The synergistic evolution mechanisms of He bubbles and dislocation loops under 30 keV H
2+ & H e+ dual-beam ions irradiation at 650° C in the Ni-based alloy GH3535, which is the …

The effect of dose rate on neutron-induced microstructural evolution was experimentally
estimated. Solution-annealed austenitic model alloys were irradiated at≃ 400° C with fast …

CrFeNi-based multi-principal element alloys (MPEAs) are being considered for nuclear
applications because of their potentially superior mechanical properties and irradiation …

He bubbles are characteristic microstructures under fusion reactor conditions. They
approach and coalesce through their own migration, which significantly impacts the …

When stainless steels are exposed to high irradiation dose, a fraction of Frank loops will
unfault and transform into perfect loops. After unfaulting, perfect loops can glide and impinge …

The accumulation of point defects and defect clusters in materials, as seen in irradiated
metals for example, can lead to the formation and growth of voids. Void nucleation is derived …

Complete sets of microstructural data have recently become available for two different
irradiation times and for pure ternary alloys of austenitic stainless steels. Using these data as …

A novel computational treatment of dense, stiff, coupled reaction rate equations is introduced
to study the nucleation, growth, and possible coalescence of cavities during neutron …

Austenitic stainless steels, which are used as incore structural materials in light water
reactors, are characterized by an extremely low stacking fault energy (SFE) among face …

In this study, a Neural Network Potential (NNP) using an Artificial Neural Network (ANN) was
developed for Zr, which is used as fuel claddings in light water reactors. The reference data …