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 …

With ITER, the largest tokamak ever built, and the growing number of fusion energy startups
in the world, the need for numerical simulations has never been more crucial to progress …

The neoclassical confinement and the bootstrap current are analysed in the configuration
space of W7-X by self-consistent neoclassical transport simulations. Since the establishment …

To make predictions for and design fusion reactors, a multitude of physical processes must
be considered. In the edge and scrape-off layer (SOL), turbulent fluctuations intertwine with …

The island divertor concept is an innovative and promising idea to handle heat and particle
exhaust in stellarators. At the Wendelstein 7-X (W7-X) stellarator, this divertor concept plays …

How much of the density pedestal structure is determined by fueling versus transport is still
an open question. In most current tokamaks, the scrape-off layer is not opaque enough to …

Abstract The recently developed Monte-Carlo code ERO2. 0 is applied to the modelling of
limited and diverted discharges at JET with the ITER-like wall (ILW). The global beryllium …

Results from three-dimensional modeling of plasma edge transport and plasma–wall
interactions during application of resonant magnetic perturbation (RMP) fields for control of …

Modeling of impurity-seeded plasma in Large Helical Device is presented for the first time by
using the three-dimensional transport code EMC3-EIRENE. High and low recycling …

The results of a first systematic assessment of plasma edge transport processes for the
limiter startup configuration at Wendelstein 7-X are presented. This includes an investigation …