Controlling the boundary layer in fusion-grade, high-performance, plasma discharges is
essential for the successful development of toroidal magnetic confinement power generating …

Tokamaks have demonstrated excellent plasma confinement capability because of their
symmetry but has an intrinsic drawback because of their pulsed inductive operation. Efforts …

First experiments with nonaxisymmetric magnetic perturbations, toroidal mode number n= 2,
produced by newly installed in-vessel saddle coils in the ASDEX Upgrade tokamak show …

A critical issue for fusion-plasma research is the erosion of the first wall of the experimental
device due to impulsive heating from repetitive edge magneto-hydrodynamic instabilities …

Large Type-I edge localized modes (ELMs) are completely eliminated with small n= 3
resonant magnetic perturbations (RMP) in low average triangularity,, plasmas and in ITER …

Operating ITER in the reference inductive scenario at the design values of I p= 15 MA and Q
DT= 10 requires the achievement of good H-mode confinement that relies on the presence …

An overview of the H-mode threshold power in ASDEX Upgrade which addresses the impact
of the tungsten versus graphite wall, the dependences upon plasma current and density, as …

Component development for operation in a large-scale fusion device requires thorough
testing and qualification for the intended operational conditions. In particular environments …

The zero-frequency linear plasma response to static applied non-axisymmetric fields is
calculated using a resistive two-fluid model in diverted, toroidal geometry. Within this model …

The observation in JET of co-deposition of tritium with carbon has led to a broad discussion
on the replacement of graphite by a high-Z material for the first wall coverage. Moreover, due …