SYMPOSIA PAPER Published: 01 January 1993

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


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.

Author Information

Van Duysen, JC
Electricité de France (EDF), Direction des Etudes et Recherches, Ecuelles, France
Bourgoin, J
EDF, Direction de la Production Thermique, Groupe Des Laboratoires, SCMI, Avoine, France
Moser, P
Centre d'Etude Nucléaire de Grenoble, DREMC/SPMM/MP, Grenoble, France
Janot, C
Institut Lauë Langevin, Avenue des Martyrs, Grenoble, France
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Developed by Committee: E10
Pages: 132–138
DOI: 10.1520/STP24769S
ISBN-EB: 978-0-8031-5228-1
ISBN-13: 978-0-8031-1478-4