A computational method is presented to determine the tokamak actuator time evolution
(trajectories) required to optimally reach a given point in the tokamak operating space while …

In tokamak fusion plasmas, control of the spatial distribution profile of the toroidal plasma
current plays an important role in realizing certain advanced operating scenarios. These …

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 …

In this work, model-predictive control (MPC) was combined for the first time with singular
perturbation theory, and an original plasma kinetic control method based on extremely …

The present work demonstrates the capabilities of the transport code RAPTOR as a fast and
reliable simulator of plasma profiles for the entire plasma discharge, ie from ramp-up to ramp …

The first real-time profile control experiments integrating magnetic and kinetic variables were
performed on DIII-D in view of regulating and extrapolating advanced tokamak scenarios to …

A general infrastructure for tokamak controllers based on data-driven neural net models is
presented. The paradigm allows for more flexible choices of both the underlying model and …

A real-time model-based controller is developed for the tracking of the distributed safety-
factor profile in a tokamak plasma. Using relevant physical models and simplifying …

In order for ITER to be capable of operating in advanced tokamak operating regimes,
characterized by a high fusion gain, good plasma confinement, magnetohydrodynamic …