Modification of oxide film electrical conductivity to maintain low corrosion potential in high-temperature water

摘要: A method for mitigating general corrosion and crack initiation growth on the surface of a metal components in water-cooled nuclear reactor. compound containing non-noble such as zirconium or titanium is injected into water reactor form solution suspension. This decomposes under thermal conditions to release ions atoms which incorporate surfaces components, including interior any cracks formed therein. The preferred compounds are acetylacetonate, nitrate zirconyl nitrate. Zirconium incorporated oxided component will reduce electrochemical potential at level below critical protect against intergranular stress cracking without addition hydrogen.