Thermophysical properties of uranium dioxide
JK Fink - Journal of nuclear materials, 2000 - Elsevier
Experimental data on thermodynamic and transport properties of solid and liquid UO2 have
been reviewed and analyzed to obtain consistent equations for the thermophysical …
been reviewed and analyzed to obtain consistent equations for the thermophysical …
A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: review and recommendations
PG Lucuta, IJ Hastings - Journal of nuclear materials, 1996 - Elsevier
The thermal conductivity of irradiated UO2 fuel is discussed considering the effects of
burnup (dissolved and precipitated solid fission products), porosity and fission-gas bubbles …
burnup (dissolved and precipitated solid fission products), porosity and fission-gas bubbles …
A review of the thermophysical properties of MOX and UO2 fuels
A critical review of the thermophysical properties of UO2 and MOX fuels has been
completed, and the best correlations for thermophysical properties have been selected. The …
completed, and the best correlations for thermophysical properties have been selected. The …
[HTML][HTML] A review of fuel performance modelling
Dr. Paul Van Uffelen graduated from the Vrije Universiteit Brussel (Belgium) and the Ecole
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …
Small polarons in real crystals: concepts and problems
Much of small polaron theory is based on highly idealized models, often essentially a
continuum description with a single vibrational frequency. These models ignore much of the …
continuum description with a single vibrational frequency. These models ignore much of the …
Thermal conductivity of hypostoichiometric low Pu content (U, Pu) O2− x mixed oxide
C Duriez, JP Alessandri, T Gervais… - Journal of Nuclear …, 2000 - Elsevier
The 'laser flash'method was used to measure the thermal diffusivity of PWR mixed oxide
fuels with Pu contents ranging from 3 to 15 wt% and oxygen to metal ratio (O/M) ranging …
fuels with Pu contents ranging from 3 to 15 wt% and oxygen to metal ratio (O/M) ranging …
Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors
Accident-tolerant fuel (ATF) has attracted considerable research attention since the 2011
Fukushima nuclear disaster. To improve the accident tolerance of the fuel-cladding systems …
Fukushima nuclear disaster. To improve the accident tolerance of the fuel-cladding systems …
Evaluation of thermal properties of UO2 and PuO2 by equilibrium molecular dynamics simulations from 300 to 2000 K
The thermal properties of UO2 and PuO2 have been investigated by the equilibrium
molecular dynamics (EMD) simulations between 300 and 2000K using the Born–Mayer …
molecular dynamics (EMD) simulations between 300 and 2000K using the Born–Mayer …
Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3 Si2) with increased uranium loading
The processing steps necessary to prepare a potential accident-tolerant fuel composite
consisting of uranium mononitride (UN) combined with uranium sesquisilicide (U 3 Si 2) are …
consisting of uranium mononitride (UN) combined with uranium sesquisilicide (U 3 Si 2) are …
Thermal diffusivity and conductivity of thorium–plutonium mixed oxides
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 …
single oxides PuO2 and ThO2 was measured using the laser flash technique. In several …