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 …

Reduced activation ferritic/martensitic steels are currently the most technologically mature
option for the structural material of proposed fusion energy reactors. Advanced next …

Tungsten is the front-runner candidate for building the plasma-facing armour components for
future fusion reactors. However, in-service irradiation by fusion-neutrons and helium will …

This study examines clustering and hardening in W–2 at.% Re and W–1 at.% Re–1 at.% Os
alloys induced by 2 MeV W+ ion irradiation at 573 and 773 K. Such clusters are known …

The effects of ion irradiation in materials for research are usually limited to a shallow surface
layer of the order of one micrometre in depth. Determining the mechanical properties of such …

Using transient grating spectroscopy (TGS) we measure the thermal diffusivity of tungsten
exposed to different levels of 20 MeV self-ion irradiation. Damage as low as 3.2× 10− 4 …

We propose and demonstrate a microstructurally-based experimental method to quantitively
determine the depth regions in self-ion-irradiated metals that are affected by the injected …

FeCrAl alloys are candidates for accident tolerant fuel cladding of light water reactors. In this
work, a microstructure-and temperature-dependent crystal plasticity model is employed to …

Point defects in body-centred cubic Fe, Cr and concentrated random magnetic Fe-Cr are
investigated using density functional theory and theory of elasticity. The volume of a …

The objective of this study is to evaluate the influence of dose rate and cascade morphology
on nanocluster evolution in a model Fe-9% Cr oxide dispersion strengthened steel and the …