Marc Tupin

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

Differences in reactivity of oxide growth during the oxidation of Zircaloy-4 in water vapour before and after the kinetic transition

Marc Tupin, M. Pijolat, F. Valdivieso et al. · Journal of Nuclear Materials · 2003 · 77 citations

Oxygen Reduction Reaction, Advanced Oxidation Process, Chemical Engineering +9

ASSESSMENT AT CEA OF COATED NUCLEAR FUEL CLADDING FOR LWRS WITH INCREASED MARGINS IN LOCA AND BEYOND LOCA CONDITIONS

Isabel Idarraga-Trujillo, Marion Le Flem, Jean-Christophe Brachet et al. · 2013 · 48 citations

Materials Science, Nuclear Reactors, Engineering +1

Mechanism of corrosion of zirconium hydride and impact of precipitated hydrides on the Zircaloy-4 corrosion behaviour

Marc Tupin, Caroline Bisor, Philippe Bossis et al. · Corrosion Science · 2015 · 46 citations

Materials Science, Chemical Engineering, Corrosion Protection +8

Hydrogen diffusion process in the oxides formed on zirconium alloys during corrosion in pressurized water reactor conditions

Marc Tupin, F.A. Martin, Caroline Bisor et al. · Corrosion Science · 2016 · 45 citations · Full text

Materials Science, Chemical Engineering, Engineering +6