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U.S. Department of Energy
Office of Scientific and Technical Information

IMPROVED ZIRCONIUM ALLOYS. Technical Progress Report, November 1, 1962- July 31, 1963

Technical Report ·
OSTI ID:4679220

One phase of this program was the development of zirconium-base alloys superior to Zircaloy-2 in 680 deg F water. This objective, on the basis of corrosion resistance, tensile strengih, and hydrogen pickup, was accomplished. The alloys exhibiting these enhanced properties are Zr--0.75Cr-0.4Te and Zr-- 0.5Nb--0.4Te as well as other compositions within this system having very similar alloy concentrations Additional work is being carried out on these alloys for elucidation of general mechanical properties and to determine the effects of various heat treatments. A further objective of this program was the development of zirconium alloys acceptable for application in 750 and 900 deg F steam. Ternary alloy modifications made during the current year are presently being evaluated in these media. Preliminary data indicate that compositions in the systems Zr-Cr--Fe, Zr-V--Fe, and Zr-Nb--Te will satisfy this objective for 750 deg F and that alloys of Zr -Cr -(Te, Fe, Nb) and Zr --V--(Mo, Te) might be suitable for use at 900 deg F. Further corrosion data for long exposure times are being obtained so that more specific compositions will be indicated. (auth)

Research Organization:
illinois Inst. of Tech., Chicago. IIT Research Inst.
NSA Number:
NSA-17-034347
OSTI ID:
4679220
Report Number(s):
IITRI-B198-43; EURAEC-805
Country of Publication:
United States
Language:
English