You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.


    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

      Format Pages Price  
    PDF () 7 $25   ADD TO CART
    Complete Source PDF (7.9M) 7 $103   ADD TO CART


    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.


    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,

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP24769S

    CrossRef ASTM International is a member of CrossRef.