With increasing size of a tokamak device and associated fusion power gain an increasing
power flux density towards the divertor needs to be handled. A solution for handling this …

In a wide variety of natural and laboratory magnetized plasmas, filaments appear as a result
of interchange instability. These convective structures substantially enhance transport in the …

Robust power exhaust schemes employing impurity seeding are needed for target
operational scenarios in present day tokamak devices with metallic plasma-facing …

New data from Alcator C-Mod have extended the range of heat flux measurements and
scalings to poloidal magnetic fields above ITER-level. Knowledge of how the scrape-off …

The high confinement mode (H-mode) is the operational scenario foreseen for ITER, DEMO
and future fusion power plants. At high densities, which are favorable in order to maximize …

Using recently installed scrape-off layer diagnostics on the tokamak à configuration variable,
we characterise the poloidal and parallel properties of turbulent filaments. We access both …

A summary of recent results on filamentary transport, mostly obtained with the ASDEX-
Upgrade tokamak (AUG), is presented and discussed in an attempt to produce a coherent …

The low temperature boundary layer plasma (scrape-off layer or SOL) between the hot core
and the surrounding vessel determines the level of power loading, erosion and implantation …

The transport of particles and energy into the scrape-off layer (SOL) region at the outboard
midplane of medium-sized tokamaks, operating in low confinement mode, is investigated by …

A set of high density, highly shaped H-mode discharges has been performed in the TCV
tokamak with the aim of assessing the effects of increasing divertor neutral recycling on the …