As the most noticeable plasma-oriented material (PFM), metal tungsten is widely used in
nuclear fusion reactors. However, its oxidation resistance is poor at high temperatures …

In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat
and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing …

Heat loads on the tungsten divertor targets in the ITER and the tokamak power reactors
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …

The interaction of externally applied small non-axisymmetric magnetic perturbations (MP)
with tokamak high-confinement mode (H-mode) plasmas is reviewed and illustrated by …

The I-mode confinement regime can feature small edge temperature drops that can lead to
an increase in the energy deposited onto the divertor targets. In this work, we show that …

The influence of recrystallization on thermal shock resistance has been identified as an
issue that may influence the long term performance of ITER tungsten (W) divertor …

Full tungsten poloidal and mushroom limiters were tested in series of experiments with
disruptions in the T-10 tokamak. Significant melting, formation of small craters and erosion of …

Divertor power load is a major challenge towards a burning plasma in a next-step tokamak.
Here, the first results of a divertor power load characterisation in tritium plasmas in type-I …

Fine-grain tungsten alloys could be one of the solutions for the plasma facing materials of
future DEMO reactors. In order to evaluate the service performances of the newly developed …

A wet-chemical method combined with spark plasma sintering was used to prepare W-0.5
wt% Y 2 O 3 alloy. The W-0.5 wt% Y 2 O 3 precursor was reduced at 800° C for 4 h under …