P. T. Bonoli, M. Porkolab, J. Ramos,
Y. Takase1, 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. Rowan2, J. A. Snipes, J. Terry,
J. Weaver3, 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
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
= 2(p)/B20 is the volume averaged toroidal plasma beta. Current profile
control at the -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.
IAEA 2001