STP824

    In-Reactor Creep of Zr-2.5Nb

    Published: Jan 1984


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    Abstract

    The anisotropy of irradiation creep of Zr-2.5Nb alloy tubes at 570 K has been investigated using creep of helical springs and stress relaxation of twisted rods and bent beams. These tests measure creep rate directly since strains associated with irradiation growth are absent. Creep rates from these tests and from results on creep of pressurized tubes reported in the literature can be correlated through consideration of the crystallographic texture, slip systems, and dislocation density of the Zr-2.5Nb tubing. A creep model based on glide of 1311¯20 type dislocations on prismatic planes in combination with secondary glide of 1311¯22 dislocations on {10¯11} pyramidal planes provides a consistent correlation. The creep rate is only slightly dependent on dislocation density as measured by X-ray diffraction.

    Keywords:

    zirconium alloys, nuclear industry, creep, stress relaxation, in-reactor, texture, springs, Zr-2.5Nb


    Author Information:

    Causey, AR
    Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories, Chalk River, Ont.

    Holt, RA
    Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories, Chalk River, Ont.

    MacEwen, SR
    Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories, Chalk River, Ont.


    Paper ID: STP34476S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP34476S


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