Contributions of thermokinetic calculations to the understanding of the microstructural evolutions of E-ATF Cr Coated Zr-based nuclear fuel claddings upon high temperature transients

Abstract

International audienceChromium coated zirconium based nuclear fuel claddings are among the most promising evolutive concepts in the field of Enhanced Accident Tolerant Fuel (EATF) developments [1-2]. The development of these new claddings has been accelerated since 2011 and the Fukushima-DAICHI nuclear accident. Among some other objectives, one of the main ideas is to develop new concepts of nuclear fuel claddings able to delay the High Temperature (HT) steam oxidation kinetics and the associated hydrogen production (explosion risk) and to improve the resultant Post-Quenching (PQ) cladding strength and ductility upon and following hypothetical accident conditions such as Loss-of-Coolant-Accident (LOCA). In this context, Cr-coated Zr based alloys, with 10-20µm thick Cr coating (PVD deposition), show promising behaviour