Jean-Christophe Brachet

AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding

E. Schweitzer, F. Schuster, J. Brachet, 2018 .

Quantification and local distribution of hydrogen within Zircaloy-4 PWR nuclear fuel cladding tubes at the nuclear microprobe of the Pierre Süe Laboratory from μ-ERDA

D. Hamon, J. Béchade, C. Raepsaet, 2008 .

Effect of a pre-oxide on the high temperature steam oxidation of Zircaloy-4 and M5Framatome alloys

S. Urvoy, J. Brachet, M. L. Saux, 2019, Journal of Nuclear Materials.

“Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe

C. Toffolon-Masclet, S. Urvoy, J. Lacour, 2017 .

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

R. Boichot, M. Pons, F. Lomello, 2018, Surface and Coatings Technology.

An approach to study oxidation-induced stresses in Zr alloys oxidized at high temperature

T. Guilbert, J. Brachet, M. L. Saux, 2018, Corrosion Science.