Abstract: A method for at least partially disrupting or removing radioactive deposits formed on a surface of a structure in a nuclear water reactor is disclosed. The method includes identifying the structure, taking the structure out of operational service, isolating the structure, contacting the surface of the structure with an aqueous solution, and adding an effective amount of an elemental metal in solid form to the aqueous solution. The effective amount includes an amount to at least partially disrupt or remove the radioactive deposits formed on the surface of the structure. The method is conducted at ambient temperature. The radioactive deposits include oxide-containing radionuclides deposited on the surface. The surface is a primary side structure in the nuclear water reactor.

Abstract: A nuclear power plant comprising a primary coolant circuit, a steam-water circuit separated from the primary coolant circuit and a steam generator connected to the primary coolant circuit and the steam-water circuit to transfer heat from the primary coolant circuit into the steam-water circuit has at least one dosing point in the steam-water circuit to inject a reducing agent into the steam-water circuit, wherein the reducing agent is an organic compound consisting of carbon, hydrogen and oxygen. Furthermore, a method for operating said nuclear power plant and the use of the method for downtime preservation of the secondary side of a steam generator of a nuclear power plant are provided.

Abstract: A recirculating cooling system includes a coolant sampling line, a deterministic lateral displacement (DLD) microfluidic separation device, a monitoring device, and an alert generation device. The coolant sampling line is in fluid communication with a recirculating coolant line, and the DLD microfluidic separation device receives a coolant sample diverted into the coolant sampling loop from the recirculating coolant line via the coolant sampling line. The DLD microfluidic separation device includes a separation array for separating bacteria into an output channel according to a size threshold. The monitoring device monitors a characteristic property of the coolant sampling loop for comparison to a threshold for bacterial growth in the recirculating cooling system. The alert generation device generates an alert to remediate the bacterial growth in the recirculating cooling system responsive to the characteristic property of the coolant sampling loop satisfying the threshold.

Abstract: The present disclosure provides a method for relieving a corrosive environment of a boiling water reactor, the method including a step of injecting hydrogen and a noble metal compound into water to be replenished into the reactor pressure vessel during a period of a generating operation of a boiling water nuclear power plant including the reactor pressure vessel. In the method, the hydrogen is injected into water to be supplied into the reactor pressure vessel, and the noble metal compound is injected into water in a line of the boiling water nuclear power plant in which a concentration of oxygen or hydrogen peroxide is stoichiometrically higher than the concentration of hydrogen at which hydrogen undergoes a chemical reaction to turn to water.

Abstract: 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.

Abstract: A chemical solution injection system 30 of an embodiment includes: a chemical solution reservoir 31 that stores a chemical solution containing a depositing substance to deposit to a member in contact with cooling water for absorbing heat in a plant; a pipe 32 through which the chemical solution passes; a first heat exchanger and a second heat exchanger that exchange heat between the cooling water and the chemical solution; a cooling water pipe 49 which connects the heat exchangers in series and in which the cooling water passes; and a pump 34 that conveys the chemical solution. The temperature of the chemical solution in the chemical solution reservoir 31 is lower than that of the cooling water. The pipe 32 sequentially connects the chemical solution reservoir 31, the first heat exchanger, the second heat exchanger and the plant. The cooling water guided from the inside of the plant passes through the second heat exchanger and subsequently passes through the first heat exchanger.

Abstract: The present invention provides a corrosion-resistant structure for a high-temperature water system comprising: a structural material 1; and a corrosion-resistant film 3 formed from a substance containing at least one of La and Y deposited on a surface in a side that comes in contact with a cooling water 4, of the structural material 1 which constitutes the high-temperature water system that passes a cooling water 4 of high temperature therein. Due to above construction, there can be provided the corrosion-resistant structure and a corrosion-preventing method capable of operating a plant without conducting a water chemistry control of cooling water by injecting chemicals.

Abstract: A radiation source reducing system and method for nuclear power plants whereby radiation source can be reduced are provided. The radiation source reducing system for nuclear power plants includes a dispersant injecting unit, which injects a dispersant into a coolant of a nuclear power plant coolant system. The dispersant is polyacrylic acid, and has an average molecular weight in a range of 16000 to 26000, inclusive.

Abstract: 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.

Abstract: 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.

Abstract: Example embodiments of the present invention relate to a method of adjusting an oxygen concentration of a reactor water side stream in a nuclear plant. The method may include injecting demineralized water into the reactor water side stream to produce an oxygenated stream with an increased oxygen concentration. The oxygenated stream may be tested to determine the effect of a process treatment on the reactor system.

Abstract: A nuclear reactor fuel integrity monitor includes: a ?-ray detector which detects ?-ray of a specific radionuclide of a subject measurement medium of a nuclear reactor; a sample container which retains the subject measurement medium therein and surrounds the circumference of the ?-ray detector; and a measurement control device which performs a control so that a predetermined amount of the subject measurement medium is introduced into the sample container and calculates a concentration of the specific radionuclide from ?-ray data per each unit time detected by the ?-ray detector and a volume of the subject measurement medium introduced into the sample container.

Abstract: A method of and apparatus for optimizing a hydrogen producing system is provided. The method of optimizing the hydrogen producing system comprises producing hydrogen gas using a hydrogen producing formulation and removing a chemical substance that reduces the hydrogen gas producing efficiency. Further, the hydrogen producing system comprises a hydrogen producing catalyst, a hydrogen generating voltage applied to the hydrogen producing catalyst to generate hydrogen gas, and a catalyst regenerating device to regenerate the hydrogen producing catalyst to a chemical state capable of generating the hydrogen gas when a hydrogen generating voltage is applied.

Abstract: 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.

Abstract: An object is to reduce radiation exposure in a nuclear plant. A nuclear plant 1 is a nuclear power generating plant where steam is generated by thermal energy generated by nuclear fission of a nuclear fuel 2C in a nuclear reactor 2, and a turbine 8 is driven by the steam to generate heat by a power generator 10. After a nuclear plant 1 is newly constructed, when a primary cooling system of the nuclear reactor 2 raises the temperature to around a power operation temperature for the first time, zinc is injected into a primary coolant C1 present in the primary cooling system by a zinc injector 20.

Abstract: 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.

Abstract: 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.

Abstract: 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 (S11), converting the injected metal ions into metal particles by a chemical reaction with hydrogen (H2), hydrazine (N2H4), or amine in water (S12), and forming an insulating layer or a catalyst layer by depositing metal particles or metal nanoparticles on a metal surface or an oxide coating film of the cooling or circulating system (S13).

Abstract: A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form is provided. The nanoparticles are delivered in locations such as the cold leg accumulator and high and low pressure pumps of an emergency core cooling system. Motor driven valves and pressurization can aid in the delivery. Methods for providing the nanoparticles are also provided.

Abstract: A radiation exposure reduction method includes the steps of: injecting iron into a coolant which flows from the reactor cooling system to the reactor core in a nuclear power plant; and ferritizing and fixing radionuclides or parent nuclides thereof, which are contained in the coolant, on the surface of a reactor core structure, wherein an iron citrate which is soluble organic iron, or iron oxalate or iron fumarate which has a particle diameter of 3 ?m or less, is used as the iron to be injected into the coolant.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: In a nuclear power plant, a corrosion-resistant oxide film on a surface of the metal component of a reactor structure is exposed to a high-temperature water, the corrosion-resistant oxide film containing an oxide having a property of a P-type semiconductor, and a catalytic substance having a property of an N-type semiconductor is deposited on the oxide film. The oxide film maintains the property of the P-type semiconductor.

Abstract: In a nuclear power plant, a corrosion-resistant oxide film on a surface of the metal component of a reactor structure is exposed to a high-temperature water, the corrosion-resistant oxide film containing an oxide having a property of a P-type semiconductor, and a catalytic substance having a property of an N-type semiconductor is deposited on the oxide film. The oxide film maintains the property of the P-type semiconductor.

Abstract: Disclosed is a basket 50 that is located within a basket containment vessel, into which a boric acid solution capable of dissolving a pH adjuster flows, and can allow a pH adjuster solution to flow out by the inflowing boric acid solution. The basket 50 includes a plurality of containment units 71 stacked in a vertical direction with a predetermined first space L1 therebetween. The pH adjuster can be stored in each of the containment units 71. Also disclosed is a pH adjusting device including the basket 50, the basket containment vessel in which the basket 50 can be contained and in which cooling water can be stored, and an overflow pipe that, within the basket containment vessel, allows the pH adjuster solution that is obtained from the pH adjuster dissolved in the cooling water to flow out.

Abstract: A bath containing nickel ions and formic acid is injected into a film-forming aqueous solution flowing in a circulation pipe connected to feed water pipe made of carbon steel in a BWR plant. This film-forming aqueous solution is supplied into the feed water pipe through the circulation pipe, and then, a nickel metal film is formed on an inner surface of the feed water pipe. After the nickel metal film is formed, a film-forming aqueous solution containing iron (II) ions, formic acid, nickel ions, hydrogen peroxide, and hydrazine is supplied to the feed water pipe. A nickel ferrite film is formed on the surface of the nickel metal film in the feed water pipe. Then, the nickel ferrite film is come into contact with water containing dissolved-oxygen at 150° C. or above to transform the nickel metal film into a nickel ferrite film. A thick nickel ferrite film is formed on the inner surface of the feed water pipe. Corrosion of the carbon steel member composing the plant can further reduce.

Abstract: A bath containing nickel ions and formic acid is injected into a film-forming aqueous solution flowing in a circulation pipe connected to a feed water pipe made of carbon steel in a BWR plant. This solution is supplied into the pipe through the circulation pipe, and a nickel metal film is formed on an inner surface of the pipe. After the film is formed, a film-forming aqueous solution containing iron (II) ions, formic acid, nickel ions, hydrogen peroxide, and hydrazine is supplied to the pipe. A nickel ferrite film is formed on the surface of the nickel metal film in the pipe. The nickel ferrite film comes into contact with water containing dissolved oxygen at or above 150° C. to transform the nickel metal film into a nickel ferrite film. A thick nickel ferrite film is formed on the inner surface of the feed water pipe.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: This invention relates to a nuclear plant having a reactor vessel and a fluid circuit including flow path defining means, defining a flow path for circulating a reactor coolant fluid from and to the reactor vessel. The nuclear plant includes a particle collection zone defined along at least part of the length of the flow path, and particle deflection means arranged in particle deflecting relationship with the flow path to deflect particles from a fluid stream in the flow path into or toward the particle collection zone.

Abstract: In a nuclear power plant, a corrosion-resistant oxide film on a surface of the metal component of a reactor structure is exposed to a high-temperature water, the corrosion-resistant oxide film containing an oxide having a property of a P-type semiconductor, and a catalytic substance having a property of an N-type semiconductor is deposited on the oxide film. The oxide film maintains the property of the P-type semiconductor.

Abstract: 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.

Abstract: A pH adjusting apparatus arranged above a water pit for refueling disposed in a reactor container that stores a nuclear reactor includes a pH adjuster, a basket 50 that contains the pH adjuster, and a basket housing container 51 that houses the basket 50 therein and has formed therein an inlet through which a solvent for dissolving or diluting the pH adjuster flows in and an overflow pipe 52 through which a pH-adjusted solution generated by dissolving or mixing the pH adjuster in the solvent flows out to the water pit for refueling. Consequently, even if it is difficult to dispose the basket 50 on a floor of the water pit for refueling, it is possible to suitably perform pH adjustment in the reactor container.

Abstract: 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.

Abstract: 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.

Abstract: 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 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.

Abstract: A measuring device for carrying out purity measurements in a media circuit of a power station with an ion exchanger device and a measuring means for measuring a parameter of a media current flowing through the ion exchanger device is described. In order to obtain measurements in a rapid and reliable manner at the start up of the ion exchanger device, for example during the start-up phase of the power station, it is suggested that the ion exchanger device has two flow paths for two different operating modes of the power station.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: An injection system designed to deliver a chemical solution into a reactor through feedwater system taps during normal operating condition of a power reactor is disclosed. The process of delivery is via positive displacement pumps. Injection of chemical is in a concentrated solution form, which is internally diluted by the system prior to discharging from the skid. The injection system minimizes chemical loss due to deposition on the transit line, enables a higher concentrated solution to be used as the injectant, eliminates the time consuming laborious process of chemical dilution, raises chemical solution to the pressure required for injection, prevents solid precipitations out of solution at the injection pump head through the use of a flush solution, and deposits fresh chemical on new crack surfaces that develop during a power reactor start-up, shutdown and operation.

Abstract: A pH adjusting system includes a water pit for refueling 35 that is disposed in a reactor container 10, which stores a reactor, and is capable of storing cooling water and a pH adjusting apparatus 37 that is disposed above the water pit for refueling 35 and houses a pH adjuster. The pH adjusting apparatus 37 causes a pH-adjusted solution generated by dissolving or mixing the pH adjuster to flow out to the water pit for refueling 35 below the pH adjusting apparatus 37. Consequently, even when it is difficult to dispose the pH adjusting apparatus on a floor of the water pit for refueling, it is possible to suitably perform pH adjustment in the reactor container 10.

Abstract: 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.

Abstract: An object is to reduce radiation exposure in a nuclear plant. A nuclear plant 1 is a nuclear power generating plant where steam is generated by thermal energy generated by nuclear fission of a nuclear fuel 2C in a nuclear reactor 2, and a turbine 8 is driven by the steam to generate heat by a power generator 10. After a nuclear plant 1 is newly constructed, when a primary cooling system of the nuclear reactor 2 raises the temperature to around a power operation temperature for the first time, zinc is injected into a primary coolant C1 present in the primary cooling system by a zinc injector 20.