The major increase in discharge duration and plasma energy in a next step DT fusion
reactor will give rise to important plasma-material effects that will critically influence its …

ITER will use beryllium as a plasma-facing material in the main chamber, covering a total
surface area of about 620 m 2. Given the importance of beryllium erosion and co-deposition …

The use of tungsten (W) as material for plasma-facing components (PFM) in fusion devices
is reviewed with respect to its plasma and material compatibility under burning plasmas …

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

The erosion of tungsten (W), induced by the bombardment of plasma and impurity particles,
determines the lifetime of plasma-facing components as well as impacting on plasma …

The Spherical Tokamak for Energy Production (STEP) programme aims to deliver a first-of-a-
kind fusion prototype powerplant (SPP). The SPP plasma places extreme heat, particle and …

JET is used as a test bed for ITER, to investigate beryllium migration which connects the
lifetime of first-wall components under erosion with tokamak safety, in relation to long-term …

Tungsten erosion in H-mode plasmas is quantified in the outer divertor of the JET ITER-Like
Wall environment with optical emission spectroscopy on the 400.9 nm atomic neutral …

Gross and net erosion of tungsten (W) and other plasma-facing materials in the divertor
region have been investigated in deuterium (D) and helium (He) plasmas during dedicated …

ERO is a Monte-Carlo code for modeling plasma-wall interaction and 3D plasma impurity
transport for applications in fusion research. The code has undergone a significant upgrade …