Tungsten, the primary material under consideration as the divertor material in magnetic-
confinement nuclear fusion reactors, has been known for the last decade to form'fuzz'—a …

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 …

In this work, using in-situ uniaxial tensile and compressive testing, microscopy, and
theoretical analysis, we study the mechanism underlying the ultrahigh irradiation hardening …

Understanding the interaction of hydrogen (H) with defects has been recognized as a central
aspect in hydrogen-induced damages in metals. In this work, the role of coherent and semi …

The mechanism of tungsten (W) blistering under deuterium (D) plasma exposure is still
under investigation. To clearly demonstrate the microstructure and nucleation mechanism of …

Tungsten (W) has been chosen as the primary plasma-facing material in nuclear fusion
reactors. However, when helium (He) ions are continuously irradiated, enormous amounts of …

In situ irradiations with 30 keV He+ have been performed on W–0.5 wt% ZrC at 823 and
1073 K. Detailed characterization showed that the dislocation loops around the ZrC particles …

In this work, we utilized spherical nanoindentation to investigate the mechanical property
changes of helium (He) implanted tungsten (W) at different damage doses. According to the …

Molecular dynamics simulations were used to study the growth process of a He bubble on
an edge dislocation in W, and the results indicated that the growth was controlled by a …

Tritium retention and microstructural modifications due to helium accumulation are two of the
main concerns regarding plasma-facing materials in fusion applications. Crystal defects in …