The change in surface damage/microstructures and its effects on the hydrogen (H)
isotope/helium (He) dynamic behavior are the key factors for investigating issues of tungsten …

How displacement damage defects generate and evolve in materials irradiated by energetic
particles is a perennial topic in the field of nuclear materials. Here we experimentally reveal …

We studied the influence of thin, electro-chemically grown tungsten (W) surface oxide films
on hydrogen isotope release from W. As deuterium (D) reservoir underneath the oxide, we …

Bulk tungsten samples were irradiated sequentially with 20 MeV tungsten ions and exposed
to deuterium plasma. The experiments were performed in order to simulate the displacement …

We studied the uptake of deuterium (D) into tungsten (W) through thin films of W oxide. Two
surface oxide films with thicknesses of 33 and 55 nm were thermally grown on W substrates …

Fuel retention in plasma facing tungsten components is a critical phenomenon affecting the
mechanical integrity and radiological safety of fusion reactors. It is known that hydrogen can …

Irradiation of materials in nuclear test reactors and power plants is known to alter the
properties of the material. The irradiation event happening at pico-or nanosecond time …

An extended understanding of ion-solid interaction processes is of great interest in many
different research areas. Especially for weathering of the surfaces of planets, moons and …

For future fusion power plants, the uptake, retention and release of fuel elements (deuterium
and radioactive tritium) in plasma-facing components (PFCs) is essential for the fuel self …

Plasma-facing materials in fusion reactors experience extreme conditions as high energy
particles such as neutrons and ions interact with the materials. Irradiation damage caused …