STP1170

    Study by Positron Annihilation of Neutron Damage in a Pressurized Water Reactor (PWR) Pressure Vessel Steel After a 13-Year Irradiation in the CHOOZ A Reactor Surveillance Program

    Published: Jan 1993


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    Abstract

    The microstructural evolution of a pressure vessel steel (C shell base metal) was studied after a long-term irradiation (13 years) in the surveillance program of a CHOOZ A reactor. The positron lifetime technique was used to determine if the neutron-induced damage is partially composed of voids. Analysis of spectra measured on irradiated samples (fluence = 14 × 1019 n∙cm-2, E > 1 MeV) reveals that the neutron irradiation has not induced the formation of voids containing more than about 50 vacancies (that is, voids with a radius higher than about 0.5 nm). On the other hand, some results suggest the presence after irradiation of a low density of very small voids (less than 10 vacancies) probably located in precipitates.

    Keywords:

    pressure vessel, surveillance program, irradiation damage, transmission electron microscopy, small angle neutron scattering, positron annihilation


    Author Information:

    Van Duysen, JC
    Head of the Metallurgical Group, Electricité de France (EDF), Direction des Etudes et Recherches, Ecuelles,

    Bourgoin, J
    Research engineer, EDF, Direction de la Production Thermique, Groupe Des Laboratoires, SCMI, Avoine,

    Moser, P
    Research engineer, Centre d'Etude Nucléaire de Grenoble, DREMC/SPMM/MP, Grenoble,

    Janot, C
    Professor, Institut Lauë Langevin, Avenue des Martyrs, Grenoble,


    Paper ID: STP24769S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP24769S


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