X. Averty - Concepedia

Concepedia

Author

X. Averty

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Also Known As

Averty, X., Averty, Xavier, X Averty, X. Averty, Xavier Averty

33

Publications

1.2K

Citations

18

H-Index

24

Concepts

All Affiliations

Commissariat à l'Énergie Atomique et aux Énergies Alternatives CEA Paris-Saclay Direction des Energies Centre National de la Recherche Scientifique Paul Scherrer Institute

XA

About

X. Averty is an author at Commissariat à l'Énergie Atomique et aux Énergies Alternatives specializing in materials science, engineering, and mechanical engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	17	20	1.1K
2	Materials Science	17	20	1.1K
3	Mechanical Engineering	14	16	645
4	Materials Engineering	5	5	318
5	Chemistry	1	1	220

X. Averty

×

22

Publications

1.2K

Citations

18

H-Index

	Year	Citations
A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels M.H. Mathon, Y. de Carlan, G. Geoffroy, Journal of Nuclear Materials Materials ScienceEngineeringSans InvestigationHigh Strength Low Alloy SteelCr Martensitic Steels	2003	220
Assessment of ODS-14%Cr ferritic alloy for high temperature applications Jesús A. del Alamo, V Lambard, X. Averty, Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringCorrosionHigh Temperature Applications	2004	173
Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part II: Irradiation induced hardening C. Pokor, Y. Bréchet, Philippe Dubuisson, Journal of Nuclear Materials Materials ScienceDamage MechanismEngineeringExperimental InvestigationCorrosion	2004	94
Behavior and failure of uniformly hydrided Zircaloy-4 fuel claddings between 25°C and 480°C under various stress states, including RIA loading conditions Matthieu Le Saux, Jacques Besson, S. Carassou, Engineering Failure Analysis Materials ScienceMaterials EngineeringHigh Temperature MaterialsEngineeringRia Loading Conditions	2009	80
Neutron/proton irradiation and He effects on the microstructure and mechanical properties of ferritic/martensitic steels T91 and EM10 Yong Dai, J. Henry, Zhao Tong, Journal of Nuclear Materials Materials ScienceNeutron/proton IrradiationEngineeringMechanical PropertiesMechanical Engineering	2011	77
Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325°C up to 78dpa J. Henry, X. Averty, Jesús A. del Alamo Journal of Nuclear Materials Materials ScienceEngineeringFast ReactorMechanical EngineeringAlloy Design	2010	60
The PROMETRA Program: Fuel Cladding Mechanical Behavior under High Strain Rate B. Cazalis, J. Desquines, C. Poussard, Nuclear Technology	2007	54
High dose, up to 80 dpa, mechanical properties of Eurofer 97 B. van der Schaaf, C. Petersen, Y. de Carlan, Journal of Nuclear Materials Materials ScienceEngineeringMechanical PropertiesHigh DoseMechanical Engineering	2009	50
A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditions Matthieu Le Saux, Jacques Besson, S. Carassou, Journal of Nuclear Materials Materials ScienceEngineeringRia Loading ConditionsMechanical BehaviorMechanical Engineering	2008	47
Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250–450°C Jesús A. del Alamo, M.G. Horsten, X. Averty, Journal of Nuclear Materials Materials ScienceEngineeringMechanical BehaviorConventional Martensitic SteelsRange 250–450°C	2000	44

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