STP1270

    Microstructure and Mechanical Properties of WWER-440 Reactor Vessel Metal After Service Life Expiration and Recovery Anneal

    Published: Jan 1996


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    Abstract

    The microstructure of base and weld metals (st.15Kh2MFA) of Novovoronezh Nuclear Power Plant Units 1 and 4 reactor vessels was studied after service life expiration and recovery anneal by means of light metallography and transmission electron microscopy. The qualitative characteristics of flow structure were determined. The estimates were made for the contributions of different flows to the radiation hardening and its total value. The conclusion was made that the marked difference in the mechanical properties of irradiated weld and base metals can be caused either by different original structure conditions or by the difference of alloying and impurity elements content.

    Keywords:

    radiation, pressure vessel steel, hardening, embrittlement, microstructure


    Author Information:

    Gorynin, IV
    Director, senior research scientist, head of laboratory and division chief, Central research institute of structural materials “Prometey”, St.Petersburg,

    Nesterova, EV
    Director, senior research scientist, head of laboratory and division chief, Central research institute of structural materials “Prometey”, St.Petersburg,

    Nikolaev, VA
    Director, senior research scientist, head of laboratory and division chief, Central research institute of structural materials “Prometey”, St.Petersburg,

    Rybin, VV
    Director, senior research scientist, head of laboratory and division chief, Central research institute of structural materials “Prometey”, St.Petersburg,


    Paper ID: STP16477S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP16477S


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