Magnetic-fusion plasmas are complex self-organized systems with an extremely wide range
of spatial and temporal scales, from the electron-orbit scales (∼ 10− 11 s,∼ 10− 5 m) to the …

A new paradigm is presented to reconstruct the plasma current density profile in a tokamak
in real-time. The traditional method of basing the reconstruction on real-time diagnostics …

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 …

A new model of heating, current drive, torque and other effects of neutral beam injection on
NSTX-U that uses neural networks has been developed. The model has been trained and …

ITER plasma control design solutions and performance requirements are strongly driven by
its nuclear mission, aggressive commissioning constraints, and limited number of …

The RAPTOR code is a control-oriented core plasma profile simulator with various
applications in control design and verification, discharge optimization and real-time plasma …

A controller is designed for the tokamak safety factor profile that takes real-time-varying
operational and physics limits into account. This so-called model predictive controller (MPC) …

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 …

In a magnetic fusion reactor, the achievement of a certain type of plasma current profiles,
which are compatible with magnetohydrodynamic stability at high plasma pressure, is key to …

We present a framework to solve a finite-time optimal control problem for parabolic partial
differential equations (PDEs) with diffusivity-interior actuators, which is motivated by the …