The current status of zirconium alloys fuel cladding

Abstract

Properties such as corrosion and radiation resistance of zirconium alloys fuel claddings for nuclear reactors and ways to improve them are considered. The need to ensure high radiation and corrosion resistance and reliability of fuel claddings for the safe operation of pressurized water reactors of NPPs under operating conditions is substantiated. The use of sponge zirconium as the base of the alloys provides safety criteria under LOCA conditions. Optimization of the Fe content in the Zr-1%Nb alloy leads to increased corrosion resistance in the coolant and resistance to radiation growth during irradiation.