Abstract The Chinese Fusion Engineering Testing Reactor (CFETR), complementing the
ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to …

Diverted discharges at negative triangularity on the DIII-D tokamak sustain normalized
confinement and pressure levels typical of standard H-mode scenarios (H 98y2≃ 1, β N≃ 3) …

In this paper, a linear model for plasma current, position and shape control based on the
plasma rigid motion assumption is presented and implemented in an EAST tokamak …

Operating experimental devices have provided key inputs to the design process for ITER
axisymmetric control. In particular, experiments have quantified controllability and …

Negative triangularity (NT) is a potentially transformative configuration for tokamak-based
fusion energy with its high-performance core, edge localized mode (ELM)-free edge, and …

We report the first preemptive direct stabilization of $ m, n= 2, 1$ neoclassical tearing modes
(NTMs) in DIII-D low-torque ITER baseline scenario plasmas by electron cyclotron waves …

Real-time simultaneous control of several radially distributed magnetic and kinetic plasma
parameters is being investigated on JET, in view of developing integrated control of …

Abstract P-EFIT, a GPU parallel equilibrium reconstruction code, is based on the EFIT
framework, but built with the CUDA™(Compute Unified Device Architecture) to take …

A helical coil designed to passively generate non-axisymmetric fields during a plasma
disruption is shown (via electromagnetic analysis, linear MHD modeling, and relativistic drift …

Vertical control of DIII-D discharges with strong negative triangularity - IOPscience Skip to
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