摘要:
A method of reducing hydrogen absorption in fuel assembly (46) components fabricated from zirconium alloys in a nuclear reactor (10) is provided. The method includes, in an exemplary embodiment, depositing at least one noble metal on at least one surface of the fuel assembly component. Depositing at least one noble metal includes exposing the zirconium alloy fuel assembly components, outside the nuclear reactor, to an aqueous solution including at least one compound containing at least one noble metal.
摘要:
A method for mitigating crack growth on the surface of stainless steel or other alloy components in a water-cooled nuclear reactor wherein a solution or suspension of a compound containing a noble metal is injected into the coolant water along with a reducing agent. The presence of the reducing agent will assist in better deposition of the noble metal, for example, palladium, on metal surfaces, thereby increasing the noble metal loading and also improving the tenacity with which the noble metal is bound onto the metal. The extent of noble metal doping is important in providing a better (lower) ECP response of the metal in the presence of a stoichiometric ratio of H 2 to 0 2 , which reduces the hydrogen demand considerably. The more tenacious the noble metal is bound to the metal surface, the longer its expected life will be, particularly under in-reactor situations where the metal surfaces are subjected to a variety of hydrodynamic conditions.
摘要:
A composite particle (34) comprises a zinc containing compound (36) such as zinc oxide and a noble metal (38) such a platinum, and process for fabrication thereof. The particles facilitate simultaneous controlled introduction of the zinc and noble metal (38) species into a nuclear reactor.
摘要:
A method for improving the performance and longevity of coatings of metal deposited from aqueous solutions of inorganic, organic or organometallic 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 operating a nuclear reactor may include adding one or more chemicals to water in the reactor prior to reactor shutdown, during reactor shutdown, or prior to and during reactor shutdown. The one or more chemicals may trigger release of one or more radioactive substances from at least one out-of-core surface of the reactor into the reactor water. A method for reducing post-shutdown radiation levels of a nuclear reactor may include adding one or more chemicals to water in the reactor prior to reactor shutdown, during reactor shutdown, or prior to and during reactor shutdown. The one or more chemicals may include, for example, one or more metals, metal ions, metal compounds, metals and metal ions, metals and metal compounds, metal ions and metal compounds, or metals, metal ions, and metal compounds.
摘要:
Method for controlling erosion and cracking in a metal component of a nuclear reactor, particularly in the highly concentrated primary and secondary systems of a PWR, comprising creating a catalytic surface on the component; and generating a stoichiometric excess of reductant in the water of the reactor to reduce the oxidant concentration at the surface to substantially zero.
摘要:
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 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.