CORROSION BEHAVIOR OF URANIUM-ZIRCONIUM ALLOYS IN HIGH TEMPERATURE WATER AND STEAM
The corrosion behavior of uranium -zirconium alloys cortaining 50 wt. % U has been determined in high temperature water at 600 and 680 deg F and in steam at 750 deg F. Data for other compositions in the range of 10 to 60 wt. % uranium are also presented to indicate the general effect of uranium content on corrosion behavior of uraniumzirconium alloys. It was found that, in general, the 50 wt. % U-50 wt. % Zr alloys are essentially unaffected by heat treatment. They exhibit a linear rate of corrosion at 680 deg F. These rates increase with increasing tem perature according to the Arrhenius relationship. Corrosion life as a function of uranium content and temperature is presented and a mechanism of corrosion is suggested. The increase in total hydrogen content of the 50 wt. % U-50 wt. % Zr alloys resulting from corrosion at 680 deg F in water is presented. From a comparison of oxidation data obtained in water with those obtained in dry oxygen at similar temperatures, it is concluded that hydrogen is probably not involved in the mechanism of corrosion of these materials because of the good agreement between the two kinds of data. This idea is further substantiated by data from another laboratory which indicates that the hydride formed in the 50 wt. % U-50 wt. % Zr alloy is similar to ZrH/sub 1.2 to 1.4) rather than to uranium hydride. (auth)
- Research Organization:
- Westinghouse Electric Corp. Bettis Plant, Pittsburgh
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(11-1)-GEN-14
- NSA Number:
- NSA-12-010585
- OSTI ID:
- 4324147
- Report Number(s):
- WAPD-T-416
- Country of Publication:
- United States
- Language:
- English
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