Interdiffusion in Zircaloy-2 Clad U - 2 w/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior
- Nuclear Metals, Inc., Concord, MA (United States)
Properties of the interdiffusion zone in Zircaloy-2 clad U - 2 w/o Zr fuel materials have been investigated and the results correlated with the corrosion behavior of defected specimens in high-temperature water. Electron microprobe and metallographic examinations of the zones were carried out, as well as corrosion studies on specimens annealed after the diffusion treatment. The results indicate that the beneficial effect of the diffusion treatment upon the corrosion behavior of defected specimens results from improved strength properties of the bond zone. During corrosion, the combined strengths of the zone and Zircaloy-2 cladding are great enough to compact the oxide corrosion product at the base of the defect, the compacted oxide inhibiting further attack. The formation of equilibrium alpha uranium in the inner portion of the zone must, however, be minimized in order to achieve the effect of the diffusion treatment.
- Research Organization:
- Nuclear Metals, Inc., Concord, MA (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-14-018125
- OSTI ID:
- 4158011
- Report Number(s):
- NMI--1233
- Country of Publication:
- United States
- Language:
- English
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