D. Drouan

Reaction in air and in nitrogen of pre-oxidised Zircaloy-4 and M5™ claddings

Christian Duriez, D. Drouan, G. Pouzadoux · Journal of Nuclear Materials · 2013 · 60 citations

Materials Science, Chemical Engineering, Engineering +6

Influence of temperature and hydrogen content on stress-induced radial hydride precipitation in Zircaloy-4 cladding

J. Desquines, D. Drouan, M.C. Billone et al. · Journal of Nuclear Materials · 2014 · 45 citations

Materials Science, Zircaloy-4 Cladding, Engineering +7

Investigation on boron carbide oxidation for nuclear reactor safety: Experiments in highly oxidising conditions

N. Cocuaud, D. Drouan, A. Constant et al. · Journal of Nuclear Materials · 2007 · 39 citations

Materials Science, Chemical Engineering, Engineering +10

Extended defect change in UO2 during in situ TEM annealing

C. Onofri, C. Sabathier, Cédric Baumier et al. · Acta Materialia · 2020 · 33 citations · Full text

Materials Engineering, Materials Science, Nuclear Ceramic +8

Embrittlement of pre-hydrided Zircaloy-4 by steam oxidation under simulated LOCA transients

J. Desquines, D. Drouan, S. Guilbert et al. · Journal of Nuclear Materials · 2015 · 24 citations

Materials Science, Chemical Engineering, Industrial Chemistry +8