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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 Pages: 7 Published: Jan 1993
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View License Agreement 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 ASTM International is a member of CrossRef. | ||