V. Chabretou

发表

Simulation of C-Ring, O-Ring and tensile ring specimens for Iodine induced Stress Corrosion Cracking experiments on zirconium alloy

Martin, N. Mozzani, K. Wilczyńska, 2018 .

CASTA DIVA ® : Experiments and Modeling of Oxide-Induced Deformation in Nuclear Components

P. Barbéris, J. Vermoyal, V. Chabretou, 2008 .

REFLET Experiment in OSIRIS: Relaxation under Flux as a Method for Determining Creep Behavior of Zircaloy Assembly Components

F. Rozenblum, S. Dean, S. Carassou, 2010 .

Thermal Creep Model for CWSR Zircaloy-4 Cladding Taking into Account the Annealing of the Irradiation Hardening

C. Cappelaere, V. Chabretou, P. Bouffioux, 2012 .

Impact of Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys

F. Onimus, C. Cappelaere, V. Chabretou, 2010 .

Microstructural Evolution of Q12TM Alloy Irradiated in PWRs and Comparison with Other Zr Base Alloys

A. Ambard, S. Doriot, V. Chabretou, 2018 .

Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties

S. Trapp-Pritsching, P. Barbéris, J. Vermoyal, 2011 .

In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5® and Recrystallized Low-Tin Zircaloy-4

S. Doriot, V. Chabretou, D. Gilbon, 2009 .

Quantitative analysis of the effect of the binder phase composition on grain growth in WC-Co sintered materials

J. Missiaen, C. Allibert, V. Chabretou, 2003 .

Quantitative evaluation of normal and abnormal grain growth of cemented carbides during liquid phase sintering

J. Missiaen, C. Allibert, O. Lavergne, 1999 .