Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads
to tolerable heat and particle loads on the wall is a major challenge. The new European …

The divertor of a tokamak reactor will have to satisfy a number of critical constraints, the first
of which is that the divertor targets not fail due to excessive heating or sputter-erosion. This …

Detachment of high power discharges is obtained in ASDEX Upgrade by simultaneous
feedback control of core radiation and divertor radiation or thermoelectric currents by the …

A large scale program to develop a conceptual design for a demonstration fusion power
plant (DEMO) has been initiated in Europe. Central elements are the baseline design points …

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 …

In the European fusion roadmap, ITER is followed by a demonstration fusion power reactor
(DEMO), for which a conceptual design is under development. This paper reports the first …

Plasmas in machines with all metal plasma facing components have a lower Z eff, less
radiation cooling in the scrape-off layer and divertor regions and are prone to impurity …

A first-principles scaling law, based on turbulent transport considerations, and a
multimachine database of density limit discharges from the ASDEX Upgrade, JET, and TCV …

For several reasons the challenge to keep the loads to the first wall within engineering limits
is substantially higher in DEMO compared to ITER. Therefore the pre-conceptual design …

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 …