Abstract
The application of zinc injection at pressurized water reactors (PWRs) shows great bene- fits in reducing the radiation field and mitigating the primary water stress corrosion cracking (PWSCC) initiation and crack propagation of structure materials to a certain extent. The oxide film of Inconel 690 exposed to 300 ℃ dynamic high temperature water without/with 50 μg/kg Zn injec- tion up to 1200 h has been investigated by XPS, SEM and EDS. It is revealed that the oxide film formed on Inconel 690 in the water with 50 μg/kg Zn addition is much thinner with grain size much smaller than that without Zn addition, while the distribution of grain size of the oxide film followed the Gauss function. The highest zinc concentration is found in the outer portion of the ox- ide layer close to the outer surface. Compounds ZnCr2O4and ZnFe2O4 with low Gibbs energy were formed on the surface of the alloy in water with Zn addition, which make the oxide film much more stable than those in the Zn free water.
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