G - Physics – 21 – C
Patent
G - Physics
21
C
G21C 21/00 (2006.01) C23F 11/08 (2006.01) C23F 11/18 (2006.01) G21C 17/022 (2006.01) G21C 19/30 (2006.01) G21C 19/307 (2006.01) G21C 21/14 (2006.01)
Patent
CA 2143241
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 contain- ing 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 inter- ior surfaces of any cracks formed therein. The compound may be organic, organometallic or inorganic in nature. Zirconium deposited inside a crack will reduce the electrochemical potential inside the crack even if the bulk surface zirconium is depleted under high fluid flow conditions. As a result, the electrochemical potential inside the crack is decreased to a level below the critical potential to protect against intergranular stress corrosion cracking.
Diaz Thomas Pompilio
Hettiarachchi Samson
Company General Electric
Wilson Craig
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