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Abstract. Research in the National Spherical Torus Experiment, NSTX, has
been conducted to establish spherical torus plasmas to be used for
high- , auxiliary heated experiments. The device has a major radius
R0 = 0.86 m, a midplane half-width of 0.7 m, and has been operated with
toroidal magnetic field
B0
0.3 T and
Ip
1.0 MA. The
evolution of the plasma equilibrium is analyzed between shots with an
automated version of the EFIT code. Limiter, double-null, and lower
single-null diverted configurations have been sustained for several energy
confinement times. Plasma stored energy has reached 92 kJ (
= 17.8%) with neutral beam heating. Plasma elongation of
1.6
2.0 and triangularity in the range
0.25
0.45 have
been sustained, with values of
= 2.5 and
= 0.6 being
reached transiently. The reconstructed magnetic signals are fit to the
corresponding measured values with low error. Aspects of the plasma
boundary, pressure, and safety factor profiles are supported by measurements
from non-magnetic diagnostics. Plasma densities have reached 0.8 and 1.2
times the Greenwald limit in deuterium and helium plasmas, respectively,
with no clear limit encountered. Instabilities including sawteeth and
reconnection events (REs), characterized by Mirnov oscillations, and
perturbation of the Ip,
, and li evolution, have been
observed. A low q limit was observed and is imposed by a low toroidal mode
number kink instability.
IAEA 2001