25 citations · 45 across the 4 of their papers we have counts for
5 papers
A Simple Modeling for Gas Release During Annealing of Irradiated Nuclear Fuel
Jimmy Losfeld, Lionel Desgranges, Yves Pontillon +1
We have developed a gas flow model in the spent nuclear fuel during the annealing. It postulates that the gas release during an isothermal plateau at 1200{\textdegree}C corresponds…
Influence of the U3O7 domain structure on cracking during the oxidation of UO2
Lionel Desgranges, Hervé Palancher, M. Gamaléri +5
Cracking is observed when a UO_{2} single crystal is oxidised in air. Previous studies led to the hypothesis that cracking occurs once a critical depth of U_{3}O_{7} oxidised layer…
Specific Aspects of Internal Corrosion of Nuclear Clad Made of Zircaloy
Jean-Baptiste Minne, Lionel Desgranges, Virgil Optasanu +3
In PWR, the Zircaloy based clad is the first safety barrier of the fuel rod, it must prevent the dispersion of the radioactive elements, which are formed by fission inside the UO2…
Internal Interface Strains Effects on UO2/U3O7 Oxidation Behaviour
Nicolas Creton, Virgil Optasanu, Sébastien Garruchet +4
The growth of a U3O7 oxide layer during the anionic oxidation of UO2 pellets induced very important mechanical stresses due to the crystallographic lattice parameters differences b…
A thermodynamic approach of the mechano-chemical coupling during the oxidation of uranium dioxide
Nicolas Creton, Virgil Optasanu, Tony Montesin +2
The aim of the present work is to introduce a thermodynamic model to describe the growth of an oxide layer on a metallic substrate. More precisely, this paper offers a study of oxy…