Stéphane Urvoy

Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

Jean-Christophe Brachet, Isabel Idarraga-Trujillo, Marion Le Flem et al. · Journal of Nuclear Materials · 2019 · 381 citations

Engineering, Materials Science, Nuclear Engineering +14

High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process

Jean-Christophe Brachet, Elodie Rouesne, J. Ribis et al. · Corrosion Science · 2020 · 374 citations · Full text

Natural Sciences, Materials Engineering, Materials Science +13

Understanding sigma-phase precipitation in a stabilized austenitic stainless steel (316Nb) through complementary CALPHAD-based and experimental investigations

Aurélien Perron, Caroline Toffolon-Masclet, Xavier Ledoux et al. · Acta Materialia · 2014 · 78 citations

Natural Sciences, Materials Engineering, Materials Science +15

Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200 °C in relation with oxygen diffusion/partitioning and post-quench ductility

Jean-Christophe Brachet, Matthieu Le Saux, Jeffrey E. Bischoff et al. · Journal of Nuclear Materials · 2020 · 72 citations · Full text

Natural Sciences, Materials Engineering, Materials Science +16

Microstructure and thermal conductivity of Mo–TiC cermets processed by hot isostatic pressing

Marion Le Flem, Alexandre Allemand, Stéphane Urvoy et al. · Journal of Nuclear Materials · 2008 · 51 citations

Engineering, Materials Engineering, Materials Science +16