![]() |
![]() |
![]() ![]() |
Abstract. The spherical tokamak (ST), because of its slender central
column, has very limited volt-second capability relative to a standard
aspect ratio tokamak of similar plasma cross-section. Recent experiments on
the National Spherical Torus Experiment (NSTX) have begun to quantify and
optimize the ohmic current drive efficiency in a MA-class ST device.
Sustainable ramp-rates in excess of 5MA/sec during the current rise phase
have been achieved on NSTX, while faster ramps generate significant MHD
activity. Discharges with IP exceeding 1MA have been achieved in NSTX
with nominal parameters: aspect ratio
A = 1.3 - 1.4, elongation
= 2 - 2.2, triangularity
= 0.4, internal inductance li = 0.6,
and Ejima coefficient
CE = 0.35. Flux consumption efficiency results,
performance improvements associated with first boronization, and comparisons
to neoclassical resistivity are described.
IAEA 2001