The experimental work leading to the development of Zircaloys -1, -2, - 3, and -4 are reviewed. The corrosion properties of Zircaloys-2 and -4 in high temperature water and steam and the effects of composition, heat treatment, and water chemistry upon oxide film formation and hydrogen absorption during corrosion are discussed. (auth)
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT(11-1)-GEN-14 NSA number: NSA-17-014744 OSTI Identifier 4749323 Research organization: Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh.