Patent Number: 
Section: claims

1. A zirconium-based alloy having one of improved corrosion resistance and improved creep resistance, for use in an elevated temperature environment of a nuclear reactor, comprising an alloying composition:0.2 to 1.5 weight percent niobium;0.01 to 0.6 weight percent iron;0.0 to 0.8 weight percent tin;0.0 to 0.5 weight percent chromium;0.0 to 0.3 weight percent copper;0.0 to 0.3 weight percent vanadium;0.0 to 0.1 weight percent nickel; anda balance at least 97 weight percent zirconium, including impurities, the zirconium-based alloy formed by a process, comprising:(a) melting the alloying composition to produce a melted alloy material;(b) forging the melted alloy material to produce a forged alloy material;(c) quenching the forged alloy material to produce a quenched alloy material;(d) extruding the quenched alloy material to produce a tube-shell alloy material;(e) pilgering the tube-shell alloy material to produce a reduced tube-shell alloy material;(f) annealing the reduced tube-shell alloy material to produce an annealed alloy material;(g) repeating steps (e) and (f) to produce a final alloy material; and(h) subjecting the final alloy material to a final heat treatment selected to provide the 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 final alloy material is subjected to a final heat treatment selected from a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 15% to about 20% with the remainder being stress relief annealed or a final heat treatment of stress relief annealed, andwherein for providing the zirconium-based alloy exhibiting improved creep resistance, the final alloy material is subjected to a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 80% to about 95% recrystallization with the remainder being stress relief annealed. 2. The zirconium-based alloy of claim 1, wherein said alloy is formed into an article. 3. The zirconium-based alloy of claim 2, wherein said article is selected from the group consisting of cladding. 4. The zirconium-based alloy of claim 1, wherein the alloy comprises:0.6 to 1.5 weight percent niobium;0.01 to 0.1 weight percent iron;0.15 to 0.35 weight percent chromium;0.02 to 0.3 weight percent copper; anda balance at least 97 weight percent zirconium, including impurities. 5. The zirconium-based alloy of claim 1, wherein the alloy comprises:0.2 to 1.5 weight percent niobium;0.25 to 0.45 weight percent iron;0.05 to 0.4 weight percent tin;0.15 to 0.35 weight percent chromium;0.01 to 0.1 weight percent nickel; anda balance at least 97 weight percent zirconium, including impurities. 6. The zirconium-based alloy of claim 1, wherein the alloy comprises:0.4 to 1.5 weight percent niobium;0.01 to 0.1 weight percent iron;0.05 to 0.4 weight percent tin;0.0 to 0.5 weight percent chromium;0.02 to 0.3 weight percent copper;0.12 to 0.3 weight percent vanadium; anda balance at least 97 weight percent zirconium, including impurities. 7. The zirconium-based alloy of claim 6, wherein the chromium is present in an amount from 0.05 to 0.5. 8. The zirconium-based alloy of claim 1, wherein the alloy comprises:0.4 to 1.5 weight percent niobium;0.01 to 0.6 weight percent iron;0.1 to 0.8 weight percent tin;0.0 to 0.5 weight percent chromium; anda balance at least 97 weight percent zirconium, including impurities. 9. The zirconium-based alloy of claim 8, wherein the chromium is present in an amount from 0.05 to 0.5. 10. A method of making a zirconium-based alloy 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:0.2 to 1.5 weight percent niobium;0.01 to 0.6 weight percent iron;0.0 to 0.8 weight percent tin;0.0 to 0.5 weight percent chromium;0.0 to 0.3 weight percent copper;0.0 to 0.3 weight percent vanadium;0.0 to 0.1 weight percent nickel; anda 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) extruding the quenched alloy material to produce a tube-shell alloy material;(f) pilgering the tube-shell alloy material to produce a reduced tube-shell alloy material;(g) annealing the tube-shell alloy material to produce an annealed alloy material;(h) repeating steps (f) and (g) to produce a final alloy material; and(i) subjecting the final 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 final alloy material is subjected to a final heat treatment selected from 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 or a final heat treatment of stress relief annealed, andwherein for providing the zirconium-based alloy exhibiting improved creep resistance, the final 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. 11. The method of making the zirconium-based alloy of claim 10, wherein said method further comprises forming the alloy into an article. 12. The zirconium-based alloy of claim 11, wherein said article is selected from the group consisting of cladding. 13. The method of making the zirconium-based alloy of claim 10, wherein the annealing is conducted at a temperature from about 960 to 1105° F. 14. The method of making the zirconium-based alloy of claim 13, wherein the annealing is conducted at a temperature from about 1030 to 1070° F. 15. A zirconium-based alloy for use in an elevated temperature environment of a nuclear reactor, comprising an alloying composition:0.2 to 1.5 weight percent niobium;0.01 to 0.6 weight percent iron;0.0 to 0.8 weight percent tin;0.0 to 0.5 weight percent chromium;0.0 to 0.3 weight percent copper;0.0 to 0.3 weight percent vanadium;0.0 to 0.1 weight percent nickel; anda balance at least 97 weight percent zirconium, including impurities, the zirconium-based alloy formed by a process, comprising:(a) melting the alloying composition to produce a melted alloy material;(b) forging the melted alloy material to produce a forged alloy material;(c) 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 a conditioned alloy material;(g) repeating steps (e) and/or (f) to produce a final alloy material; and(h) subjecting the final alloy material to a final heat treatment selected to provide the 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 final alloy material is subjected to a final heat treatment selected from a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 15% to about 20% with the remainder being stress relief annealed or a final heat treatment of stress relief annealed, andwherein for providing the zirconium-based alloy exhibiting improved creep resistance, the final alloy material is subjected to a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 80% to about 95% recrystallization with the remainder being stress relief annealed. 16. The zirconium-based alloy of claim 15, wherein said alloy is formed into an article. 17. The zirconium-based alloy of claim 16, wherein said article is strip. 18. The zirconium-based alloy of claim 15, wherein the forged alloy material has a rectangular cross-section.