STP1270

    Mitigation of Irradiation Embrittlement by Annealing

    Published: Jan 1996


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    Abstract

    The main results of a complex investigation carried out in Russia of post irradiation annealing and reembrittlement of WWER-440 reactor pressure vessel materials are presented. The dependence of the Charpy transition temperature recovery on annealing temperature and fluence was established. Charpy specimens were reirradiated after annealing at 340, 380, 420, and 460°C. Experimental values of the Charpy transition temperature after reirradiation are compared to that predicted by three methods. At annealing temperatures equal to or above 420°C, results of the analysis indicate that, of the methods investigated, the “lateral shift” method gives the best result for estimating the transition temperature shift due to reirradiation.

    Keywords:

    pressure vessel steels, radiation embrittlement, radiation effects, neutron fluence, annealing, reembrittlement


    Author Information:

    Amayev, AD
    Chief researcher, head of laboratory, lead researcher, and director of department, RNRC Kurchatov Institute, Moscow,

    Kryukov, AM
    Chief researcher, head of laboratory, lead researcher, and director of department, RNRC Kurchatov Institute, Moscow,

    Levit, VI
    Chief researcher, head of laboratory, lead researcher, and director of department, RNRC Kurchatov Institute, Moscow,

    Platonov, PA
    Chief researcher, head of laboratory, lead researcher, and director of department, RNRC Kurchatov Institute, Moscow,

    Sokolov, MA
    Oak Ridge National Laboratory, Oak Ridge, TN


    Paper ID: STP16476S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP16476S


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