Zirconium-based claddings with an outer chromium coating resistant to corrosion are studied and
developed as an evolutionary Enhanced Accident Tolerant Fuel (E-ATF) concept for light water reactors.
However, in hypothetical LOss-of-Coolant-Accident (LOCA) conditions, following clad ballooning and
burst, the outer coating does not allow to protect the inner surface of the cladding from High Temperature
(HT) steam oxidation and associated secondary hydriding due to steam starvation occurring within the
gap between the clad inner surface and the nuclear fuel pellets.