Application of the Small-Punch Test to Irradiated Reactor Vessel Steels in the Brittle-Ductile Transition Region

    Volume 5, Issue 4 (April 2008)

    ISSN: 1546-962X

    CODEN: JAIOAD

    Published Online: 18 April 2008

    Page Count: 14


    Linse, T.
    TU Bergakademie Freiberg, Institute of Mechanics and Fluid Dynamics, Freiberg,

    Kuna, M.
    TU Bergakademie Freiberg, Institute of Mechanics and Fluid Dynamics, Freiberg,

    Schuhknecht, J.
    Forschungszentrum Dresden Rossendorf, Institute of Safety Research, Department of Material and Component Safety, Dresden,

    Viehrig, H.-W.
    Forschungszentrum Dresden Rossendorf, Institute of Safety Research, Department of Material and Component Safety, Dresden,

    (Received 18 January 2007; accepted 21 February 2008)

    Abstract

    In this paper, a method is applied for the identification of hardening parameters in the brittle-ductile transition region and the determination of Weibull parameters in the brittle region using small-punch tests. A small-punch-test device is developed to measure the load-displacement curve for non-irradiated and irradiated specimens of a reactor vessel steel at different temperatures inside a hot cell. In a global optimization algorithm for the identification of hardening properties, time-consuming finite element method (FEM) calculations are avoided by using neural networks that were trained with the help of a database previously generated by FEM. Identified material properties are compared with data from tensile tests, where available. The influence of irradiation and temperature on the material and fracture behavior is analyzed.


    Paper ID: JAI101008

    DOI: 10.1520/JAI101008

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    Author
    Title Application of the Small-Punch Test to Irradiated Reactor Vessel Steels in the Brittle-Ductile Transition Region
    Symposium Fifth Symposium on Small Specimen Test Techniques, 2007-02-01
    Committee E10