The spherical tokamak (ST) is a leading candidate for a Fusion Nuclear Science Facility
(FNSF) due to its compact size and modular configuration. The National Spherical Torus …

A motional Stark effect diagnostic has been utilized to reconstruct the parallel current density
profile<? format?> in a spherical-torus plasma for the first time. The measured current profile …

This paper explores a range of high-performance equilibrium scenarios achievable with
neutral beam heating in the NSTX-Upgrade device (Menard JE 2012 Nucl. Fusion 52 …

This paper describes the prediction of disruptions based on diagnostic data in the high-β
spherical torus NSTX (Ono et al 2000 Nucl. Fusion 40 557). The disruptive threshold values …

Abstract The National Spherical Torus Experiment Upgrade (NSTX-U) will advance the
physics basis required for achieving steady-state, high-beta, and high-confinement …

Progress in the development of integrated advanced ST plasma scenarios in NSTX (Ono et
al 2000 Nucl. Fusion 40 557) is reported. Recent high-performance plasmas in NSTX …

Experiments conducted in high-performance 1.0 and 1.2 MA 6 MW NBI-heated H-mode
discharges with a high magnetic flux expansion radiative divertor in NSTX demonstrate that …

To achieve its performance goals, SPARC plans to operate in equilibrium configurations
with a strong elongation of κareal~ 1.75, which in turn will destabilize the n= 0 vertical …

This paper presents the first control algorithm for the inner-and outer-strike point position for
a Spherical Torus (ST) fusion experiment and the performance analysis of the controller. A …

Steady-state handling of divertor heat flux is a critical issue for both ITER and spherical torus-
based devices with compact high power density divertors. Significant reduction of heat flux …