Prediction of material performance in fusion reactor environments relies on computational
modelling, and will continue to do so until the first generation of fusion power plants come on …

Under the anticipated operating conditions for demonstration magnetic fusion reactors
beyond ITER, structural and plasma-facing materials will be exposed to unprecedented …

A body-centered cubic W-based refractory high entropy alloy with outstanding radiation
resistance has been developed. The alloy was grown as thin films showing a bimodal grain …

High-entropy alloys (HEAs) have received much attention for the development of nuclear
materials because of their excellent irradiation tolerance. In the present study, the …

Pure tungsten samples have been neutron irradiated in HFIR at 90–850° C to 0.03–2.2 dpa.
A dispersed barrier hardening model informed by the available microstructure data has …

In-situ irradiations with 30 keV He+ were performed on tungsten in an investigation of the
influences of irradiation temperature and fluence, pre-existing dislocation and sample …

In-situ TEM observation and molecular dynamics simulation were used to investigate the
evolution of irradiation-induced dislocation loops and their interactions with the pre-existing …

In-situ irradiations with 150 keV W+ ions have been performed on W and W-5wt.%(Re; Ta;
V) alloys in a comprehensive study of the influences of irradiation temperature T irr, dose …

Displacement damage, through heavy ion irradiation was studied on two tungsten grades
(coarse grained tungsten (CGW) and nanocrystalline and ultrafine grained tungsten (NCW)) …

Simulating collision cascades and radiation damage poses a long-standing challenge for
existing interatomic potentials, both in terms of accuracy and efficiency. Machine-learning …