Current phenomenological knowledge and understanding of mechanisms are reviewed for
radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted …

The subject of radiation-induced solute segregation (RIS) in metallic alloys is reviewed. RIS
manifests itself in several different ways, including diffusion to point-defect sinks …

The degradation of austenitic stainless steels in a radiation environment is a known problem
for the in-core components of nuclear light water reactors. For a better understanding of the …

The role of d electrons in determining distributions of formation and migration energies for
point defects in equiatomic NiCoCr and NiCoFeCr concentrated solid solution alloys (CSAs) …

Austenitic stainless steels are commonly used materials for in-core components of nuclear
light water reactors. In service, such components are exposed to harsh conditions: intense …

Defect-driven diffusion of impurities is the major phenomenon leading to formation of
embrittling nanoscopic precipitates in irradiated reactor pressure vessel (RPV) steels …

We report first-principles results of the point defect properties in a V-Ta-Cr-W high-entropy
alloy (HEA) with the body-centered cubic (bcc) structure. Different from the widely …

The RIS mechanism in austenitic and ferritic–martensitic (F–M) alloys is addressed by both
atomic-scale modeling and experiment. Ab initio based modeling shows that the inverse …

To investigate the erosive wear-corrosion behavior of ZTA P ceramic reinforced high
chromium cast iron matrix composites in two types of sand at various rotational speeds, the …

Density functional theory models developed over the past decade provide unique
information about the structure of nanoscale defects produced by irradiation and about the …