In this work we investigated the adsorption of oxygen and the co-adsorption of oxygen and
hydrogen on the (110) surface of tungsten by means of Density Functional calculations. The …

A damage-induced hydrogen trap creation model is proposed, and parameters for tungsten
are identified using experimental data. The methodology for obtaining these parameters …

A kinetic surface model is presented and used to explain the loading and desorption kinetics
of tritium retained in micrometre-sized tungsten (W) dust particles. The model describes the …

The reduced activation ferritic martensitic steel EUROFER is one of the foreseen structural
materials for future fusion reactors. The exposure to energetic fusion neutrons will generate …

The effect of helium (He) on deuterium (D) retention and transport in the bulk of tungsten (W)
was investigated. For this purpose samples were irradiated by 500 keV He ions at 300 K to …

We present an analytical thermodynamic model of a surface in contact with a gas phase,
which enables us to determine the surface coverage of the adsorbate depending on the …

Rate equation modelling is performed to simulate D2 and D2+ D+ 2 exposure of the W (110)
surface with varying coverage of oxygen atoms (O) from the clean surface up to 0.75 …

The commonly accepted picture for the uptake of hydrogen isotopes (HIs) from the gas
phase across the surface into a metal with an endothermic heat of solution for HIs is that of …

Tungsten is currently the most promising material for plasma-facing in FRs. The
accumulation of radioactive tritium in tungsten is caused by presence of hydrogen traps in …

One of the priority tasks for sustainable operations of future fusion devices is the systematic
control of hydrogen isotope content in plasma-facing components. A remote non-damaging …