QUARTERLY PROGRESS REPORT OF THE TECHNOLOGY SECTION-SPECIAL MATERIALS SECTION FOR THE PERIOD JULY 1 TO SEPTEMBER 30, 1958
- Published
- United States : [publisher not identified], 1958.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1958. - Physical Description
- microopaque : positive ; 8 x 13 cm
- Summary
- The inclusions in Zircaloy-2 have been attributed to faulty welding procedures with carbon electrcdes. The 28day corrosion results for both 750 deg F steam and 680 deg F water tests of the impurity program coupons show only slight variations in weight gain. Silicon content of about 300 ppm in Zircaloy-2 apparently reduces the deleterious effccts on the corrosion resistance of furnace- cooled material. Ingots of Zircaloy-2 containing up to 10,000 ppm O/sub 2/ can be forged. Temperature must be increased to about 1900 deg F for those ingots with greater than 5000 ppm O/sub 2/ Slabs containing up to 5000 ppm can be hot rolled. Slabs containing greater than 5000 ppm could not be rolled even at temperatures up to 1825 deg F. Tensile strength of Zircaloy-2 increase linearly with O/sub 2/ contents up to 10,000 ppm. Castings of Zircaloy-2 have been found to be suitable for reactor applications. Zircaloy-2 strip has been cold rolled commercially to tolerances of1/2 to1/3 of commercial tolerances. Zircaloy-2 cold- rolled strip can be slit to very exacting dimensions. (For preceding period see WAPD-NCE-9040.) (auth)
- Report Numbers
- WAPD-NCE-666
- Other Subject(s)
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- NSA number: NSA-14-001780
OSTI Identifier 4227410
Research organization: Westinghouse Electric Corp. Bettis Plant, Pittsburgh.
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