摘要:
A method for mitigating crack initiation and propagation on the surface of metal components in a water-cooled nuclear reactor. An electrically insulating coating is applied on the surfaces of IGSCC-susceptible reactor components. The preferred electrically insulating material is yttria-stabilized zirconia. The presence of an electrically insulating coating on the surface of the metal components shifts the corrosion potential in the negative direction without the addition of hydrogen and in the absence of noble metal catalyst. Corrosion potentials .ltoreq.-0.5 V.sub.she can be achieved even at high oxidant concentrations and in the absence of hydrogen.
摘要:
A method for mitigating general corrosion and crack initiation and growth on the surface of a 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 or atoms of the non-noble metal which incorporate in 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 incorporated in the oxided surface of a metal component will reduce the electrochemical corrosion potential at the surface to a level below the critical potential to protect against intergranular stress corrosion cracking without the addition of hydrogen.
摘要:
A method for improving the performance and longevity of coatings of metal deposited from aqueous solutions of inorganic, organic or oraganometallic metal compounds. The method involves co-deposition of noble metal or corrosion-inhibiting non-noble metal during growth of oxide film on a component made of alloy, e.g., stainless steels and nickel-based alloys. The result is a metal-doped oxide film having a relatively longer life in the reactor operating environment. In particular, incorporation of palladium into the film provides greatly increased catalytic life as compared to palladium coatings which lie on the oxide surface.
摘要:
A method for mitigating crack initiation and propagation on the surface of metal components in a water-cooled nuclear reactor. An electrically insulating coating doped with a noble metal is applied on the surfaces of IGSCC-susceptible reactor components. The preferred electrically insulating material is yttria-stabilized zirconia doped with palladium or platinum. The presence of an electrically insulating coating on the surface of the metal components shifts the corrosion potential in the negative direction without the addition of hydrogen. Corrosion potentials .ltoreq.-0.5 V.sub.SHE are believed to be achievable even at high oxidant concentrations and in the absence of hydrogen, although the coatings are believed to be particularly suited to applications where a reductant, such as hydrogen, is present.
摘要:
An apparatus and a method for measuring and controlling the crack growth rate within a double cantilever beam type test specimen. The arms of the test specimen are fitted with a pressure-actuated bellows to induce a predetermined load and with a sensing assembly to provide feedback on the amount of beam displacement resulting from application of that load. In this manner a loaded test specimen may be remotely mounted and adjusted inside the reactor pressure vessel or piping of a nuclear reactor in order to maintain a stress intensity which is constant or which varies in a predetermined manner for inducing stress corrosion cracking or corrosion fatigue in the specimen.
摘要:
A high-chromium stainless steel alloy having improved resistance to stress corrosion cracking in high temperature water is comprised of, in weight percent; about 22 to 32 percent chromium, about 16 to 40 percent nickel, up to about 10 percent manganese, up to about 0.06 percent carbon, and the balance substantially iron. A preferred high-chromium alloy is further comprised of about 2 to 9 weight percent of a metal from the group consisting of titanium, niobium, tantalum, and mixtures thereof. Another preferred high-chromium alloy is further comprised of a platinum group metal in an effective amount to reduce the corrosion potential of the alloy in high-temperature water provided with hydrogen.
摘要:
A method for lowering the corrosion potential on components formed from carbon steel, alloy steel, stainless steel, nickel based alloys, or cobalt based alloys, and exposed to high-temperature water comprised of oxidizing species, comprising: providing a reducing species in the high temperature water that can combine with the oxidizing species, and forming the component to have a catalytic layer of a platinum group metal.