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Creep studies for zircaloy life prediction in water reactors

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  • Nuclear Reactor Life Extension
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Abstract

Zirconium alloys, commonly used as cladding tubes in water reactors, undergo complex biaxial creep deformation. The anisotropic nature of these metals makes it relatively complex to predict their dimensional changes in-reactor. These alloys exhibit transients in creep mechanisms as stress levels change. The underlying creep mechanisms and creep anisotropy depend on the alloy composition as well as the thermomechanical treatment. The anisotropic biaxial creep of cold-worked and recrystallized Zircaloy-4 in terms of Hill’s generalized stress formulation is described, and the temperature and stress dependencies of the steady-state creep rate are reviewed. Predictive models that incorporate anelastic strain are used for transient and transients in creep.

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Authors and Affiliations

  1. the Department of Nuclear Engineering, North Carolina State University, USA

    K. Linga Murty (a professor)

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  1. K. Linga Murty
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Additional information

For more information, contact K.L. Murty, North Carolina State University, Department of Nuclear Engineering, Campus Box 7909, Raleigh, North Carolina 27695-7909; (919) 515-3657; fax (919) 515-5115; e-mail murty@ncsu.edu.

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Murty, K.L. Creep studies for zircaloy life prediction in water reactors. JOM 51, 32–39 (1999). https://doi.org/10.1007/s11837-999-0184-6

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