The thermal diffusivity of (Th, Pu) O2 (with 3, 8 and 30wt.% PuO2) mixed oxides and of the
single oxides PuO2 and ThO2 was measured using the laser flash technique. In several …

Recycling and burning minor actinides (MA, eg, americium, neptunium) in mixed-oxide
(MOX) nuclear fuel is a strategic option for fast reactor concepts of Generation IV, especially …

Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its
performance under irradiation, since they determine the fuel temperature profile and the …

Thorium-uranium oxide pellets with high densities were prepared at the Canadian Nuclear
Laboratories (CNL) by co-milling, pressing, and sintering at 2023 K, with UO 2 mass …

Lanthanide‐doped thoria is relevant both to nuclear energy and to solid oxide fuel cell
technology. It is also a simple model system in which oxygen vacancy concentration is …

The current modelling of thermal properties (thermal conductivity, melting temperature) of
mixed-oxide (MOX) nuclear fuels in Fuel Performance Codes (FPCs), eg, GERMINAL …

The behavior of nuclear fuel during irradiation is largely dependent on its thermophysical
properties and their change with temperature and burnup. Experimental data on out-of-pile …

Values are presented for thermal conductivity, specific heat, spectral and total hemispherical
emissivity of ThO2 (a potential nuclear fuel material) in a temperature range representative …

High-density Th1− xMxO2− y (M= Y, La, Ce, Nd, Gd and U; x= 0.05 and 0.10) samples were
fabricated by solid-state reaction followed by Spark plasma sintering. The lattice parameter …

Research activities are currently underway worldwide to develop Generation IV nuclear
reactor concepts with the objective of improving thermal efficiency and increasing economic …