STP1170: Surveillance of WWER-440Č Reactor Pressure Vessels

    Brumovský, M
    RPV project manager, Nuclear Research Institute,

    áš Páv, T
    Head, Mechanical Hot Cells GroupNuclear Research Institute, Řež,

    Pages: 14    Published: Jan 1993


    Abstract

    In Czechoslovakia there are six units of Water-Water Power Reactor (WWER)-440Č type reactors (pressurized water reactor [PWR] type) incorporated with pressure vessel surveillance specimens. These sets of specimens are kept for carrying out static tensile testing, impact notch toughness testing, and static fracture toughness testing, and are supplemented by necessary sets of neutron flux monitors.

    Results of mechanical testing of these specimens evaluated after one to five years of reactor operation are summarized and discussed with respect to the effect of individual heats and welding joints, radiation embrittlement laws, and lead factor and pressure vessel lifetime assessment.

    Keywords:

    pressure vessel steels, irradiation embrittlement, transition temperature shift, WWER-440, surveillance programs, 15Kh2MFA type steel, lead factor


    Paper ID: STP24763S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP24763S


    CrossRef ASTM International is a member of CrossRef.