ZIRCALOY-2 is a zirconium alloy recommended as a structural material for heat transfer in nuclear reactors. Its use is limited to 750 F operation. This datasheet provides information on composition, physical properties, microstructure, hardness, elasticity, and tensile properties as well as fracture toughness and creep. It also includes information on low and high temperature performance, and corrosion resistance as well as forming, heat treating, machining, joining, and surface treatment. Filing Code: Zr-3. Producer or source: Carborundum Metals Company.

chemical composition, corrosion-resistant alloys, creep properties, elasticity, fracture toughness, hardness, heat treatability, high-temperature alloys, joinability, low-temperature alloys, machinability, microstructure, nuclear reactors, physical properties, tensile properties, workability, Zircaloy-2
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Copyright © ASM International® 1996
1996
ASM International
Topics
Microstructure Nuclear reactors Corrosion-resistant alloys High-temperature alloys Zirconium alloys Chemical composition Heat treatability Joinability Machinability Workability Creep properties Elastic modulus Fracture toughness Hardness Tensile properties Physical properties Thermal properties
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