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AN INVESTIGATION OF ZIRCONIUM ALLOYS FOR RESISTANCE TO CARBON DIOXIDE CORROSION

Technical Report ·
OSTI ID:4111617
An investigation was made of zirconium base alloys suitable for reactor core hardware in a CO/sub 2/-cooled, D/sub 2/Omoderated reactor. Commercially available alloys were investigated for times to 18,000 hours at temperatures from 800 to 1300 deg F. Sixty-five experimentally prepared binary alloys containing 26 addition elements at different contents were also investigated. Data are presented in condensed form and emphasis was placed on aspects of interest to the general problem of zirconium corrosion. Multiple rate transition behavior was found at 1050 deg F, while at 1150 deg F and above, rates were linear. The order of merit'' of the alloys containing various addition elements varied from temperature to temperature. Thermal cycling at times to 3000 hours had little effect on the more resistant alloys as did changes in pressure from atmospheric to 500 psi. Diffusion of oxygen into the metal was not found. Beta heat treatment improved the corrosion resistance of certain alloys. Both similarities and differences in behavior of the alloys in C/sub O/2 as compared with behavior in oxygen were found. Rather high but acceptable corrosion rates at l050 deg F for two year periods were determined for the commercial 1/2% Cu--1/2% Mo alloys and several of the experimental binary alloys in the dry (<10 ppm H/sub 2/O), carbon monoxide free, CO/sub 2/ employed. At 1150 deg F, exposures of several thousand hours were possible without excessive attack. Twelve beneficial alloying elements were identified. Four elements were shown to be deleterious in the compositions tested. (auth)
Research Organization:
General Nuclear Engineering Corp., Dunedin, Fla.
NSA Number:
NSA-18-012576
OSTI ID:
4111617
Report Number(s):
GEAP-4089(Vol.I)(Paper 3)
Country of Publication:
Country unknown/Code not available
Language:
English