REPORT OF THE MARCH 1953 MEETING OF THE ZIRCONIUM ALLOY CORROSION COMMITTEE
Technical Report
·
OSTI ID:4326399
The results of work done on the corrosion of Zircaloy-2 and other alloys are presented. Zircaloy-2 shows excellent corrosion resistance to steam at 750 deg F and water at 680 deg F for periods up to three and four months, respectively. There is little or no effect of Sn content on the corrosion resistance of sponge-base alloys of Zr containing 0.12% Fe, 0.10% Cr, and 0.05% Ni tested for 45 days at 750 deg F and 28 days at 680 deg F. This suggests lowering the Sn content in Zircaloy-2 to obtain increased fabricability with no sacrifice in corrosion resistance. Enough Sn should remain to insure a good N/ sub 2/ tolerance. Although relative effectiveness of Fe, Ni, and Cr in Zircaloy- 2 has not yet been determined, it appears that low totals of Fe, Ni, and Cr are detrimental to corrosion resistance. Some samples of unalloyed Zr sponge displayed excellent corrosion resistance to 680 deg F water for 14 days and 750 deg F steam for 48 hours. (W.L.R.)
- Research Organization:
- Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
- NSA Number:
- NSA-12-001963
- OSTI ID:
- 4326399
- Report Number(s):
- WAPD-MM-200(Del.)
- Country of Publication:
- United States
- Language:
- English
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