Study on a new zirconium alloy for nuclear reactors
Conference
·
OSTI ID:48050
- Northwest Institute for Nonferrous Metal Research (NIN), Shaanxi (China)
Zr-1.5Mo-0.5Cr-0.3Fe-0.2Nb(wt.%) is a new alloy for nuclear reactors. The main properties and out-of-pile corrosion behaviour of the alloy are reported in this paper. The results indicate that the alloy possesses good comprehensive properties and its strength and out-of-pile corrosion resistance are superior to Zircaloy-2 and Zircaloy-4 at higher temperature especially. The transition time to acceleration of the corrosion rate is 240 days in water at 360{degrees}C. The uniform corrosion rate is 4.75 mg/dm{sup 2} {center_dot} month before the transition, and 6.82 mg/dm{sup 2} {center_dot} month after the transition, and both are less than Zircaloy-2. After immersing for 406 days, the oxide film on the surface remains bright black. The corrosion resistance of the welded zone of the sample falls down, but it can be notably improved by an annealing treatment.
- OSTI ID:
- 48050
- Report Number(s):
- CONF-910808--
- Country of Publication:
- United States
- Language:
- English
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