Patent ID: 9725791
Date: 2017-08-08
CPC Classifications: C22C,C22F,G21C,Y02E

Claim:
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; and a 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, and wherein 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.