On the eve of component procurement, this paper discusses the present physics basis for
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …

Divertor heat flux data from infra red (IR) from various tokamaks in H-Mode regime show that
the power width, $\lambda_ {q} $, scales approximately like 1.6 (R/a) ρ s, pol. However, the …

The design of future fusion reactors and their operational scenarios requires an accurate
prediction of the plasma confinement. We have developed a new model that integrates …

Abstract The EUROfusion JET-ILW pedestal database is described, with emphasis on three
main issues. First, the technical aspects are introduced, including a description of the data …

Integrated edge-localized-mode (ELM)-free or small ELM scenarios for the demonstration
fusion power plant (DEMO) are investigated in ASDEX Upgrade using argon seeding for …

Most of the detachment experiments done to date on the tokamak à configuration variable
(TCV), both in standard and alternative divertor geometries, focused on L-mode integrated …

Recent US fusion development strategy reports all recommend that the US should pursue
innovative science and technology to enable construction of a fusion pilot plant (FPP) that …

Abstract Changes in global and edge plasma parameters (H 98 (y, 2), dimensionless
collisionality ν*, core density peaking, separatrix density ne, sep) with variations in the D 2 …

Impurity seeding will be an important tool to reduce the peak power loads and temperatures
at the divertor targets in future tokamak devices. To improve the physics understanding and …

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 …