STP1170: Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels

    Munier, A
    Ph.D. student and senior researcher, Institut de Génie Atomique, Ecole Polytechnique Fédérale de Lausanne, Lausanne,

    Schaller, R
    Ph.D. student and senior researcher, Institut de Génie Atomique, Ecole Polytechnique Fédérale de Lausanne, Lausanne,

    Mercier, O
    Senior researchers, Paul Scherrer Institute, Villigen,

    Waeber, WB
    Senior researchers, Paul Scherrer Institute, Villigen,

    Pages: 14    Published: Jan 1993


    Abstract

    The radiation embrittlement of reactor pressure vessel steels may be partially explained by the creation of irradiation-induced defects that interact with the moving dislocations during plastic deformation. This research studies the nature of the interaction mechanisms and the microstructural properties and the mobility of the dislocations.

    Internal friction measurements, torsional plastic deformation tests, and transmission electron microscopy observations have been performed in ferritic steels used for reactor pressure vessels, more precisely the JRQ (Japanese Reference Quality) steel (International Atomic Energy Agency [IAEA] correlation monitoring material). The influence of neutron irradiation and of annealing treatments is discussed.

    Keywords:

    pressure vessel steels, radiation embrittlement, mechanical properties, microstructure, internal friction, torsional deformation


    Paper ID: STP24781S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP24781S


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