Helium (He) bubbles are typical radiation defects in structural materials in nuclear reactors
after high dose energetic particle irradiation. In the past decades, extensive studies have …

The flow stress in irradiated Austenitic Stainless Steels (ASSs) is analyzed in terms of the
microstructure features and the fundamental mechanisms of plastic deformation. A set of …

A series of Fe-3 to 18 at.% Cr binary ferritic alloys were neutron irradiated side by side, in the
Advanced Test Reactor (ATR) at a temperature of∼ 320° C to a dose of∼ 1.8 dpa. Three …

The plastic behavior of irradiated Reactor Pressure Vessel (RPV) steels is described by
constitutive equations capturing the temperature and strain rate sensitivities. The flow stress …

In order to understand the effect of irradiation on the material properties, we need to look into
the atomistic evolution of the system during the recoil event. The nanoscale features formed …

Oxide dispersed strengthened steel (ODSS) is widely used in nuclear industry due to its
excellent creep and void swelling resistance. The presence of high density of uniformly …

The resistance of a dislocation to bowing under stress governs the strength of the gamut of
metallic material systems. This resistance is commonly referred to as the dislocation line …

In this work the interactions of an edge dislocation with Cu precipitates of different diameters
in α-Fe were investigated by molecular dynamics simulation. The influence of Fe atoms or …

Solute cluster induced hardening plays a dominant role in the irradiation embrittlement of
reactor pressure vessel. For Cu-rich clusters, the Russell and Brown model (1972) is often …

Abstract The interactions of a 1/2< 111>{110} edge dislocation with nano-sized Cu, Cu-Ni
and Cu-Mn precipitates have been investigated by using of molecular dynamics method. It is …