Zirconium alloy for nuclear reactor cladding material

The invention discloses a zirconium alloy for a nuclear reactor cladding material. The zirconium alloy is composed of following compositions including 0.2% to 0.6% of Sn, 0.1% to 0.4% of Nb, 0.35% to 0.65% of Fe, 0.1% to 0.3% of Cr, 0.05% to 0.25% of Mo, 0% to 0.4% of Ge or Bi or V, 0% to 0.25% of Mn or Cu, 0.06% to 0.15% of O, less than 0.008% of C, less than 0.006% of N and the balance Zr and impurities. On the basis of a Zr-Sn-Nb alloy, other compositions for improving the alloy performance are added, the proper component content is selected, and the performance of the provided alloy meets the requirement of nuclear power reactor high burnup for a reactor core structure. Uniform corrosion resistance of a product prepared from the prototype alloy in out-of-reactor pure water and a lithium hydroxide aqueous solution is improved, and nodular corrosion resistance of the product in high-temperature steam is improved.