Abstract:
A method for reducing corrosion of metal components in a water cooled nuclear reactor. A compound containing a platinum group metal, e.g. palladium, is injected alone in small amounts into the high temperature water of the reactor in the form of a solution or suspension. This compound decomposes under reactor thermal conditions to release atoms of the metal in an amount sufficient when present on the metal components to reduce the electrochemical corrosion potential of the metal components to a level below the critical potential to protect against intergranular stress corrosion cracking.
Abstract:
A method for mitigating general corrosion and crack initiation and growth on the surface of metal components in a water-cooled nuclear reactor. A compound containing a non-noble metal such as zirconium or titanium is injected into the water of the reactor in the form of a solution or suspension. This compound decomposes under reactor thermal conditions to release ions/atoms of the non-noble metal which incorporate in or deposit on the surfaces of the components, including the interior surfaces of any cracks formed therein. The preferred compounds are zirconium compounds such as zirconium acetylacetonate, zirconium nitrate and zirconyl nitrate. Zirconium deposited in or on an oxided surface of a metal component will reduce the electrochemical potential at the surface to a level below the critical potential to protect against intergranular stress corrosion cracking.
Abstract:
Method for reducing corrosion of alloy components in a water cooled nuclear reactor or associated components comprising the step of injecting into the water of the reactor in the presence of zinc a noble metal cation-releasing compound which releases noble metal cations or cationic species containing noble metal species into the reactor water under operating reactor thermal conditions.
Abstract:
A method for mitigating general corrosion and crack initiation and growth on the surface of metal components in a water-cooled nuclear reactor. A compound containing a non-noble metal such as zirconium or titanium is injected into the water of the reactor in the form of a solution or suspension. This compound decomposes under reactor thermal conditions to release ions/atoms of the non-noble metal which incorporate in or deposit on the surfaces of the components, including the interior surfaces of any cracks formed therein. The preferred compounds are zirconium compounds such as zirconium acetylacetonate, zirconium nitrate and zirconyl nitrate. Zirconium deposited in or on an oxided surface of a metal component will reduce the electrochemical potential at the surface to a level below the critical potential to protect against intergranular stress corrosion cracking.
Abstract:
Method for controlling the amount of metal atoms deposited into an oxide layer present on a metal surface, which metal atoms increase the corrosion resistance of metal when present in the oxide film, wherein the metal surface is submeerged in water at a selected temperature within the range of about to 200 DEG to 550 DEG F; and a solution of a compound containing the metal which increases the corrosion resistance of the metal surface when present in the oxide film is injected into the water. The compound decomposes at the selected temperature to release atoms of the metal which incorporate in the oxide film at a desired loading.
Abstract:
Method for controlling the amount of metal atoms deposited into an oxide layer present on a metal surface, which metal atoms increase the corrosion resistance of metal when present in the oxide film, wherein the metal surface is submeerged in water at a selected temperature within the range of about to 200° to 550 °F; and a solution of a compound containing the metal which increases the corrosion resistance of the metal surface when present in the oxide film is injected into the water. The compound decomposes at the selected temperature to release atoms of the metal which incorporate in the oxide film at a desired loading.
Abstract:
A method for reducing corrosion of metal components in a water cooled nuclear reactor. A compound containing a platinum group metal, e.g. palladium, is injected alone in small amounts into the high temperature water of the reactor in the form of a solution or suspension. This compound decomposes under reactor thermal conditions to release atoms of the metal in an amount sufficient when present on the metal components to reduce the electrochemical corrosion potential of the metal components to a level below the critical potential to protect against intergranular stress corrosion cracking.
Abstract:
A method for reducing corrosion of metal components in a water cooled nuclear reactor. A compound containing a platinum group metal, e.g. palladium, is injected alone in small amounts into the high temperature water of the reactor in the form of a solution or suspension. This compound decomposes under reactor thermal conditions to release atoms of the metal in an amount sufficient when present on the metal components to reduce the electrochemical corrosion potential of the metal components to a level below the critical potential to protect against intergranular stress corrosion cracking.