Materials subjected to high dose irradiation by energetic particles often experience severe
damage in the form of drastic increase of defect density, and significant degradation of their …

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 …

L1 2-strengthened high entropy alloys (HEAs) with excellent room and high-temperature
mechanical properties have been proposed as promising candidates as structural materials …

Mechanically alloyed Fe-based alloys with oxide dispersion strengthening have largely
dropped out of the marketplace due to high cost related to problems with complex and …

This paper provides an overview of advanced scanning transmission electron microscopy
(STEM) techniques used for characterization of irradiated BCC Fe-based alloys. Advanced …

Face-centered cubic (FCC) high-entropy alloys (HEA), as emerging alloys with equal-molar
or near equal-molar constituents, show a promising radiation damage resistance under …

The formation of helium bubbles and subsequent property degradation poses a significant
challenge to tungsten as a plasma-facing material in future long-pulse plasma-burning …

As one of the most promising first wall/blanket structure materials in fusion reactors, oxide
dispersion strengthened (ODS) ferritic steel has been extensively studied in past decades …

The microstructural evolution of purity Pd under 30 keV He+ irradiation at 573 K was
investigated by in-situ transmission electron microscopy. The nucleation, growth, merging …

Quantifying chemical compositions around nanovoids is a fundamental task for research
and development of various materials. Atom probe tomography (APT) and scanning …