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Optimization of DIII-D advanced tokamak discharges with respect to the β limit

  • J. R. Ferron
  • , T. A. Casper
  • , E. J. Doyle
  • , A. M. Garofalo
  • , P. Gohil
  • , C. M. Greenfield
  • , A. W. Hyatt
  • , R. J. Jayakumar
  • , C. Kessel
  • , J. Y. Kim
  • , T. C. Luce
  • , M. A. Makowski
  • , J. Menard
  • , M. Murakami
  • , C. C. Petty
  • , P. A. Politzer
  • , T. S. Taylor
  • , M. R. Wade

Research output: Contribution to journalArticlepeer-review

67 Scopus citations

Abstract

Results are presented from comparisons of modeling and experiment in studies to assess the best choices of safety factor q profile, pressure profile, and discharge shape for high Β, steady-state, noninductive advanced tokamak operation in the DIII-D device [J. L. Luxon, Nucl. Fusion 42, 614 (2002)]. These studies are motivated by the need for high qmin ΒN to maximize the self-driven bootstrap current while maintaining high toroidal Β to increase fusion gain. Modeling shows that increases in the normalized beta ΒN stable to ideal, low toroidal mode number (n=1,2), instabilities can be obtained through broadening of the pressure profile and use of a symmetric double-null divertor shape. Experimental results are in agreement with this prediction. The general trend is for qmin ΒN to increase with the minimum q value (qmin) although ΒN decreases as qmin increases. By broadening the pressure profile, ΒN ≈4 is obtained with qmin ≈2. Modeling of equilibria with near 100% bootstrap current indicates that operation with ΒN ≈5 should be possible with a sufficiently broad pressure profile.

Original languageEnglish
Article number056126
Pages (from-to)1-10
Number of pages10
JournalPhysics of Plasmas
Volume12
Issue number5
DOIs
StatePublished - May 2005

Funding

This work was supported by the U.S. Department of Energy under Grant Nos. DE-FC02-04ER54698, W-7405-ENG-48, DE-FG03-01ER54615, DE-FG02-89ER53297, DE-AC02-76CH03073, and DE-AC05-00OR22725.

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