Matthieu Le Saux

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 · 369 citations

Materials Science, Nuclear Ceramic, Chemical Engineering +7

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 · 353 citations · Full text

Materials Science, Materials Engineering, Chemical Engineering +6

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 et al. · Engineering Failure Analysis · 2009 · 80 citations

Materials Science, Materials Engineering, High Temperature Materials +7

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

Materials Science, Chemical Engineering, Engineering +9

High-temperature oxidation resistance of chromium-based coatings deposited by DLI-MOCVD for enhanced protection of the inner surface of long tubes

Alexandre Michau, F. Maury, Frédéric Schuster et al. · Surface and Coatings Technology · 2018 · 61 citations · Full text

Materials Engineering, Materials Science, Chemical Engineering +13