Zirconium alloys with improved corrosion/creep resistance due to final heat treatments

A method of making a zirconium based alloy article which exhibits one of improved corrosion resistance and improved creep resistance for use in an elevated temperature environment of a nuclear reactor, comprising the steps:

• (a) combining
• 0.4 to 1.5 weight percent niobium,
• 0.4 to 0.8 weight percent tin,
• 0.05 to 0.3 weight percent iron,
• 0.0 to 0.5 weight percent chromium, and
• the balance at least 97 weight percent zirconium including impurities to provide an alloy mixture;
• (b) melting the alloy mixture to produce a melted alloy material;
• (c) forging the melted alloy material to produce a forged alloy material;
• (d) quenching the forged alloy material to produce a quenched alloy material;
• (e) rolling the quenched alloy material to produce a rolled alloy material;
• (f) annealing the rolled alloy material to produce an annealed alloy material;
• (g) following completion of steps (b), (c), (d), (e) and (f), subjecting the annealed alloy material to a final heat treatment selected to provide a zirconium-based alloy exhibiting one of improved corrosion resistance and improved creep resistance,
• wherein for providing the zirconium-based alloy exhibiting improved corrosion resistance, the annealed alloy material is subjected to a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 15% to 20% with the remainder being stress relief annealed, and
• wherein for providing the zirconium-based alloy exhibiting improved creep resistance, the annealed alloy material is subjected to a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 80% to 95% recrystallization with the remainder being stress relief annealed.