C. Sabathier

Commissariat à l'Énergie Atomique et aux Énergies Alternatives — France

Materials Science · Physical Sciences

21h-index961citations49works6.72yr avg
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Research Topics

Nuclear Materials and Properties(43), Radioactive element chemistry and processing(24), Nuclear materials and radiation effects(23), Nuclear reactor physics and engineering(20), Fusion materials and technologies(14)

Publications49 total

Experimental characterizations by EBSD and TEM of sub-grain boundaries and dislocations in low irradiated UO2 fuels
Journal of Nuclear Materials·2025· 2 citedOpen Access
Accurate quantification of dislocation loops in complex functional alloys enabled by deep learning image analysis
Scientific Reports·2024· 9 citedOpen Access
Versatility of dislocation motions in polycrystalline UO2 deformed at 1550 °C investigated by TEM
Scripta Materialia·2024· 9 citedOpen Access
Fission products at the fuel-cladding interface of PWR fuel rods: morphological and chemical study
Journal of Nuclear Materials·2023· 5 cited
Electron inelastic mean free path in UO2 and (U, Pu)O2 fuels
Acta Materialia·2023· 7 cited
Characterization by electron probe microanalysis, Raman spectroscopy and transmission electron microscopy of a MOX fuel sintered from a freeze-granulated powder
Journal of the European Ceramic Society·2022· 4 cited
Electron Inelastic Mean Free Path in UO2 and (U, Pu)O2 Fuels
SSRN Electronic Journal·2022· 1 citedOpen Access
Microstructural characteristics of a fresh U(Mo) monolithic mini-plate: Focus on the Zr coating deposited by PVD
Nuclear Engineering and Technology·2021· 6 citedOpen Access
Extended defect change in UO2 during in situ TEM annealing
Acta Materialia·2020· 33 citedOpen Access
Changes in voids induced by ion irradiations in UO2: In situ TEM studies
Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms·2019· 24 cited
TEM characterisation of helium platelets in implanted uranium dioxide
Journal of Nuclear Materials·2019· 3 cited
On the origins and the evolution of the fuel-cladding bonding phenomenon in PWR fuel rods
Journal of Nuclear Materials·2019· 18 citedOpen Access
Influence of exogenous xenon atoms on the evolution kinetics of extended defects in polycrystalline UO2 using in situ TEM
Journal of Nuclear Materials·2018· 22 cited
Outcomes of the PELGRIMM project on Am-bearing fuel in pelletized and spherepac forms
Journal of Nuclear Materials·2018· 17 citedOpen Access
Atomic scale simulations provide insights on swelling induced by irradiations
HAL (Le Centre pour la Communication Scientifique Directe)·2018
Full characterization of dislocations in ion-irradiated polycrystalline UO2
Journal of Nuclear Materials·2017· 40 cited
Early stages of irradiation induced dislocations in urania
Applied Physics Letters·2016· 59 cited
Evolution of extended defects in polycrystalline Au-irradiated UO 2 using in situ TEM: Temperature and fluence effects
Journal of Nuclear Materials·2016· 36 cited
Strain relaxation in He implanted UO2 polycrystals under thermal treatment: An in situ XRD study
Journal of Nuclear Materials·2016· 8 citedOpen Access
Study of Rare Gases Behavior in Uranium Dioxide
EPJ Web of Conferences·2016· 1 citedOpen Access
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Frequent Co-authors

Philippe Garcia(17), G. Carlot(17), C. Onofri(15), Guillaume Martin(13), H. Palancher(10), P. Martín(9), D. Drouan(9), Serge Maillard(8), C. Valot(8), M. Legros(6), C. Bachelet(6), Marjorie Bertolus(5), Cédric Baumier(5), J. Chaumont(5), P. Desgardin(5), Thierry Sauvage(5), A. Michel(4), Olivier Proux(4), Michel Freyss(4), W. Petry(4)