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    West German Research Programs on Irradiation Effects on Reactor Pressure Vessels

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    Reactor pressure vessels of nuclear installations are subjected to operating parameters that lead to a change in material and flaw state. The safety margin of both the material for older vessels and the optimized material has to be quantified with reference to extremely long-term effects. Research programs in West Germany are focused on assessing criteria for the applicability of small-scale specimen testing to component behavior under all realistic and postulated loading conditions. The problem will be treated theoretically and experimentally for a wide range of materials, including the worst-case material state at the end of life.


    light water reactors, pressure vessel steels, irradiation, fracture mechanics, pressurized thermal shock, large scale specimens, intermediate size vessels, welded joints

    Author Information:

    Kussmaul, K
    Professor and Director, Staatliche Materialprüfungsanstalt, University of Stuttgart, Stuttgart,

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP31845S