Uranium mononitride (UN) is an attractive fuel for a range of reactors, including, with
adequate protection against reaction with water, for large scale and small modular light …

High-entropy carbide ceramics (WTiVNbTa) C 5 were prepared by spark plasma sintering
and irradiated with 1.0 MeV C-ions at room temperature (RT) and 650℃. Irradiation induced …

We have addressed the issue of improper and unreliable analysis of materials
characterization data by developing an artificial intelligence based methodology that can …

Ultra-high temperature ceramics (UHTCs) hold great potential as structural materials in
advanced nuclear reactors that operate in harsh environments characterized by high …

Silicon nitride and zirconium nitride have been proposed as potential materials for multiple
nuclear applications (inert matrix fuels, accident tolerant fuels, space nuclear power, fusion …

The composite Zinc oxide/calcium phosphate was successfully prepared using the sol–gel
method. The structural and optical properties are observed by using x-ray Diffraction and …

Abstract Employing wide spectral range (0.06–6 eV) optical reflectance measurements and
high energy X-ray photoemission spectroscopy (HE-XPS), we studied the effect of 800 keV …

In the framework of the SELENIUM project, ZrN coated U-Mo fuel kernels were irradiated in
the Belgium Reactor 2 of SCK• CEN to a plate average burnup of 48% 235 U and a local …

The effects on the local structure due to self-irradiation damage of Ga stabilized δ-Pu stored
at cryogenic temperatures have been examined using extended x-ray absorption fine …

ZrN is a promising material for inert matrix fuel and transmutation targets in advanced
nuclear applications. The nucleation-and-growth process of radiation-induced defects in …