Abstract: The invention presented herein relates to a zirconium alloy with superior corrosion resistance and high strength for use in fuel rod claddings, spacer grids and structural components in reactor core of light water and heavy water nuclear power plant. The zirconium alloy of this invention with superior corrosion resistance and high strength comprises an alloy composition as follows: niobium in a range of 0.15 to 0.25 wt. %; tin in a range of 1.10 to 1.40 wt. %; iron in a range of 0.35 to 0.45; chromium in a range of 0.15 to 0.25; one element selected from the group consisting of molybdenum, copper and manganese in a range of 0.08 to 0.12 wt. %; oxygen in a range of 0.10 to 0.14 wt. %; and the balance being zirconium.

Abstract: The present invention is directed to an advanced zirconium alloy having superior corrosion resistance and high strength suitable for fuel rod cladding, spacer grids and other structural components in a reactor core of nuclear power plants.

Abstract: The invention presented herein relates to a zirconium alloy with superior corrosion resistance and high strength for use in fuel rod claddings, spacer grids and structural components as used in reactor core of light water and heavy water nuclear power plant. The zirconium alloy of this invention with superior corrosion resistance and high strength comprises an alloy composition as follows:niobium(Nb), in a range of 0.05 to 0.3 wt. %;tin(Sn), in a range of 0.8 to 1.6 wt. %;iron(Fe), in a range of 0.2 to 0.4 wt. %;a selected one from the group consisted of vanadium(V), tellurium(Te), antimony(Sb), molybdenum(Mo), tantalum(Ta), and copper(Cu), in a range of 0.05 to 0.20 wt. %;oxygen(O), in a range of 600 to 1400 ppm; andthe balance being zirconium(Zr).