The interaction between glissile dislocations and precipitates within a continuum is
responsible for marked increases in material strength. Due to their desirable engineering …

The understanding of materials' behaviour during continuous irradiation is of great interest
for utilizing materials in environments where harsh radiation is present, like nuclear power …

Oxide dispersed strengthened (ODS) steel is an important candidate for Gen-IV reactors.
Oxide embedded in Fe can help to trap irradiation defects and enhances the strength of …

To investigate the reason why low-carbon steels with carbon-clusters shows the maximum
strength during low-temperature aging, interactions between an edge dislocation and …

The irradiation damage-induced voids can hinder dislocation glide, and thereby change the
mechanical properties in the nuclear materials. However, the detailed process of the …

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

Assessment of candidate materials for fusion power plants provides one of the major
structural materials challenges of the next decades. Both plasma and the release of high …

Nanocrystalline materials with high grain boundary fractions have been proposed as
potential candidates for radiation-tolerant materials in nuclear reactors due to their high …

抄録 To investigate the reason why low-carbon steels with carbon-clusters shows the
maximum strength during low-temperature aging, interactions between an edge dislocation …