IMPROVED ZIRCONIUM ALLOYS. Quarterly Report, August 1, 1963-October 31, 1963
The development of a zirconium-base alloy superior to Zircaloy-2 for application in 680 deg F water has---on the basis of corrosion resistance, strength, and hydrogen pickup characteristics---been successfully accomplished. In particular, the materials Zr-0.75Cr-0.4Te and Zr-0.5Nb0.4Te have exhibited properties which are significantly improved over Zircaloy-2 and could be applied to in-core reactor uses. Study of a wide variety of alloys in 750 deg F steam was fruitful. For this atmosphere, certain alloys of Zr-Cr-Fe of moderate alloy concentration and Zr-0.75V0.75Fe exhibit highly acceptable corrosion resistance on the basis of 4000 hours' exposure. The strength of these materials at 750 deg F appears satisfactory. However, the hydrogen pickup characteristics are not fully known, and it must be shown that reasonably acceptable mechanical properties are maintained at hydrogen contents of up to about 200 ppm. For the 900 deg F steam medium, further effort should be devoted to alloy development. Perhaps acceptable corrosion resistance can be obtained with Zr2Cr or Zr-4Fe ternary modifications; however, the pickup of corrosion hydrogen would be fairly substantial. (auth)
- Research Organization:
- Illinois Inst. of Tech., Chicago. IIT Research Inst.
- NSA Number:
- NSA-18-002162
- OSTI ID:
- 4144459
- Report Number(s):
- IITRI-B198-46; EURAEC-888
- Country of Publication:
- United States
- Language:
- English
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DEVELOPMENT OF IMPROVED ZIRCONIUM ALLOYS FOR USE IN SUPERHEATED WATER AND STEAM
IMPROVED ZIRCONIUM ALLOYS. Quarterly Report, October 1, 1962-December 31, 1962