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

ZIRCONIUM HIGHLIGHTS, APRIL 1958

Technical Report ·
OSTI ID:4327146
The preparation of Zircaloy-2 surfaces for corrosion exposure consists of the chemical removal of one to two mils of surface metal by bright etching in an aqueous solution of nitric and hydrofluoric acid. Experiments were initiated to determine the effects of substituting sulfuric acid for the nitric acid on pickling and corrosion behavior. A satisfactory metallographic technique for identification of the zirconium hydride phase after various thermal treatments was developed to determine the hydrogen content in Zircaloy-2. The hydrogen is removed by vacuum annealing at 1450 deg F. The properties of cast Zircaloy-2 are being investigated in order that cast components might be used for reactor application. Stress-rupture tests of atmosphere-melted, extruded, and annealed Zircaloy-2 were performed in helium at 600, 700, and 800 deg F. Rupture values, minimum creep rates, and time to various amounts of total deformation are shown as a function of applied stress. (For preceding period see WAPD-ZH-5.) (W.D.M.)
Research Organization:
Westinghouse Electric Corp. Bettis Plant, Pittsburgh Page(s): 22
DOE Contract Number:
AT(11-1)-GEN-14
NSA Number:
NSA-12-009836
OSTI ID:
4327146
Report Number(s):
WAPD-ZH-6
Country of Publication:
United States
Language:
English

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