CORROSION STUDIES IN HIGH TEMPERATURE WATER ON U-2 W/O Zr ALLOY COEXTRUDED IN ZIRCALOY-2
Technical Report
·
OSTI ID:4285068
Samples of urannium-2 wt.% zirconium alloys sheathed in Zircaloy-2 were exposed to high temperature water. The Zircaloy sheaths were defected by drilling a small hole, allowing water to contact the uranium alloy. In the absence of a diffusion bond between the urannium alloy and the Zircaloy, very rapid corrosion occurred. The addition of 2 wt.% zirconium to the uranium affects the corrosion rate very little, however, it may affect the release of activity to the water. Heat treating the uranium-zirconinm alloy to produce a diffusion layer at the Zircaloy-uranium interface produces a corrosion-resiatant layer between the sheath and core which can have a marked effect on the corrosion resistance of the element at a defect. (J.R.D.)
- Research Organization:
- Atomic Energy of Canada Ltd. Chalk River Project, Chalk River, Ont.
- NSA Number:
- NSA-13-003809
- OSTI ID:
- 4285068
- Report Number(s):
- CRMet-802; AECL-702
- Country of Publication:
- Canada
- Language:
- English
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