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 …

Reduced activation ferritic/martensitic steels are currently the most technologically mature
option for the structural material of proposed fusion energy reactors. Advanced next …

Oxide dispersion-strengthened (ODS) steels are the most promising candidate materials for
fuel cladding of Generation IV nuclear reactors. The progress and current status for …

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 …

This study presents the influence of the main selective laser melting (SLM) processing
parameters on the densification behavior and microstructure evolution of oxide dispersion …

Currently, state-of-the-art reactors concept is based upon higher efficiency and better
utilization of nuclear power. This energy is considered an alternate source replacing …

In this study, it is presented an analytical model of chemical composition correction for
nanoclusters observed by atom probe tomography, tacking into account artefacts that can …

High temperature heat treatment is one of the critical steps in hot compression bonding
(HCB), which was recently developed to scale up the fabrication of oxide dispersion …

Abstract Oxide Dispersion Strengthened (ODS) steels are promising candidates for future
nuclear reactors, partly due to the fine dispersion of the nanoparticles they contain. Until …

In the course of a recrystallization study of Oxide Dispersion Strengthened (ODS) ferritic
steels during extrusion, particular interest was paid to the (GB) Grain Boundaries interaction …