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Cadmium metal embrittlement of Zircaloy-2

Nature volume 265, pages 36–37 (1977)Cite this article

Abstract

EFFECTS of chemical environments upon the mechanical properties of zirconium alloys are of great interest because such alloys are used to contain fissionable fuel in water-cooled nuclear reactors. Particular interest attaches to stress corrosion cracking or liquid metal embrittlement because both of these phenomena are known to produce non-ductile fractures in otherwise ductile materials. Rosenbaum et al. reported iodine stress corrosion cracking of Zircaloy-2 some years ago1,2, and this phenomenon has been extensively investigated by others3–5. Zircaloy-2 is an alloy of zirconium containing by weight about 1.5% tin, 0.15% iron, 0.1% chromium, 0.05% nickel and 0.12% oxygen. Cox has reported embrittilement of Zircaloy by mercury or liquid caesium at room temperature3. However, the phenomenon of liquid metal embrittlement is known to be favoured by low temperatures6, and Zircaloy nuclear fuel cladding operates in the vicinity of 300 °C.

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Authors and Affiliations

  1. General Electric Company Research and Development Center, Schenectady, New York, 12309

    W. T. GRUBB

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  1. W. T. GRUBB
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GRUBB, W. Cadmium metal embrittlement of Zircaloy-2. Nature 265, 36–37 (1977). https://doi.org/10.1038/265036a0

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