Author Information

Xavier Averty

Affiliation: CEA-Saclay

Division/Department: DEN/DMN/SEMI

Address:
Gif-sur-Yvette, 91191
France

Other Names:
X. Averty

Publications


Behavior of Different Austenitic Stainless Steels, Conventional, Reduced Activation (RA) and ODS Chromium-Rich Ferritic-Martensitic Steels Under Neutron Irradiation at 325°C in PWR Environment

STP10553S
X. Averty
Commissariat à l'Energie Atomique, CEA-Saclay


Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior

JAI12465
Xavier Averty
CEA-Saclay


Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior

STP37538S
Xavier Averty
CEA-Saclay


Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels after Thermal Aging and Neutron Irradiation

STP10564S
Xavier Averty
DRN/DRE/Service d'Etudes des Matéfiaux Irradiés


Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa

STP37569S
Xavier Averty
CEA-Saclay


Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa

JAI12354
Xavier Averty
CEA-Saclay


Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening

STP37573S
Xavier Averty
CEA-Saclay


Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening

JAI12381
Xavier Averty
DEN/SEMI, Commissariat à l'Energie Atomique, CEA-Saclay


StockCodeTitlePublished AsAffiliationPub Date by Most Viewed
STP10553S Behavior of Different Austenitic Stainless Steels, Conventional, Reduced Activation (RA) and ODS Chromium-Rich Ferritic-Martensitic Steels Under Neutron Irradiation at 325°C in PWR Environment X. Averty Commissariat à l'Energie Atomique, CEA-Saclay 01 January 2001
JAI12465 Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior Xavier Averty CEA-Saclay 01 June 2005
STP37538S Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior Xavier Averty CEA-Saclay 01 January 2005
STP10564S Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels after Thermal Aging and Neutron Irradiation Xavier Averty DRN/DRE/Service d'Etudes des Matéfiaux Irradiés 01 January 2001
STP37569S Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa Xavier Averty CEA-Saclay 01 January 2006
JAI12354 Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa Xavier Averty CEA-Saclay 22 June 2005
STP37573S Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening Xavier Averty CEA-Saclay 01 January 2006
JAI12381 Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening Xavier Averty DEN/SEMI, Commissariat à l'Energie Atomique, CEA-Saclay 00 October 2005