Exploration of the Equilibrium Operating Space For NSTX-Upgrade
Authors: S.P. Gerhardt, R. Andre and J.E. Menard
Abstract:
This paper explores a range of high-performance equilibrium scenarios available in the NSTX-Upgrade
device [J.E. Menard, submitted for publication to Nuclear Fusion]. NSTX-Upgrade is a
substantial upgrade to the existing NSTX device [M. Ono, et al., Nuclear Fusion 40, 557 (2000)],
with significantly higher toroidal field and solenoid capabilities, and three additional neutral
beam sources with significantly larger current drive efficiency. Equilibria are computed with freeboundary
TRANSP, allowing a self consistent calculation of the non-inductive current drive
sources, the plasma equilibrium, and poloidal field coil current, using the realistic device
geometry. The thermal profiles are taken from a variety of existing NSTX discharges, and
different assumptions for the thermal confinement scalings are utilized. The no-wall and idealwall
n=1 stability limits are computed with the DCON code. The central and minimum safety
factors are quite sensitive to many parameters: they generally increases with large outer plasmawall
gaps and higher density, but can have either trend with the confinement enhancement factor.
In scenarios with strong central beam current drive, the inclusion of non-classical fast ion
diffusion raises qmin, decreases the pressure peaking, and generally improves the global stability,
at the expense of a reduction in the non-inductive current drive fraction; cases with less beam
current drive are largely insensitive to additional fast ion diffusion. The non-inductive current
level is quite sensitive to the underlying confinement and profile assumptions. For instance, for
BT=1.0 T and Pinj=12.6 MW, the non-inductive current level varies from 875 kA with ITER-98y,2
thermal confinement scaling and narrow thermal profiles to 1325 kA for an ST specific scaling
expression and broad profiles. This sensitivity should facilitate the determination of the correct
scaling of transport with current and field to use for future fully non-inductive ST devices.
Scenarios are presented which can be sustained for 8-10 seconds, or (20-30)τCR, at βN=3.8-4.5,
facilitating, for instance, the study of disruption avoidance for very long pulse. Scenarios have
been documented which can operate with βT~25% and equilibrated qmin>1. The value of qmin can
be controlled at either fixed non-inductive fraction of 100% or fixed plasma current, by varying
which beam sources are used, opening the possibility for feedback qmin control. In terms of
quantities like collisionality, neutron emission, non-inductive fraction, or stored energy, these
scenarios represent a significant performance extension compared to NSTX and other present
spherical torii.
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2012 Nucl. Fusion 52 083020 doi:10.1088/0029-5515/52/8/083020
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Download PPPL-4757 (pdf 22 MB 70 pp)
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