International audienceThis work presents an experimental characterization of uranium dioxide (UO2) in compression under Reactivity Initiated Accident (RIA) conditions. Pellet samples were tested at four temperatures (1100, 1350, 1550 and 1700°C) and at a strain rate varying over 4 decades (10-4–10-3–10-2–10-110-4–10-3–10-2–10-1/s). The experimental results show that the stress–strain curves cannot be fitted with a unique power law as it is the case at smaller strain rates (10-9–10-510-9–10-5/s). A strain-hardening also appears in most of the tests. The microstructural observations show a pronounced evolution of the porosity at the pellet center during the tests. A hyperbolic sine model which accounts for volume variations (pore compressibil...
International audienceUranium dioxide (UO2) is a polycrystalline ceramic used as nuclear fuel within...
Le dioxyde d'uranium (UO2) est le combustible de référence pour les réacteurs nucléaires à eau press...
Modelling of UO2 mechanical behavior requires detailed knowledge of the local stresses and strains d...
International audienceThis work presents an experimental characterization of uranium dioxide (UO2) i...
International audienceIn this paper, the behavior of a dense UO2 (porosity less than 2%) was studied...
L'objectif de ce travail est de caractériser et de modéliser le comportement mécanique des oxydes d'...
International audienceControlling and predicting the high temperature mechanical behaviour of nuclea...
In an effort to increase the understanding of the mechanical properties of UO2 small scale mechanica...
International audienceThe aim of this work is to study the role of the intra-granular voids, on the ...
International audienceSintered UO2 pellets with relatively large grains (similar to 25 pm) are teste...
International audienceFour batches of UO2 pellets were studied comparatively, before and after creep...
International audienceStoichiometric uranium dioxide (UO2) pellets were deformed by uniaxial compres...
National audienceThis numerical study presents a micromechanical modelling of uranium dioxide, a pol...
International audienceUranium dioxide (UO2) is a polycrystalline ceramic used as nuclear fuel within...
Le dioxyde d'uranium (UO2) est le combustible de référence pour les réacteurs nucléaires à eau press...
Modelling of UO2 mechanical behavior requires detailed knowledge of the local stresses and strains d...
International audienceThis work presents an experimental characterization of uranium dioxide (UO2) i...
International audienceIn this paper, the behavior of a dense UO2 (porosity less than 2%) was studied...
L'objectif de ce travail est de caractériser et de modéliser le comportement mécanique des oxydes d'...
International audienceControlling and predicting the high temperature mechanical behaviour of nuclea...
In an effort to increase the understanding of the mechanical properties of UO2 small scale mechanica...
International audienceThe aim of this work is to study the role of the intra-granular voids, on the ...
International audienceSintered UO2 pellets with relatively large grains (similar to 25 pm) are teste...
International audienceFour batches of UO2 pellets were studied comparatively, before and after creep...
International audienceStoichiometric uranium dioxide (UO2) pellets were deformed by uniaxial compres...
National audienceThis numerical study presents a micromechanical modelling of uranium dioxide, a pol...
International audienceUranium dioxide (UO2) is a polycrystalline ceramic used as nuclear fuel within...
Le dioxyde d'uranium (UO2) est le combustible de référence pour les réacteurs nucléaires à eau press...
Modelling of UO2 mechanical behavior requires detailed knowledge of the local stresses and strains d...