Digital Library / STP / STP1170-EB / STP24769S



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

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

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

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

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


Pages: 7    Published: Jan 1993


Download this paper for $25 PDF (136K)          View License Agreement
        Click here to download the complete source publication for $103 PDF (7.9M)


Source: STP1170-EB


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

Paper ID: STP24769S
Committee/Subcommittee: E10.08
DOI: 10.1520/STP24769S
CrossRef ASTM International is a member of CrossRef.