Zirconium alloys have been widely used as fuel cladding materials for light water reactors (LWRs) because of their very low absorption cross-section for thermal neutron, good mechanical properties, and corrosion resistance under normal LWR operating conditions. The Fukushima Daiichi accident in 2011 revealed the limitation of Zr-alloys in accident scenarios where high temperature steam oxidation led to generation of heat and hydrogen, and destruction of the reactor core. In response to this accident, the nuclear community is considering several approaches such as to develop accident tolerant fuel (ATF) cladding designs that have superior oxidation resistance at high temperatures. ATF cladding materials are studied into two different categories: application of coatings to Zircaloy cladding (near-term technologies) and development of non-Zircaloy monolithic alternative materials (longer-term technologies). A number of studies have demonstrated that ceramic coatings such as, SiC, TiAlCrN, CrN and metallic coating such as, FeCrAl and Cr have excellent resistance to oxidation at higher temperature.