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

IMPROVED ZIRCONIUM ALLOYS. Quarterly Report for January 1, 1961-March 31, 1961

Technical Report ·
DOI:https://doi.org/10.2172/4029107· OSTI ID:4029107
Corrosion testing data are presented for a large number of Zr alloys in 68O deg F water (1043 and 1902 hr), 750 deg F steam (329 hr), and 900 deg F steam (97 hr). These alloys include Zircaloy-2 and Zr alloyed with Nb, Sn, V, Sb, C r, Cu, Fe, Si, W, Mo, Ta, Co, Pt, Pd, Rh, As, Bi, Te, Ge, Ag, and Ni. Tensile test data are also reported for ten of these alloys at 68O deg F; these alloys are Zr alloyed with Nb, Sn, Fe, V, Cr, Mo, Sb, and Co, in addition to unalloyed Zr and Zircaloy-2. (D.L.C.)
Research Organization:
Illinois Inst. of Tech., Chicago. Armour Research Foundation
NSA Number:
NSA-15-015992
OSTI ID:
4029107
Report Number(s):
ARF-2198-15; EURAEC-87
Country of Publication:
United States
Language:
English