M.-L. Lescoat - Concepedia

Author

M.-L. Lescoat

Centre National de la Recherche Scientifique

Also Known As

M-L. Lescoat, M.-L. Lescoat, M.L. Lescoat

Publications

440

Citations

H-Index

Concepts

All Affiliations

Centre National de la Recherche Scientifique Commissariat à l'Énergie Atomique et aux Énergies Alternatives Direction des Energies Université de Lille Université Paris-Sud

About

M.-L. Lescoat is an author at Centre National de la Recherche Scientifique specializing in engineering, materials science, and microstructure.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	9	9	412
2	Applied Physics	5	5	314
3	Materials Engineering	4	4	127
4	Chemical Engineering	1	1	24
5	Electrical Engineering	1	1	20

M.-L. Lescoat

Publications

412

Citations

H-Index

Page 1

	Year	Citations
Radiation-induced Ostwald ripening in oxide dispersion strengthened ferritic steels irradiated at high ion dose M.-L. Lescoat, J. Ribis, Y. Chen, Acta Materialia Materials ScienceEngineeringApplied PhysicsHigh Strength Low Alloy SteelRadiation Application	2014	132
In situ TEM study of the stability of nano-oxides in ODS steels under ion-irradiation M.-L. Lescoat, J. Ribis, A. Gentils, Journal of Nuclear Materials Materials ScienceEngineeringCorrosionOxidation ResistanceOxide Electronics	2011	75
Influence of the low interfacial density energy on the coarsening resistivity of the nano-oxide particles in Ti-added ODS material J. Ribis, M.-L. Lescoat, Shengyi Zhong, Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringNanoscale ChemistryMaterial Property	2012	48
Amorphization of oxides in ODS materials under low and high energy ion irradiations M.-L. Lescoat, I. Monnet, J. Ribis, Journal of Nuclear Materials Materials EngineeringMaterials ScienceIon ImplantationEngineeringOxidation Resistance	2011	34
TEM study of the nucleation of bubbles induced by He implantation in 316L industrial austenitic stainless steel S. Jublot-Leclerc, M.-L. Lescoat, F. Fortuna, Journal of Nuclear Materials Materials ScienceBubble DynamicEngineeringCorrosionHydrodynamic Cavitation	2015	32
Microstructure of Au-ion irradiated 316L and FeNiCr austenitic stainless steels S. Jublot-Leclerc, X. Li, L. Legras, Journal of Nuclear Materials Materials ScienceMaterials EngineeringIon ImplantationEngineeringApplied Physics	2016	25
Application of synchrotron radiation to analyze the precipitation in ODS materials before irradiation in Fe–9%Cr single grain of powder and consolidated Fe–18%Cr Jean-Luc Béchade, Denis Menut, M.-L. Lescoat, Journal of Nuclear Materials Materials ScienceNuclear CeramicChemical EngineeringEngineeringPowder Metallurgy	2011	24
Modeling of helium bubble nucleation and growth in austenitic stainless steels using an Object Kinetic Monte Carlo method A. De Backer, Gilles Adjanor, Christophe Domain, Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms Bubble DynamicEngineeringPhysicsCorrosionMonte Carlo	2014	22
Amorphization of oxides in ODS steels/materials by electronic stopping power I. Monnet, C. Grygiel, M.-L. Lescoat, Journal of Nuclear Materials Materials EngineeringMaterials ScienceElectrical EngineeringEngineeringOxidation Resistance	2012	20

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