| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376305000 | Corrosion or damage prevention | 43 |
| 20080226012 | Proliferation-Resistant Nuclear Reactor - Proliferation-resistant nuclear reactors are disclosed according to some aspects. In one embodiment the proliferation-resistant nuclear reactor comprises a plurality of spherically-shaped micro-fuel elements (MFEs), each comprising a MFE core having one or more fuel kernels, a buffer external to the fuel kernels, and one or more coatings external to the MFE core providing corrosion resistance, erosion resistance, fission product containment, or a combination thereof. The MFEs are not suspended in a solid material and each MFE is sized such that its delay time is less than its accident time. The nuclear reactor further comprises a reactor core containing at least a portion of the plurality of MEs, wherein the reactor core is configured for cross-flow of a coolant. | 09-18-2008 |
| 20090003507 | METHOD AND APPARATUS FOR SUPPRESSING CORROSION OF CARBON STEEL, METHOD FOR SUPPRESSING DEPOSIT OF RADIONUCLIDE ONTO CARBON STEEL MEMBERS COMPOSING A NUCLEAR POWER PLANT, AND FILM FORMATION APPARATUS - The present invention is a method for suppressing corrosion of carbon steel members composing a nuclear power plant. That is, the processing solution contains a chemical including iron (II) ions, an oxidizing agent for oxidizing at least one part of the iron (II) ions into iron (III) ion, and a pH adjustment agent for adjusting pH. The pH of the processing solution is adjusted in the range of 5.5 to 9.0 by the pH adjustment agent. The processing solution is introduced into a purifying system pipe having the carbon steel members. The iron (II) ions are adsorbed on an inner surface of the purifying system pipe, namely, a surface of the carbon steel members. The ferrite film is formed on the surface of the carbon steel members by oxidizing the absorbed iron (II) ions. Therefore, corrosion of the carbon steel members is suppressed by the ferrite film. | 01-01-2009 |
| 20090003508 | Method of suppressing deposition of radioactive isotope - A formic acid aqueous solution that contains Fe (II) ions is produced by dissolving metal iron in a formic acid aqueous solution. Nitrogen is supplied from a nitrogen supply device to a chemical liquid tank and then discharged from a discharge line to reduce the dissolved oxygen concentration in the aqueous solution. The chemical liquid tank is filled with the formic acid aqueous solution sealed with nitrogen, and is transferred from a factory to a nuclear reactor building designated as radiation-controlled areas. Inside the nuclear reactor building, the chemical liquid tank is installed in a film deposition apparatus connected to a reactor water recirculation pipeline. The formic acid aqueous is supplied from the chemical liquid tank to the inside of the reactor water recirculation pipeline, and then a ferrite film is formed on the inner surface of the reactor water recirculation pipeline. | 01-01-2009 |
| 20090010377 | INHIBITOR OF CORROSION AND STRESS CORROSION CRACKING CONTAINING NICKEL BORIDE (NiB) IN THE SECONDARY SIDE OF STEAM GENERATOR TUBES IN A NUCLEAR POWER PLANT AND INHIBITING METHOD USING THE SAME - A method of inhibiting corrosion and stress corrosion cracking of a steam generator tube in a nuclear power plant, includes the steps of providing a nuclear power plant having a secondary side feedwater system including a secondary side feedwater of a steam generator tube; and supplying nickel boride to said secondary side feedwater to inhibit corrosion and stress corrosion cracking. | 01-08-2009 |
| 20090046825 | Protective coating applied to metallic reactor components to reduce corrosion products into the nuclear reactor environment - An insulating coating is applied to the metallic components in a nuclear reactor water environment to decrease and/or mitigate general corrosion and erosion-corrosion of the reactor component's metallic surfaces. Preferably, the coating is a 0.1 micron to 0.3 mm thin layer of an oxide coating such as titania (TiO | 02-19-2009 |
| 20090141849 | Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant and Ferrite Film Formation Apparatus - A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film. | 06-04-2009 |
| 20090190712 | METHOD OF STRESS CORROSION CRACKING MITIGATION FOR NUCLEAR POWER PLANT STRUCTURAL MATERIALS - The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc. | 07-30-2009 |
| 20090290675 | METHOD AND APPARATUS FOR SUPPRESSING CORROSION OF CARBON STEEL, METHOD FOR SUPPRESSING DEPOSIT OF RADIONUCLIDE ONTO CARBON STEEL MEMBERS COMPOSING A NUCLEAR POWER PLANT, AND FILM FORMATION APPARATUS - The present invention is a method for suppressing corrosion of carbon steel members composing a nuclear power plant. That is, the processing solution contains a chemical including iron (II) ions, an oxidizing agent for oxidizing at least one part of the iron (II) ions into iron (III) ion, and a pH adjustment agent for adjusting pH. The pH of the processing solution is adjusted in the range of 5.5 to 9.0 by the pH adjustment agent. The processing solution is introduced into a purifying system pipe having the carbon steel members. The iron (II) ions are adsorbed on an inner surface of the purifying system pipe, namely, a surface of the carbon steel members. The ferrite film is formed on the surface of the carbon steel members by oxidizing the absorbed iron (II) ions. Therefore, corrosion of the carbon steel members is suppressed by the ferrite film. | 11-26-2009 |
| 20100014624 | Nuclear reactor components including material layers to reduce enhanced corrosion on zirconium alloys used in fuel assemblies and methods thereof - Example embodiments are directed to providing a thin, adherent coating on the surfaces of nuclear reactor components, which are known to cause increased corrosion on adjacent zirconium alloy structures, and methods of reducing the increased corrosion. Example embodiments include coatings being structurally bonded to components such that the difference in the corrosion potential between a coated component and a zirconium alloy component is less than that between a component without the coating and the zirconium alloy component. | 01-21-2010 |
| 20100091930 | APPARATUS FOR FORMING STRESS CORROSION CRACKS - An apparatus for forming stress corrosion cracks comprises a heating unit which includes a conductive member and a heating coil disposed adjacent to the conductive member to generate steam pressure in the tube specimen, an end holding unit, and a control unit for controlling the heating unit and the end holding unit. The stress corrosion cracks occurring in the equipment of nuclear power plants or apparatus industries during operation can be directly formed in a tube specimen using steam pressure under conditions similar to those of the actual environment of nuclear power plants, thus increasing accuracy for analysis of properties of stress corrosion cracks which are in actuality generated, thereby improving reliability of nuclear power plants or apparatus industries and effectively assuring nondestructive testing capability, resulting in very useful industrial applicability. | 04-15-2010 |
| 20120069949 | METHOD OF AND SYSTEM FOR SUPPRESSING DEPOSITION OF RADIOACTIVE SUBSTANCE - A radioactive substance is effectively suppressed by an oxide-film removal step of removing an oxide film on a metallic material surface with which a coolant containing the radioactive substance comes in contact, and a titanium-oxide deposition step of depositing a titanium oxide on the metallic material surface after the oxide film has been removed. | 03-22-2012 |
| 20120230459 | METHOD OF IMPROVING WEAR AND CORROSION RESISTANCE OF ROD CONTROL CLUSTER ASSEMBLIES - The present invention relates to tubular elements, such as fuel assembly tubes, which are designed to be used in high pressure and high temperature water in nuclear reactors, such as pressurized water nuclear reactors. In particular, the present invention relates to a method of improving wear resistance and corrosion resistance by depositing a protective coating having a depth of from about 5 to about 25 μm on the surface of the tubular elements. The coating is provided by nitriding the tubular element at a temperature of from about 400° C. to about 440° C. The nitridation of the tubular element can be carried out for a duration of from about 12 hours to about 40 hours. | 09-13-2012 |
| 20130070888 | METHOD OF REDUCING CORROSION OF NUCLEAR REACTOR STRUCTURAL MATERIAL - In a method of reducing corrosion of a material constituting a nuclear reactor structure, an electrochemical corrosion potential is controlled by injecting a solution or a suspension containing a substance generating an excitation current by an action of at least one of radiation, light, and heat existing in a nuclear reactor, or a metal or a metallic compound forming the substance generating the excitation current under the condition in the nuclear reactor to allow the substance generating the excitation current to adhere to the surface of the nuclear reactor structural material, and by injecting hydrogen in cooling water of the nuclear reactor while controlling the hydrogen concentration in a feed water. | 03-21-2013 |
| 20130182814 | METHOD FOR SUPPRESSING CORROSION IN PLANT AND PLANT - In a plant including a system which is provided with a steam generator | 07-18-2013 |
| 20140029712 | DIELECTRIC COATING FOR SURFACES EXPOSED TO HIGH TEMPERATURE WATER - Example embodiments relate to a method and apparatus for reducing electrostatic deposition of charged particles on wetted surfaces that are exposed, periodically or substantially continuously, to high velocity fluid flow within a coolant flow path in a nuclear reactor. The method may include depositing a first or base dielectric layer and a second or outer dielectric layer on a conductive surface that forms a portion of a high velocity flow path to attain the apparatus. The first dielectric layer material is selected to provide improved adhesion and insulation to the conductive surface and the second dielectric layer material is selected to provide suitable adhesion to the first dielectric layer and improved corrosion and/or mechanical resistance in the anticipated operating environment. | 01-30-2014 |
| 20140177777 | STARTUP/SHUTDOWN HYDROGEN INJECTION SYSTEM FOR BOILING WATER REACTORS (BWRS), AND METHOD THEREOF - A system and a method for injecting hydrogen into Boiling Water Reactor (BWR) reactor support systems in operation during reactor startup and/or shutdown to mitigate Inter-Granular Stress Corrosion Cracking (IGSCC). The system may provide hydrogen at variable pressures (including relatively higher pressures) that match changing operating pressures of the reactor supports systems as the reactor cycles through startup and shutdown modes. | 06-26-2014 |
| 20140334592 | FUEL ROD ASSEMBLY AND METHOD FOR MITIGATING THE RADIATION-ENHANCED CORROSION OF A ZIRCONIUM-BASED COMPONENT - There is provided a fuel rod assembly comprising a first component of a zirconium-based material. The first component is in contact with or is located adjacent to a second component of a material different from the zirconium-based material, e.g. a nickel-based or iron-based alloy. A coating is disposed on an outer surface of the first component, which is effective to reduce an electrochemical corrosion potential difference between the first component and the second component relative to an electrochemical corrosion potential difference between the first component and the second component without the coating. | 11-13-2014 |
| 376306000 | By addition of material to coolant | 26 |
| 20080292042 | Method of stress corrosion cracking mitigation for nuclear power plant structural materials - The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc. | 11-27-2008 |
| 20090316852 | METHOD FOR SUPPRESSING DEPOSIT OF RADIONUCLIDE ONTO STRUCTURE MEMBER COMPOSING NUCLEAR POWER PLANT AND FERRITE FILM FORMATION APPARATUS - A method for suppressing deposit of radionuclide onto structure member composing a nuclear power plant, comprising the steps of:
| 12-24-2009 |
| 20100020915 | METHOD OF RENDERING A RADIOACTIVE AND AQUEOUS HEAT TRANSFER LIQUID IN A NUCLEAR REACTOR TO A REDUCED RADWASTE QUANTITATIVE STATE AND RETURNING THE REMAINING WASTE WATER VOLUMES TO AN ENVIRONMENTAL RELEASE POINT FOR LIQUID EFFLUENTS - Environmentally protective Method of treating an aqueous radioactive fluid (AF) in a nuclear reactor cycle or radwaste system to selectively capture or remove radioactive isotopes in a reduced quantitative package to minimize radwaste generated and revitalize neutron absorption capacity of nuclear reactor coolant by separately carrying away boron constituents, when B | 01-28-2010 |
| 20100027731 | BWR START UP CORROSION PROTECTION - The oxidizing chemistry environment of BWR reactor water is a key factor promoting intergranular stress corrosion cracking of stainless steel and nickel based alloys used in reactor coolant system piping and vessel internals. This is typically mitigated during power operation with hydrogen injection. However, this method is only effective when the reactors are at power. Accordingly, this invention proposes a method of reducing electrochemical corrosion potential during the start-up phase of BWR reactors. The method includes the steps of providing a mitigation additive adapted to reduce electrochemical corrosion of a BWR reactor; and injecting the mitigation additive into the BWR reactor at a predetermined location prior to hydrogen injection coming online. | 02-04-2010 |
| 20100074389 | Replacement basket, a system using the replacement basket, and a method for loading the replacement basket - Provided is a replacement basket configured to house a pellet bed through which fluid may pass. The flow direction of the fluid prevents the bed of pellets from fluidizing within the replacement basket. Provided also is a system using the replacement basket and a method of providing pellets in the replacement basket. According to example embodiments, a replacement basket may include a top surface portion, a bottom, and at least one vertical wall with a hole. The hole is configured to allow a flow of fluid to enter the replacement basket. A plenum, below the pellet bed, may allow a flow of fluid to proceed through the pellet bed in a downward direction. A central pipe may be provided in the replacement basket to allow the flow of fluid in the basket to exit the replacement basket. | 03-25-2010 |
| 20100080335 | Boiling water reactor nuclear power plant with alcohol injection - A nuclear power plant is provided including a BWR, a reactor cooling system cooling the BWR, an HWC hydrogen injection system connected to the reactor cooling system and an alcohol injection system connected to the reactor cooling system. Methods for providing methanol and hydrogen are also provided. | 04-01-2010 |
| 20100135450 | Crystal Habit Modifiers for Nuclear Power Water Chemistry Control of Fuel Deposits and Steam Generator Crud - Crystal habit modifiers (CHM) are provided to ameliorate deposit-related concerns in nuclear plant systems. The principal targets for utilization of crystal habit modifiers are Pressure Water Reactor (PWR) primary-side fuel rod crud and secondary-side steam generator deposits and Boiling Water Reactor (BWR) coolant system deposits. | 06-03-2010 |
| 20100246745 | Methods for operating and methods for reducing post-shutdown radiation levels of nuclear reactors - 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. | 09-30-2010 |
| 20100246746 | PROCESS FOR ADDING AN ORGANIC COMPOUND TO COOLANT WATER IN A PRESSURIZED WATER REACTOR - The present invention relates generally to a process for a pressurized water reactor. The pressurized water reactor includes a primary circuit and a reactor core. The process includes adding a sufficient amount of an organic compound to coolant water passing through the primary circuit of the pressurized water reactor. The organic compound includes elements of carbon and hydrogen for producing elemental carbon. | 09-30-2010 |
| 20100290577 | NUCLEAR REACTOR HAVING EFFICIENT AND HIGHLY STABLE THERMAL TRANSFER FLUID - A pressurized water nuclear reactor (PWNR) | 11-18-2010 |
| 20100329410 | BASKET AND pH ADJUSTING DEVICE - Disclosed is a basket | 12-30-2010 |
| 20110075785 | METHOD OF OPERATING NUCLEAR PLANT - An object is to reduce radiation exposure in a nuclear plant. A nuclear plant | 03-31-2011 |
| 20110176649 | Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant - A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film. | 07-21-2011 |
| 20120039429 | PLANT OPERATION METHOD AND PLANT OPERATION SYSTEM - The present invention provides an operation method of a plant which has a low-pressure feed water heater, a deaerator and a high-pressure feed water heater sequentially arranged in a feed water pipe reaching a steam generator from a condenser, and leads high-temperature feed water to the steam generator, wherein an oxidant is injected onto a surface of a structural material from an oxidant injection line in order to form a film that suppresses an elution of an element constituting the structural material such as the feed water pipe, the low-pressure feed water heater, the deaerator and the high-pressure feed water heater, which come in contact with the high-temperature feed water, and a corrosion suppression substance is further introduced from a corrosion suppression substance introduction line in order to deposit the corrosion suppression substance on a surface of the structural material in which corrosion accelerated by a flow of the feed water occurs. | 02-16-2012 |
| 20120263269 | METHOD OF REDUCING CORROSION OF NUCLEAR REACTOR STRUCTURAL MATERIAL - In a method of reducing corrosion of a material constituting a nuclear reactor structure, an electrochemical corrosion potential is controlled by injecting a solution or a suspension containing a substance generating an excitation current by an action of at least one of radiation, light, and heat existing in a nuclear reactor, or a metal or a metallic compound forming the substance generating the excitation current under the condition in the nuclear reactor to allow the substance generating the excitation current to adhere to the surface of the nuclear reactor structural material, and by injecting hydrogen in cooling water of the nuclear reactor while controlling the hydrogen concentration in a feed water. | 10-18-2012 |
| 20120288050 | PROCESS FOR ADDING AN ORGANIC COMPOUND TO COOLANT WATER IN A PRESSURIZED WATER REACTOR - The present invention relates generally to a process for a pressurized water reactor. The pressurized water reactor includes a primary circuit and a reactor core. The process includes adding a sufficient amount of an organic compound to coolant water passing through the primary circuit of the pressurized water reactor. The organic compound includes elements of carbon and hydrogen for producing elemental carbon. | 11-15-2012 |
| 20130251086 | REACTOR DECONTAMINATION PROCESS AND REAGENT - The present application is related to a concentrated decontaminating reagent composition and related method useful for decontamination of nuclear reactors, or components thereof. The concentrated reagent composition is injected into the nuclear reactor, or component thereof, to form a dilute reagent that comprises from about 0.6 to about 3.0 g/L (2.1-10.3 mM) EDTA and from about 0.4 to about 2.2 g/L (2.1-11.5 mM) citric acid. The composition and method of this application can be used effectively in a regenerative process to decontaminate a nuclear reactor, or a component of thereof, with high efficiency without causing significant corrosion to the components of the cooling systems. | 09-26-2013 |
| 20130272476 | METHOD FOR PROTECTING COMPONENTS OF A PRIMARY SYSTEM OF A BOILING WATER REACTOR IN PARTICULAR FROM STRESS CORROSION CRACKING - A method for protecting the components of the primary system of a boiling water reactor, especially against stress cracking corrosion, includes feeding a reducing agent into the primary coolant in order to reduce the number of substances having a oxidizing effect or in order to modify the electrochemical potential of the component surfaces covered with an oxide layer to negative values. An alcohol that can be oxidized in the conditions of a reactor is fed in as a reducing agent, preferably in a liquid form, into the primary coolant. The component surfaces are provided with a blank coating or a single intrinsic oxide coating. | 10-17-2013 |
| 20140037037 | Method of Depositing Noble Metal on Structure Member of Nuclear Plant - A noble metal injection apparatus is connected to a piping of a nuclear plant at the time of stop of the nuclear plant before start of the nuclear plant. In chemical decontamination, oxidation decontamination agent decomposition, and reduction decontamination on an inner surface of the pipe system are executed. After reduction decontamination, a part of an oxalic acid included in a reduction decontamination solution is decomposed and platinum is injected into the reduction decontamination solution of pH 3.5 or higher. When the platinum concentration becomes a preset concentration, a reduction agent is injected and the reduction decontamination solution including the platinum and reduction agent is brought into contact with the inner surface of the piping. The platinum is deposited on the inner surface of the piping. The injection of the platinum and reduction agent is stopped and the platinum and reduction agent are decomposed. | 02-06-2014 |
| 20140140465 | Platinum Oxide Colloidal Solution, Manufacturing Method Therefor, Manufacture Apparatus Thereof, and Method of Injection Noble Metal of Boiling Water Nuclear Power Plant - An aqueous solution of alkali hexahydroxo platinate is produced. As a alkali hexahydroxo platinate, sodium hexahydroxoplatinate or potassium hexahydroxoplatinate is used. The aqueous solution of alkali hexahydroxo platinate is passed through a hydrogen form cation exchange resin layer in a cation exchange resin tower. The aqueous solution of alkali hexahydroxo platinate makes contact with the hydrogen form cation exchange resin of the hydrogen form cation exchange resin layer, thus a suspension of hexahydroxo platinic is generated. If gamma rays are irradiated to the suspension, a platinum oxide colloidal solution in which colloidal particles including a platinum dioxide, a platinum monoxide, and a platinum hydroxide exist is generated. In a platinum oxide colloidal solution, the content of impurities is little and a noble metal compound is dispersed stably in water. | 05-22-2014 |
| 20140211903 | METHOD OF OPERATING A POWER GENERATOR BASED ON NOBLE METAL INDUCED OXIDATION OF A HEAT TRANSFER SURFACE - A method of operating a power generator is provided. The method includes determining an amount of oxides on a heat transfer surface of the power generator as a function of a concentration of a noble metal substance in the oxides; and altering operation of the power generator when the amount of oxides on the heat transfer surface reaches a predetermined value. A method of operating a nuclear reactor is also provided. | 07-31-2014 |
| 20150085966 | METHOD OF REFORMING METAL SURFACE OF COOLING OR CIRCULATING SYSTEM OF NUCLEAR OR THERMAL POWER PLANT - A method of reforming a metal surface of a cooling or circulating system of a nuclear or thermal power plant is provided. The method of reforming a metal surface of a cooling or circulating system of a nuclear or thermal power plant includes injecting metal ions or metal nanoparticles into a cooling or circulating system of a nuclear or thermal power plant (S | 03-26-2015 |
| 20150085967 | RADIATION SOURCE REDUCING SYSTEM AND METHOD FOR NUCLEAR POWER PLANT - Provided are radiation source reducing system and method for nuclear power plants whereby radiation source can be reduced. This radiation source reducing system for nuclear power plants is characterized in being provided with a dispersant injecting unit, which injects a dispersant into a coolant of a nuclear power plant coolant system. | 03-26-2015 |
| 20150117587 | AMBIENT TEMPERATURE DECONTAMINATION OF NUCLEAR POWER PLANT COMPONENT SURFACES CONTAINING RADIONUCLIDES IN A METAL OXIDE - This invention generally concerns radioactive decontamination of deposits on components in a nuclear power plant and is specifically concerned with improved systems and methods for disrupting, dissolving, removing and reducing at ambient temperature radionuclides formed on the primary side surfaces of components in a pressurized water reactor and the internal components of a boiling water reactor. The methods include identifying the structure, taking the structure out of operational service, contacting the structure with an aqueous solution (e.g., a recirculating flow or static immersion), and adding an effective amount of elemental metal in solid form to the aqueous solution. | 04-30-2015 |
| 20160035442 | CHEMICAL PROCESS FOR PRIMARY SYSTEM MATERIAL PASSIVATION DURING HOT FUNCTIONAL TESTING OF NUCLEAR POWER PLANTS - The present invention relates to a pre-core hot functional testing (HFT) preconditioning process, which includes the introduction of chemical additives, e.g., zinc, into coolant water that circulates through the primary system of a new nuclear power plant, at various temperatures. The chemical additives contact the primary system surfaces, which results in the formation of a protective zinc-containing oxide film on the fresh surfaces to control corrosion release and deposition during subsequent normal operation of the nuclear power plant. The method includes a series of three chemistry phases to optimize the passivation process: 1) an alkaline-reducing phase, 2) an acid-reducing phase and 3) an acid-oxidizing phase. | 02-04-2016 |
| 20170236604 | Platinum Oxide Colloidal Solution, Manufacturing Method Therefor, Manufacture Apparatus Thereof, and Method of Injection Noble Metal of Boiling Water Nuclear Power Plant | 08-17-2017 |
