Due to their low sputtering yield, low intrinsic tritium retention, high melting point, and high
thermal conductivity, W and W alloys are promising candidates for the divertor region in a …

The nucleation and subsequent growth of helium bubbles in bulk tungsten is investigated
using molecular dynamics simulations. By considering a setting that includes the diffusion …

Tungsten (W) has been perceived as one of the most promising plasma facing materials
(PFMs) for future fusion reactors. In the past decade, its behavior under irradiation and …

Tungsten is one of the prime candidates for a first-wall material near the divertor area due to
its high temperature strength, high thermal conductivity, low erosion rate and low tritium …

The low solubility of hydrogen in tungsten leads to the growth of near-surface hydrogen
precipitates during high-flux plasma exposure, strongly affecting migration and trapping in …

Different behaviours of noble gas X (X= He or Ne) atoms in the bulk and on the surface of
tungsten (W) have been studied with molecular dynamics simulations to explore the fuzz …

Abstract Tantalum–tungsten (Ta–W) alloys have been considered candidates for plasma-
facing materials (PFMs) in advanced nuclear fusion design due to their excellent thermal …

Our study investigates the interaction of dislocations with hexagonal close-packed (hcp) and
chi-phase (χ) particles in body-centred cubic (bcc) tungsten (W) using molecular dynamics …

This work, with an emphasis on helium irradiation rates appropriate for fusion-plasma
conditions, advances the understanding of helium evolution at grain boundaries in W, an …

Due to a lack of direct experimental results, the detailed mechanisms that govern the
blistering behavior of tungsten (W) exposed to ITER-relevant condition in nuclear fusion …