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Service d'étude des matériaux irradiés - DES/ISAS/DMN

Les 20 dernières publications

Titre Auteurs Date de publication Source
Modeling size effects in microwire torsion: A comparison between a Lagrange multiplier-based and a CurlF<sup>p</sup> gradient crystal plasticity model Jean–Michel –M Scherer 01/07/2022 European Journal of Mechanics, A/Solids
A micromechanical analysis of swelling-induced embrittlement in neutron-irradiated austenitic stainless steels J. Hure, A. Courcelle, I. Turque 01/07/2022 Journal of Nuclear Materials
Micromorphic crystal plasticity approach to damage regularization and size effects in martensitic steels Jean–Michel –M Scherer 01/04/2022 International Journal of Plasticity
Interactions of hydrogen with zirconium alloying elements and oxygen vacancies in monoclinic zirconia M. Tupin 15/02/2022 Acta Materialia
Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature A. Courcelle 01/01/2022 Journal of Nuclear Materials
Impact of the microstructure on the swelling of aluminum alloys: Characterization and modelling bases Victor Garric, Kimberly Colas, Véronique Cloute-Cazalaa, Bénédicte Kapusta 15/12/2021 Journal of Nuclear Materials
Rate-limiting step of the deuterium desorption kinetics from Zircaloy-4 oxidized in PWR light primary water C. Juillet, Frantz Martin, Q. Auzoux 18/11/2021 International Journal of Hydrogen Energy
A strain gradient plasticity model of porous single crystal ductile fracture Jean–Michel –M Scherer, J. Hure, Benoît Tanguy 01/11/2021 Journal of the Mechanics and Physics of Solids
The effect of strain biaxiality on the fracture of zirconium alloy fuel cladding A. Zouari, Matthew Bono, David Le Boulch, Thomas Le Jolu 01/10/2021 Journal of Nuclear Materials
Impact of ion and neutron irradiation on the corrosion of the 6061-T6 aluminium alloy Sarah L'haridon Quaireau, Kimberly Colas, Bénédicte Kapusta, Bénédicte Verhaeghe 01/09/2021 Journal of Nuclear Materials
A single grain boundary parameter to characterize normal stress fluctuations in materials with elastic cubic grains J. Hure 01/08/2021 European Journal of Mechanics, A/Solids
Kinetics of deuterium permeation through Zircaloy-4 in the 623–773 K temperature range M. Tupin 26/07/2021 International Journal of Hydrogen Energy
Effect of the precipitates on the hydrogen desorption kinetics from zirconium-niobium alloys M. Tupin 11/02/2021 International Journal of Hydrogen Energy
Mechanical and microstructural analysis of an EM10 wrapper tube after neutron irradiation in Phénix P. Gavoille, Bénédicte Verhaeghe 01/01/2021 Journal of Nuclear Materials
Lagrange multiplier based vs micromorphic gradient-enhanced rate-(in)dependent crystal plasticity modelling and simulation Jean–Michel –M Scherer, J. Hure, Benoît Tanguy 01/12/2020 Computer Methods in Applied Mechanics and Engineering
Polycrystalline modeling of the behavior of neutron-irradiated recrystallized zirconium alloys during strain path change tests Matthew Bono, Bénédicte Verhaeghe 01/11/2020 International Journal of Plasticity
Phase transformations during cooling from the β<inf>Zr</inf> phase temperature domain in several hydrogen-enriched zirconium alloys studied by in situ and ex situ neutron diffraction I. Turque 15/10/2020 Acta Materialia
Ab-initio calculations of hydrogen diffusion coefficient in monoclinic zirconia M. Tupin 01/10/2020 Journal of Nuclear Materials
Effects of temperature and pH on uniform and pitting corrosion of aluminium alloy 6061-T6 and characterisation of the hydroxide layers Sarah L'haridon Quaireau, Mathilde Laot, Kimberly Colas, Bénédicte Kapusta 25/08/2020 Journal of Alloys and Compounds
Effect of a pre-oxidation on the hydrogen desorption from Zircaloy-4 M. Tupin 15/08/2020 Corrosion Science

Nombre de publications du laboratoire par domaine scientifique (2016-2021)

Chaque publication du laboratoire peut être rangée dans une ou plusieurs disciplines scientifiques : la figure ci-dessus présente le nombre de publications du laboratoire pour chaque discipline de la classification ASJC (Elsevier)