STP458

    Ozhennite 0.5 — Its Potential and Development

    Published: Jan 1969


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    Abstract

    Results of corrosion tests on Ozhennite 0.5 in organic coolant and high-temperature steam are summarized. The alloy shows improved corrosion and hydriding resistance compared to that of the commonly known zirconium alloys, the Zircaloys and 2.5Nb zirconium. Its possible use as a pressure-tube and fuel-cladding material in organic-cooled, heavy-water moderated reactors and as fuel cladding in advanced boiling-water reactors is discussed and the development program initiated to investigate its behavior under service conditions in these systems outlined. Mechanical properties of Ozhennite 0.5 pressure tubing and fuel cladding made by commercial methods are presented. These show that the alloy has similar mechanical strength to that of Zircaloy-2.

    Keywords:

    Ozhennite 0.5, zirconium alloys, corrosion, mechanical properties, organic-cooled reactors, boiling-water reactors, steam


    Author Information:

    Boulton, J.
    Head, Materials Development Branch, and Metallurgical Engineer, Atomic Energy of Canada Ltd., Whiteshell Nuclear Research Establishment, Pinawa, Man.

    Wright, M. G.
    Head, Materials Development Branch, and Metallurgical Engineer, Atomic Energy of Canada Ltd., Whiteshell Nuclear Research Establishment, Pinawa, Man.


    Paper ID: STP43836S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP43836S


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