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High-Strength Zirconium Alloys

Description: The properties of zirconium alloyed with aluminum tin, and molybdenum were investigated. Using reactorgrade zirconium sponge, 11 zirconium-base alloys were double arc-melted and cast into 6-in.-diam. ingots weighing 35 lb each. By such standard hot working procedures as extruding and rolling, the ingots were converted to 1/8-in.-thick strips. The extruded and rolled products were used for a variety of evaluation studies which included corrosion thermal conductivity, tensile, and creep tests. The alloys demonstrated short-time elevated temperature strength properties equal to or greater than type-304 stainless steel. Their corrosion resistance in sodium, at 1000 deg F, compares favorable with that of unalloyed zirconium. The creep resistance and the thermal conductivity were found to be less than those for type-304 stainless steel, but adequate for nuclear reactor application. (auth)
Date: July 15, 1959
Creator: Wagner, R.K. & Kline, H.E.
Partner: UNT Libraries Government Documents Department

A COMPILATION OF ROOM TEMPERATURE AND 1200 F PROPERTIES OF METALLIC MATERIALS WITH SPECIFIC REFERENCE TO THEIR USE AS FUEL CLADDING IN SODIUM COOLED THERMAL REACTORS

Description: A compilation is presented of room temperature and 1200/sup o/F properties of a large number of alloys which might be considered for use in a sodium-cooled reactor. Specific consideration is given to the use of such materials as fuel cladding. The arbitrary basis for property comparison is type 304 stainless steel. The study was made of 10 classes of alloys. These alloys are alloy steels, ferritic stainless steels, austenitic stainless steels, iron and iron-aluminum alloys, precipitation-hardening stainless steels, austenitic superalloy, nickel-base alloys: cobaltbase alloys; copper-base alloys, arid refractory metals and alloys. (W.J.H.)
Date: August 16, 1960
Creator: Kline, H.E.
Partner: UNT Libraries Government Documents Department