STP1502

    Surveillance of the Fracture Behavior of Zircaloy-4 Welds Using the Small Punch Test

    Published: Jan 2009


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    Abstract

    Zircaloy-4 (Zr-4) is a zirconium alloy that has been used extensively within the nuclear industry in both power generation and research reactors. The potential for welded reactor core components to undergo embrittlement during neutron irradiation is an important materials property issue to be considered throughout the service life of the reactor. Of particular interest is the performance of welded joints which depend on the properties of both the weld heat-affected zone (HAZ) and the parent metal. For this work Zr-4 HAZ was simulated using a Gleeble weld simulator to rapidly bring the material into the β-Zr zone at peak temperatures of 1200 and 1400°C. The small punch (SP) test was then used to investigate the variation in fracture behavior of these narrow zones of the weld and compare them with the parent metal. A finite element analysis (FEA) model of the SP test was developed which can be used to predict the deformation and fracture behavior of Zr-4 welds and is compared with the experimental data obtained.

    Keywords:

    fracture, weld, small punch test, Zircaloy-4, finite element analysis


    Author Information:

    Wei, T.
    Australian Nuclear Science and Technology Organisation, Menai, NSW

    Carr, D. G.
    Australian Nuclear Science and Technology Organisation, Menai, NSW

    Li, H.
    Australian Nuclear Science and Technology Organisation, Menai, NSW

    Smith, K.
    University of Wollongong, Wollongong, NSW

    Harrison, R. P.
    Australian Nuclear Science and Technology Organisation, Menai, NSW


    Paper ID: STP48733S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP48733S


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