Contents Return Previous Page Next Page Index


Return To: Session CDP - Plasma Heating and Current Drive
Prev Page: (CDP/13) Mode-Converted Electron Bernstein Waves for Heating and
Next Page: (CDP/15) Quasi-steady State High Confinement at High Density

(CDP/14) Modelling of Advanced Tokamak Physics Scenarios in ALCATOR C-Mod

   
P. T. Bonoli , M. Porkolab , J. Ramos , Y. Takase 1, S. Wukitch , R. L. Boivin , C. Fiore , J. Goetz , R. Granetz , M. Greenwald , A. Hubbard , I. Hutchinson , J. Irby , B. LaBombard , B. Lipschultz , E. Marmar , A. Mazurenko , D. Mossessian , E. Nelson-Melby , C. S. Pitcher , J. Reardon , J. Rice , W. Rowan 2, J. A. Snipes , J. Terry , J. Weaver 3, S. Wolfe 
 
Plasma Science and Fusion Center, MIT, Cambridge, MA 02139 USA
1 Tokyo University, Tokyo, Japan
2 University of Texas, Austin, TX USA
3 University of Maryland, College Park, MD USA

Abstract
Advanced tokamak modes of operation in Alcator C-Mod  have been investigated using a simulation model which combines an MHD equilibrium and current profile control  calculation with an ideal MHD stability  analysis. Stable access to high $\rm\beta_t$ operating modes with reversed shear  current density profiles has been demonstrated using 2.4-3.0 MW of off-axis lower hybrid current drive  (LHCD). Here $\beta_{\rm t} =
2\mu_0(p)/B^2_0$ is the volume averaged toroidal plasma beta. Current profile control at the $\beta $-limit and beyond has also been demonstrated. The effects of LH power level as well as changes in the profiles of density and temperature on shear reversal radius have been quantified and are discussed.

 

Read the full paper in PDF format.


IAEA 1999