF heating experiments on the Globus-M tokamak were started one year ago. Two possible scenarios of experiments have been considered for plasma heating [1, 2]. The best heating performance (a maximum electron temperature of keV with 5 MW of ICRF power) was obtained with a preferential wave launch in the direction of the plasma current. An experiment in a new regime of ion Bernstein wave (IBW) heating has been carried out using MHz high power transmitters in the JIPP T-IIU tokamak The heating regime utilized the IBW branch.

  Heating with ICRF waves is a well-established method on present-day tokamaks and one of the heating systems foreseen for ITER. However, further work is still needed to test and optimize its performance in fusion devices with metallic high-Z plasma facing components (PFCs) in preparation of ITER and DEMO operation. This is of particular importance for the bulk ion heating capabilities of ICRF. @article{osti_, title = {ICRF heating in tokamaks}, author = {Takahashi, H.}, abstractNote = {The current status of ICRF heating of Tokamak plasmas is described. Two aspects of the subject are discussed: the physics of wave damping and the evaluation of ion heating. Recent experiments in several Tokamak devices at the second harmonic of the deuteron cyclotron frequency have exhibited. The modeling code TASK was updated to describe the momentum distribution function of multi-species and the wave dielectric tensor for arbitrary momentum distribution function. Numerical results of ICRF heating in tokamak plasmas which generates energetic tail of distribution function are reported.   Kazakov Y O et al Plasma heating and generation of energetic ions with novel three-ion ICRF scenarios on Alcator C-Mod and JET tokamak facilities Invited Talk 58th APS-DPP Meeting (San Jose, CA,) NI