Abstract: This invention describes a tubular water reactor fuel cladding having an outer cylindrical layer composed of a conventional zirconium base alloy. Bonded to the outer cylindrical layer is a second layer composed of an alloy selected from the group of zirconium base alloys consisting of: about 0.19 to 0.6 wt. % tin, about 0.19 to 0.5 wt. % iron, and about 100 to 700 ppm oxygen; or about 0.4 to 0.6 wt. % tin, about 0.1 to 0.3 wt. % iron, about 0.1 to 0.3 wt. % nickel, and about 100 to 700 ppm oxygen.

Abstract: This invention relates to a tubular water reactor fuel cladding having an outer cylindrical layer composed of a conventional zirconium base alloy. Bonded to the outer layer is a second, inner layer composed of an alloy consisting essentially of: about 0.1 to 0.3 wt. % tin; about 0.05 to 0.2 wt. % iron; about 0.05 to 0.4 wt. % niobium; about 0.03 to 0.1 wt. % of either chromium or nickel, alone or in combination with each other; while keeping the sum of the iron chromium and nickel contents below 0.25 wt. %; 300 to 1200 ppm oxygen; and the balance essentially zirconium. The inner layer is characterized by excellent resistance to PCI crack propagation, excellent aqueous corrosion resistance and a fully recrystallized microstructure.

Abstract: Articles, such as tubing, which have excellent corrosion resistance to steam at elevated temperatures and to hydriding, are produced from zirconium alloys containing 0.5 to 2.0 percent niobium, up to 1.5 percent tin, and up to 0.25 percent of a third alloying element such as iron, chromium, molybdenum, vanadium, copper, nickel and tungsten. The articles are formed by beta-treating the alloy, initially deforming the same at a temperature below 650.degree. C. and further deforming the same through cold working stages also below 650.degree. C., annealing the material between the cold working stages at a temperature between 500.degree.-650.degree. C., and final annealing the same at a temperature below 650.degree. C. to provide articles having a microstructure of fine precipitates of less than about 800 .ANG., homogeneously dispersed throughout the zirconium.