CORROSION BEHAVIOR OF ZIRCONIUM-BASE URANIUM ALLOYS
Technical Report
·
OSTI ID:4332722
The corrosion behavior in high-temperature water of Zrbase alloys containing 7 to 8 wt.% of U was studied. A marked dependence of behavior on prior heat treatment was observed. In the annealed condition the alloys lost weight at rates of the order of one mg per dm/sup 2/ per hr of exposure to 360 deg C water. In the quenched condition the same alloys gained weight consistently, without any visible loss of oxide, for periods up to 4000 hr in length. The use of sponge Zr or a Zircaloy in place of crystal bar Zr in preparing the alloy had no noticeable effect on the corrosion resistance of the annealed material, but appeared to increase the corrosion rate observed after quenching. (auth)
- Research Organization:
- Knolls Atomic Power Lab., Schenectady, N.Y.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-12-000874
- OSTI ID:
- 4332722
- Report Number(s):
- KAPL-1570
- Country of Publication:
- United States
- Language:
- English
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