Exposure of metals to neutron irradiation results in an increase in the yield strength and a
significant loss of ductility. Irradiation hardening is also closely related to the fracture …

Ferritic/martensitic steels will be used as structural components in next generation nuclear
reactors. Their successful operation relies on an understanding of irradiation-induced defect …

Transmission electron microscopy (TEM) was used to compare the microstructural defects
produced in an Fe9Cr model alloy during exposure to neutrons, protons, or self-ions …

This study presents a detailed examination of the lattice distortions introduced by glancing
incidence Focussed Ion Beam (FIB) milling. Using non-destructive multi-reflection Bragg …

Presented here are atomistic simulations of the interaction of a collision cascade in α-Fe with
different types of grain boundaries (GBs). The collision cascade was generated by a primary …

Stable precipitate takes the essential role for material strengthening in Al–Mg–Si alloys. To
reveal how the stable precipitate works in material strengthening, a molecular dynamics …

The mechanical properties of neutron irradiated Fe–Cr ferritic model alloys with various
concentrations of Cr and minor solutes (Ni, Si and P) were investigated along with high-Cr …

Spherical nanoindentation of an iron-chromium-aluminum alloy was conducted to study the
effect of ferric-ion (Fe 3+) irradiation on the time-dependent plasticity behavior in the surface …

Fe-Cr alloys constitute the model systems for the investigation of radiation damage effects in
ferritic-martensitic steels which are candidate structural materials for fusion reactors. In the …

Molecular Dynamics simulation was employed to study precipitate composition dependence
on strengthening. Edge dislocation interaction with pure, 80at.%, and 60at.% Cr precipitates …