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dc.contributor.authorKRYUKOV Alexanderen_GB
dc.contributor.authorBLAGOEVA Darinaen_GB
dc.contributor.authorDEBARBERIS Luigien_GB
dc.date.accessioned2013-12-12T01:02:15Z-
dc.date.available2013-12-11en_GB
dc.date.available2013-12-12T01:02:15Z-
dc.date.created2013-12-09en_GB
dc.date.issued2013en_GB
dc.date.submitted2013-12-02en_GB
dc.identifier.citationJOURNAL OF NUCLEAR MATERIALS vol. 443 no. 1-3 p. 171-175en_GB
dc.identifier.issn0022-3115en_GB
dc.identifier.urihttp://www.sciencedirect.com/science/article/pii/S0022311513008891en_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC86552-
dc.description.abstractThe results of long term research programme concerning the determination of irradiation embrittlement dependence on fast neutron flux for WWER-440 reactor pressure vessel steels before and after annealing are presented in this paper. The study of flux effect was carried out on commercial WWER-440 steels which differ significantly in phosphorous (0.013–0.036 wt%) and copper (0.08–0.20 wt%) contents. All specimens were irradiated in surveillance channel positions under similar conditions at high 4 1012 - cm2 s1 and low 6 1011 cm2 s1 fluxes (E > 0.5 MeV) at a temperature of 270 C. The radiation embrittlement was evaluated by transition temperature shift on the basis of Charpy specimens test results. In case of low flux, the measured Tk shifts could be 25–50 C bigger than the Tk shifts obtained from high flux data. A significant flux effect is observed in WWER-440 reactor pressure vessel steels with higher copper content (>0.13 wt%). Microstructural studies show that copper content decreases in the ferrite matrix and that there is formation of copper-enriched clusters and precipitates under irradiation and subsequent thermal annealing. Due to this fact the radiation damage does not depend on copper re-irradiation after annealing. Dependence of transition temperature shift on neutron flux is not expected for WWER-440 steels under re- irradiation after annealing.en_GB
dc.description.sponsorshipJRC.F.3-Energy securityen_GB
dc.format.mediumOnlineen_GB
dc.languageENGen_GB
dc.publisherELSEVIER SCIENCE BVen_GB
dc.relation.ispartofseriesJRC86552en_GB
dc.titleFlux effect analysis in WWER-440 reactor pressure vessel steelsen_GB
dc.typeArticles in periodicals and booksen_GB
dc.identifier.doi10.1016/j.jnucmat.2013.07.011en_GB
JRC Directorate:Energy, Transport and Climate

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