STP1405

    Master Curve Evaluation of Irradiated Russian VVER Type Reactor Pressure Vessel Steels

    Published: Jan 2001


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    Abstract

    Results of a joint German/Russian irradiation program performed on the prototype pressurized water reactor VVER-2 of the Rheinsberg nuclear power plant (Germany) are summarized. The experiment comprises Charpy V-notch (CVN), precracked Charpy size (SENB) and compact tension (CT) specimens made of different heats of Russian VVER type reactor pressure vessel (RPV) base and weld metals. Reference temperatures, T0, were evaluated according to the Master Curve (MC) concept using the multi temperature method. Neutron irradiation induced ductile-to-brittle transition temperature (DBTT) shifts determined on the basis of CVN and SENB tests are compared. On the base of the DBTT the neutron embrittlement sensitivity and the annealing behavior of tested RPV steels are evaluated. Different heats of the same VVER-RPV steel exhibit different neutron induced embrittlement and annealing behavior. The determined CVN transition temperatures correlates to the T0 temperatures evaluated by the MC concept.

    Keywords:

    reactor pressure vessel steel, integrity assessment, Charpy-V test, transition temperature, fracture toughness, reference temperature, predicting formulas, radiation embrittlement


    Author Information:

    Viehrig, H-W
    Senior Scientist, Institute for Safety Research, Dresden,

    Boehmert, J
    Head of Department, Institute for Safety Research, Dresden,

    Dzugan, J
    Research Scientist, Institute for Safety Research, Dresden,

    Richter, H
    Research Scientist, BHG Edelstahl GmbH Freital, Freital,


    Paper ID: STP10529S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP10529S


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