Early studies on Cr-Coated Zircaloy-4 as Enhanced Accident Tolerant Nuclear Fuel Claddings for Light Water Reactors, 2019. ,
URL : https://hal.archives-ouvertes.fr/hal-02090215
AREVA NP's Enhanced Accident Tolerant Fuel Developments: Focus on Cr-coated M5 Cladding, Nuclear Engineering and Technology, vol.50, pp.223-2283, 2018. ,
Mechanical behavior at Room Temperature and Metallurgical study of Low-Tin Zy-4 and M5? alloys after oxidation at 1100°C and quenching, 2001. ,
Raman investigation of pre-and post-breakaway oxide scales formed on Zircaloy-4 and M5R in air at high temperature, Journal of Nuclear Mat, pp.421-160, 2012. ,