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首页> 外文期刊>Corrosion: The Journal of Science and Engineering >Local Corrosion Behavior of Zr-1 Nb Cladding in Water-Water Energetic Reactor Primary Coolants Under Ambient Conditions and at High Temperature
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Local Corrosion Behavior of Zr-1 Nb Cladding in Water-Water Energetic Reactor Primary Coolants Under Ambient Conditions and at High Temperature

机译：Local Corrosion Behavior of Zr-1 Nb Cladding in Water-Water Energetic Reactor Primary Coolants Under Ambient Conditions and at High Temperature

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摘要

Localized corrosion of the Zr-1Nb (E110) alloy was studied in solutions of a chemical composition similar to the primary cool-ant in Russian-type water-water energetic reactor (VVER)-type reactors. Cyclic voltammetry and chronoamperometry mea-surements were used to detect pit initiation, propagation, and healing. Measurements were made at room temperature and at 300℃ under high pressure. For pit initiation, chloride and iodide ions were injected into the base buffer solution containing boric acid (H_3BO_3) and potassium hydroxide (KOH). It was conch fried that chloride ions are more aggressive than iodide ions. The critical halide concentration at high temperature, resulting in pit initiation compared to that at room temperature, was one order of magnitude smaller. Recovering of the passive state at room temperature was studied on chemically polished and preoxidized samples.

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