The process of void nucleation, growth, and coalescence is among the dominant ductile
failure modes in metallic alloys and can be transgranular as well as intergranular. In the …

It has long been recognized that exposure to irradiation environments could dramatically
degrade the mechanical properties of nuclear structural materials, ie, irradiation-hardening …

The lack of suitable materials solutions stands as a major challenge for the development of
advanced nuclear systems. Most issues are related to the simultaneous action of high …

Microcrystalline and nanocrystalline UO 2, ThO 2, and CeO 2 (∼ 2 μm and∼ 20 nm particle
size, respectively) were irradiated with 946 MeV Au ions at room temperature and …

Nanostructured tungsten has been proposed as a promising option for plasma facing
materials in future fusion reactors, because compared to conventional tungsten it shows …

The opportunity to achieve radiation tolerance in crystalline materials hinges on
understanding the structure and response of grain boundary sinks to irradiation. A common …

The magnetron sputtered Cr coatings on zirconium (Zr) alloy substrates were irradiated by
the 5 MeV Xe 20+ ions at room temperature, followed by the studies on microstructure …

Within the accident tolerant fuel cladding (ATFC) concept, chromium coatings appear to be
promising for protecting zirconium alloys from high temperature oxidation. The effects of high …

Swelling is commonly observed in austenitic stainless steels irradiated at high doses and
high temperatures, such as fuel claddings in Fast-Breeder Reactors (FBR), as a …

Thermochemical properties of aluminum micro-and nanopowders after exposure to
synchrotron radiation with energy in the range 15.5–20.6 keV has been investigated. The …