STP1270

    The Toughness of Irradiated Pressure Water Reactor (PWR) Vessel Shell Rings and the Effect of Segregation Zones

    Published: Jan 1996


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    Abstract

    To establish the integrity of pressure water reactor (PWR) vessels it is necessary to determine the toughness of A508C1.3 steel at the end of its life, that is after thermal ageing and irradiation embrittlement. In safety analyses the toughness can be deduced from a reference curve set forth in the code (ASME or RCC-M). The validity of the reference curve has been verified for several years for unirradiated French reactor vessels. Tests were performed on specimens taken from materials having heterogeneities in chemical composition. For most of the test results the reference curve is a lower bound. To solve the problem of determining the toughness of SA 508 C1.3 steel after irradiation and in the presence of possible heterogeneities, the toughness results were gathered. The synthesis shows that the RCC-M code curve is conservative.

    Keywords:

    pressurized water reactor, pressure vessel steel, SA 508 CL.3, toughness, irradiation, chemical composition heterogeneities, Charpy-V tests


    Author Information:

    Bethmont, M
    Manager, électricité de France, Moret-sur-Loing,

    Frund, J-M
    Researcher, électricité de France, Moret-sur-Loing,

    Housin, B
    Senior Consulting Engineer, Framatome, Tour Fiat, Paris La Défense

    Soulat, P
    Manager, Commissariat à l'énergie Atomique, DECM/SRMA, Gif-sur-Yvette,


    Paper ID: STP16481S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP16481S


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