Advances in nuclear power reactors include the use of mixed oxide fuel, containing uranium
and plutonium oxides. The high-temperature behaviour and structure of PuO2–x above …

Uranium–plutonium mixed oxides, containing few mol% of Am, are currently studied as fuel
for Sodium Fast Reactors. The study of the O/M ratio of these fuels is of main interest, as its …

Uranium-Plutonium mixed oxides U 1-y Pu y O 2-x are considered as the reference fuels for
Sodium-cooled Fast neutron Reactors (SFRs). Nevertheless, there is a lack of experimental …

In this letter, we developed a pragmatic strategy for coupling the phase-field model with the
thermodynamic/kinetic descriptions and applied it to quantitatively describe the complex …

In this deliverable, we outline the correlations and data that have been transferred to models
suitable for fuel performance codes (TRANSURANUS, GERMINAL) for the simulation of Am …

The present work describes original experimental results obtained on the melting and
solidification behaviour of mixed PuO 2–Fe 3 O 4 samples. The samples were laser-heated …

Mixed oxides of uranium and plutonium (MOX) are currently considered reference fuels for
the new generation of fast breeder reactors such as ASTRID. The key factor determining the …

As UO2 is easily oxidized during the nuclear fuel cycle it is important to have a detailed
understanding of the structures and properties of the oxidation products. Experimental work …

Reprocessing spent nuclear fuel creates the conditions for converting nuclear energy to a
clean and sustainable energy. Thermal conductors in reactors are molten salts, the safe use …

Uranium-americium mixed oxides are envisaged as fuels or blankets for the transmutation of
americium in fast neutron reactors, which requires an accurate knowledge of their …