Small specimen testing techniques have a long history in nuclear material research due to
the limitations posed by nuclear facilities. The limited space in reactors and the fact that the …

The indentation size effect response, based on dislocation density, of commercially pure Ni
irradiated at 120° C with 6MeV protons to 0.1 dpa, was compared with non-irradiated Ni …

The production of prismatic dislocation loops in nuclear reactor core materials results in
hardening because the loops impede dislocation motion. Yielding often occurs by a …

In this study, we demonstrate the methodology systematically developed for dislocation loop
(perfect and faulted loops) imaging and analysis in irradiated face-centered-cubic (FCC) …

Irradiation-induced anisotropic swelling in hexagonal α-SiC is known to degrade the
mechanical properties of SiC; however, the associated physical mechanism and …

Accurately quantifying swelling of alloys that have undergone irradiation is essential for
understanding alloy performance in a nuclear reactor and critical for the safe and reliable …

Imaging nanoscale features using transmission electron microscopy is key to predicting and
assessing the mechanical behavior of structural materials in nuclear reactors. Analyzing …

Thermal annealing or radiation induced segregation of solute and impurity elements to grain
boundaries (GBs) in metallic alloys changes GB chemistry and thus can alter the GB …

The results from a novel, micro-tensile testing technique, employing a micro-electro-
mechanical system, operated in a push-to-pull configuration, to study the effects of radiation …

This paper presents molecular dynamics (MD) simulations of plastic deformation in single-
crystal Ni models containing internal distributions of helium (He) bubbles and self-interstitial …