The tungsten (W) material as the divertor of fusion reactors is exposed to low-energy and
high-flux He/H isotope irradiation, leading to the growth of fuzz layers. The W fuzz growth …

Although W fuzz is formed in the divertor region of the fusion reactor, no theory may clearly
explain the W fuzz growth mechanism. In this study, we observe the growth process of W …

Based on the physical processes, such as the collisions of energetic He ions in a fuzz layer,
He+ implantations into W bulk, and surface erosion of W fuzz layer, we have modeled the …

Growth of helium (He) induced bubbles and fuzz in tungsten (W) and molybdenum (Mo) is
investigated using samples of W films on Mo substrates and Mo films on W substrates …

In this study, the nanocrystalline NbMoTaW and NbMoTaWV refractory multi-principal
element alloy (RMPEA) films were selected for the research of low-energy (50 eV), high-flux …

Based on our previous study (J. Nucl. Mater. 550 (2021) 152917), an improved model used
to predict the W fuzz growth over W targets is presented by considering the complex physical …

Molybdenum (Mo) is considered as a promising plasma-facing material, which is expected
to be used in the manufacture of critical components for the neutral beam injection (NBI) …

We report simulation results on the effect of helium (He) bubble bursting-mediated surface
hole formation on the surface morphological response of tungsten plasma-facing …

We report results of object kinetic Monte Carlo (OKMC) simulations to understand the effect
of helium flux on the near-surface helium accumulation in plasma-facing tungsten, which is …

In this study, W-(Y 0.9 La 0.1) 2 O 3 composite powders are fabricated by means of a
combination of wet chemical method and spark plasma sintering. We systematically study …