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Title: ICRF heating in Alcator C-Mod: Present status and future prospects

Abstract

Alcator C-Mod, the high field, high density, diverted, compact tokamak in the world's portfolio of high performance plasma fusion devices, is heated exclusively with ICRF auxiliary power. In this paper an overview of recent results is summarized, with particular attention given to the importance of RF operation and the flexibility afforded by different heating scenarios. Besides the routine minority heating operation, results in the mode conversion heating regime are also presented (mainly direct electron heating through mode converted ion Bernstein waves). Recent attempts at improving plasma performance by establishing internal transport barriers (ITBs) by various transient profile control techniques (the so-called Advanced Tokamak mode of operation) are also presented. Future improvements in performance afforded by the recent addition of a new 4-strap antenna and 4 MW of tunable (40-80 MHz) ICRF power are also discussed. Mode-conversion current drive (MCCD) and fast wave current drive (FWCD) will be among the many new options that will be tested with the goal of improving plasma performance. (c) 1999 American Institute of Physics.

Authors:
 [1];  [1];  [1];  [2];  [1];  [1];  [1];  [1];  [1];  [3]
  1. MIT Plasma Science and Fusion Center, Cambridge, Massachusetts 02139 (United States)
  2. Princeton Plasma Physics Laboratory, Princeton, New Jersey, 08543 (United States)
  3. Princeton Plasma Physics Laboratory, Princeton, New Jersey, 08543 (United States) (and others)
Publication Date:
OSTI Identifier:
20216680
Resource Type:
Journal Article
Journal Name:
AIP Conference Proceedings
Additional Journal Information:
Journal Volume: 485; Journal Issue: 1; Other Information: PBD: 20 Sep 1999; Journal ID: ISSN 0094-243X
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ICR HEATING; TOKAMAK TYPE REACTORS; POWER RANGE 01-10 MW; CURRENT-DRIVE HEATING; BERNSTEIN MODE; ROTATING PLASMA; EXPERIMENTAL DATA

Citation Formats

Porkolab, M., Fiore, C., Greenwald, M., Hosea, J. C., Hubbard, A., Hutchinson, I., Irby, J., Nelson-Melby, E., Marmar, E., and Phillips, C. K. ICRF heating in Alcator C-Mod: Present status and future prospects. United States: N. p., 1999. Web. doi:10.1063/1.59716.
Porkolab, M., Fiore, C., Greenwald, M., Hosea, J. C., Hubbard, A., Hutchinson, I., Irby, J., Nelson-Melby, E., Marmar, E., & Phillips, C. K. ICRF heating in Alcator C-Mod: Present status and future prospects. United States. doi:10.1063/1.59716.
Porkolab, M., Fiore, C., Greenwald, M., Hosea, J. C., Hubbard, A., Hutchinson, I., Irby, J., Nelson-Melby, E., Marmar, E., and Phillips, C. K. Mon . "ICRF heating in Alcator C-Mod: Present status and future prospects". United States. doi:10.1063/1.59716.
@article{osti_20216680,
title = {ICRF heating in Alcator C-Mod: Present status and future prospects},
author = {Porkolab, M. and Fiore, C. and Greenwald, M. and Hosea, J. C. and Hubbard, A. and Hutchinson, I. and Irby, J. and Nelson-Melby, E. and Marmar, E. and Phillips, C. K.},
abstractNote = {Alcator C-Mod, the high field, high density, diverted, compact tokamak in the world's portfolio of high performance plasma fusion devices, is heated exclusively with ICRF auxiliary power. In this paper an overview of recent results is summarized, with particular attention given to the importance of RF operation and the flexibility afforded by different heating scenarios. Besides the routine minority heating operation, results in the mode conversion heating regime are also presented (mainly direct electron heating through mode converted ion Bernstein waves). Recent attempts at improving plasma performance by establishing internal transport barriers (ITBs) by various transient profile control techniques (the so-called Advanced Tokamak mode of operation) are also presented. Future improvements in performance afforded by the recent addition of a new 4-strap antenna and 4 MW of tunable (40-80 MHz) ICRF power are also discussed. Mode-conversion current drive (MCCD) and fast wave current drive (FWCD) will be among the many new options that will be tested with the goal of improving plasma performance. (c) 1999 American Institute of Physics.},
doi = {10.1063/1.59716},
journal = {AIP Conference Proceedings},
issn = {0094-243X},
number = 1,
volume = 485,
place = {United States},
year = {1999},
month = {9}
}