In-situ irradiations with 30 keV He+ were performed on tungsten in an investigation of the
influences of irradiation temperature and fluence, pre-existing dislocation and sample …

This paper is the first of three that overview the main mechanisms that drive the
microstructure evolution in Fe alloys under irradiation. It focuses on pure α-Fe and compiles …

Abstract Iron-chromium-aluminum (FeCrAl) alloys with different content of niobium (Nb)—0,
0.4 wt%, 0.8 wt%, and 1.2 wt%—were designed and prepared. All samples were then …

On-the-fly kinetic Monte Carlo (kMC) methods have recently garnered significant attentions
after successful applications to various atomic-scale problems using a timescale outside the …

Tungsten (W) and W-based alloys are competitive candidates for plasma-facing materials in
future fusion reactors. W-tantalum (Ta) alloys get the most attention amongst these materials …

The attractive mechanical properties and superior resistance to void-swelling make
ferritic/martensitic alloys a promising structural material for advanced nuclear reactors …

Low mobility< 100> loops significantly affect the mechanical properties of body-centered
cubic materials and their generation and evolution have been a hot research topic recently …

Recent post-irradiation annealing (PIA) investigations on the neutron-irradiated reduced-
activation ferritic-martensitic (RAFM) steel EUROFER97 have led to an almost complete …

FeCrAl alloys with excellent comprehensive properties are the most promising candidates to
replace zirconium alloy fuel claddings. In our study, the dislocation loop evolution including …

Dislocation loop and gas bubble evolution in tungsten were in-situ investigated under 30
keV H 2+ and He+ dual-beam irradiation at 973 K and 1173 K. The average size and …