Prediction of material performance in fusion reactor environments relies on computational
modelling, and will continue to do so until the first generation of fusion power plants come on …

Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS)
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …

This work investigates solute transport due to self-interstitial defects and radiation induced
segregation tendencies in dilute ferritic alloys, by computing the transport coefficients of …

Radiation-enhanced precipitation of Cr-rich α′ in irradiated Fe-Cr alloys, which results in
hardening and embrittlement, depends on the irradiating particle and the displacement per …

The kinetics of phase separation in Fe–Cr alloys under irradiation is modeled by Atomistic
kinetic Monte Carlo simulations that include the formation, migration and elimination of …

The M4F project brings together the fusion and fission materials communities working on the
prediction of radiation damage production and evolution and their effects on the mechanical …

The intergranular corrosion behavior of the low-chromium ferritic stainless steel without Cr-
carbide precipitation was investigated by the methods of qualitative and quantitative …

Predicting atomic diffusion in concentrated magnetic systems is challenging due to thermal
magnetic effects and complex magnetochemical interplay. We propose an efficient approach …

Irradiation creates excess point defects in materials (vacancies and self-interstitial atoms),
which can be eliminated by mutual recombination, clustering, or annihilation of preexisting …

The occurrence of segregation in dilute alloys under irradiation is a highly unusual
phenomenon that has recently attracted attention, stimulated by the interest in the …