In order to ensure the structural integrity of a hood against a load such as pressure exerted from the outside of the hood, the present invention provides a steam dryer for a boiling water-type light-water reactor which ensures the stiffness of the hood without making the hood plate itself thicker, and which avoids lengthening the fabrication time or complicating the fabrication procedure. This steam dryer for a boiling water-type reactor comprises: a hood for guiding, to a steam dryer unit, steam separated by a gas-water separator installed above a reactor core made of a plurality of fuel assemblies disposed inside a nuclear reactor pressure vessel; a support ring; a skirt; and the steam dryer unit having a corrugated plate therein, the steam dryer being characterized in that the hood is made of a first hood plate disposed in the vertical direction, a reinforcing plate mounted on the first hood plate, a second hood plate disposed vertically above the first hood plate and the reinforcing plate, and a side plate disposed between the first hood plate and the steam dryer unit, and the reinforcing plate is formed such that the cross-section thereof is a concavo-convex shape.
G21C 15/16 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques comprenant des moyens de séparation du liquide et de la vapeur
Provided are an inspection apparatus and an inspection method capable of two-dimensionally detecting a range of recession. The inspection apparatus includes a probe group, an ultrasonic waveform recording unit (recording unit), and a computation unit. The probe group includes a plurality of vertical probes that are attached to the surface of an inspection target object and transmit and receive ultrasonic waves. The recording unit records a plurality of reception signals obtained by receiving the ultrasonic wave transmitted from a first probe by a plurality of probes other than the first probe. The computation unit calculates a plurality of attenuation indexes representing degrees of attenuation of a plurality of second reception signals received after a plurality of first reception signals, with respect to the plurality of first reception signals recorded before an occurrence of recession in the inspection target object among the plurality of reception signals.
Provided is a gas separation module that can enhance durability under high-temperature water vapor of a fixing member that fixes a filter member to a housing. A gas separation module 1 includes a filter member 2 that separates a specific gas from a mixture gas, a housing 3 that has an inflow port 35 through which the mixture gas flows into and houses the filter member 2, and a fixing member 4 that fixes the filter member 2 to the housing 3 and seals a gap between the filter member 2 and the housing 3. At least a part of an inflow side surface 42 facing the inflow port 35 of the housing 3 of surfaces of the fixing member 4 is covered with a protective layer 6. The protective layer 6 is formed of an inorganic material having a characteristic of shielding water vapor and having a characteristic of being superior in heat resistance to the fixing member.
B01D 63/04 - Modules à fibres creuses comprenant plusieurs ensembles à fibres creuses
B01D 53/22 - Séparation de gaz ou de vapeursRécupération de vapeurs de solvants volatils dans les gazÉpuration chimique ou biologique des gaz résiduaires, p. ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par diffusion
A power system, which can appropriately control an output power of a power plant, includes a power plant, a power transmission flow limiter inserted between the power plant and a substation via transmission lines and, and a control system, wherein the control system outputs to the power transmission flow limiter a power transmission flow limitation signal CP indicating that an output power P of the power plant should be limited; and the power transmission flow limiter limits the output power P of the power plant, which is transmitted via the transmission lines and on the basis of the power transmission flow limitation signal CP.
H02P 9/10 - Commande s'exerçant sur le circuit d'excitation de la génératrice afin de réduire les effets nuisibles de surcharges ou de phénomènes transitoires, p. ex. application, suppression ou changement brutal de la charge
F01K 11/02 - Ensembles fonctionnels de machines à vapeur caractérisés par des machines motrices faisant corps avec les chaudières ou les condenseurs les machines motrices étant des turbines
G21D 3/00 - Commande des installations à énergie nucléaire
H02P 101/20 - Adaptation particulière des dispositions pour la commande de génératrices pour turbines à vapeur
Provided is a power supply system that contributes to stabilization of a power system, and the like. A power supply system includes a control unit that uses at least a part of generated power of a photovoltaic power plant and a wind power plant that generate power with asynchronous power supplies as in-plant power to be used for a motor and another load during normal operation of a nuclear power plant that generates power with a main generator that is a synchronous power supply. The control unit uses at least a part of the generated power of the photovoltaic power plant and the wind power plant as the in-plant power during the normal operation of the nuclear power plant to reduce an in-plant ratio in the nuclear power plant.
H02J 3/18 - Dispositions pour réglage, élimination ou compensation de puissance réactive dans les réseaux
F03D 9/00 - Adaptations des mécanismes moteurs à vent pour une utilisation particulièreCombinaisons des mécanismes moteurs à vent avec les appareils qu’ils entrainentMécanismes moteurs à vent spécialement adaptés à l’installation dans des endroits particuliers
6.
PLANT RELIABILITY EVALUATION SYSTEM, PLANT RELIABILITY EVALUATION METHOD, AND PLANT RELIABILITY EVALUATION PROGRAM
A plant reliability evaluation system includes: a detector that detects environmental information of a plant during operation; and a health monitor that constantly monitors health of equipment constituting the plant based on the environmental information during operation and importance information of the equipment constituting the plant.
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
To provide an ultrasonic inspection method for performing a wall thickness measurement of a pipe or the like provided with a protective material such as an exterior plate implemented by a metal member, from the outside without removing the exterior plate or the like. The ultrasonic inspection method is implemented by an ultrasonic sensor provided on a surface of an object, a sensor coil connected to the ultrasonic sensor, and a transmission and reception coil provided on an outside of an exterior plate. The exterior plate is provided with an opening having a full width in one direction larger than a diameter of the coil.
An optimal operations analysis device (100) of the present invention is characterized by comprising: a parameter setting/changing unit (104) that sets a plurality of combinations of a base load operating ratio, which is the ratio of the first capacity for generating wholesale electric power to the total facility capacity of an electric power plant, and an adjustment factor, which is the ratio of a second capacity that is actually ready to generate adjustment power to the facility capacity minus the first capacity; a gross profit calculation unit (109) that calculates a corresponding gross profit for each combination on the basis of revenue from selling the wholesale electric power, revenue from selling the adjustment power, and the power source cost; and an output unit (111) that outputs the relationship between the combinations and the gross profits as well as the combination that increases the gross profit enough to meet a designated criterion.
Provided is a reactor that allows a fluid to easily flow. A reactor includes a reactor pressure vessel, a core provided in the reactor pressure vessel and loaded with a fuel assembly, and a steam-water separator provided in the reactor pressure vessel separates water and steam from a fluid containing the steam and the water generated in the core. The steam-water separator includes an annular flow channel through which the fluid flows from an upper side to a lower side and which opens to the lower side of the steam-water separator, and an opening that discharges air bubbles in the fluid flowing through the annular flow channel a side of the steam-water separator.
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
G21C 1/08 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p. ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
10.
ABNORMALITY DETECTION DEVICE FOR CONTROL ROD DRIVE MECHANISM AND ABNORMALITY DETECTION METHOD FOR CONTROL ROD DRIVE MECHANISM
The present invention comprises: a current acquisition unit 14 that acquires at least one phase current of an electric motor 1; a zero-cross section extraction unit 15, 15A that determines a zero-cross section including a zero-cross point from time-series data of the phase current acquired by the current acquisition unit 14 and extracts a current waveform of the zero-cross section; a feature amount calculation unit 16 that calculates a feature amount for detecting an abnormality of a control rod drive mechanism 11 from the current waveform of the zero-cross section; an abnormality diagnosis unit 17 that diagnoses the abnormality by using the feature amount; and a transmission unit 18 that transmits the diagnosis result of the abnormality diagnosis unit 17.
G01M 99/00 - Matière non prévue dans les autres groupes de la présente sous-classe
G01M 13/02 - Mécanismes d’engrènementMécanismes de transmission
G21C 7/08 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c.-à-d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion par déplacement des éléments de commande solides, p. ex. barres de commandes
11.
GAS-WATER SEPARATOR AND BOILING-WATER NUCLEAR REACTOR
Provided are a gas-water separator and a boiling-water nuclear reactor which make it possible to reduce pressure loss while preserving gas-water separation performance of the gas-water separator. In the gas-water separator, cooling water flowing into a reactor core is heated by a nuclear reaction of a fuel assembly to be a gas-liquid two-phase flow, which then flows into a gas-water separator through a standpipe, and the gas-liquid two-phase flow flowing through is separated into moisture-containing steam (gas phase) and water (liquid phase). A swirler having a hub and a plurality of swirl vanes is configured to have a constant hub diameter in a position of 0.5-2.0 D (D: hydraulic equivalent diameter) situated in the upstream direction from the surface of the hub at the downstream side of the flow of the gas-liquid two-phase flow.
G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques
G21C 15/16 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques comprenant des moyens de séparation du liquide et de la vapeur
12.
GAS SEPARATION MEMBRANE, GAS SEPARATION MEMBRANE MODULE, AND GAS PERMEABLE APPARATUS
Provided are a gas separation membrane having a gas separation property and gas permeability and having heat resistance and pressure resistance even under an extremely high temperature and high pressure water vapor atmosphere, which is not a related-art product, a gas separation membrane module, and a gas permeable apparatus. A gas separation membrane according to the present embodiment includes a polyimide resin and a scaly filler. In a gas separation membrane module according to the present embodiment, the gas separation membrane is disposed in a closed container having a mixed gas inlet, a permeable gas outlet, and a non-permeable gas outlet. A gas permeable apparatus according to the present embodiment includes two or more gas separation membrane modules in which the above-described gas separation membrane is disposed in the closed container having the mixed gas inlet, the permeable gas outlet, and the non-permeable gas outlet.
B01D 53/22 - Séparation de gaz ou de vapeursRécupération de vapeurs de solvants volatils dans les gazÉpuration chimique ou biologique des gaz résiduaires, p. ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par diffusion
13.
DRINKING WATER SYSTEM, AND METHOD FOR CONTROLLING DRINKING WATER SYSTEM
A drinking water system (100) comprises: a drinking water machine (10) that discharges water from a discharge port (11); and a radiation measuring instrument (20) that is disposed over the discharge port and that measures the radiation level in the vicinity thereof. The radiation measuring instrument comprises: an opening portion that allows water discharged from the discharge port to pass through; a face detecting unit that detects the face (61) of a user (60) using the drinking water machine; and a radiation level detecting unit that detects the radiation level in the vicinity thereof. At least one of the drinking water machine and the radiation measuring instrument has a shutter for closing the discharge port, and a fan for feeding an airflow toward an area in the vicinity of the face of the user situated facing the discharge port.
This flange fastening device obtained by fastening a pair of flanges, which are to be fastened with a plurality of fasteners and provided with seating surfaces radially inward of the fastening positions of the fasteners, by means of the plurality of fasteners with an annular gasket interposed between the seating surfaces, the flange fastening device comprising a surface pressure sensor which is assembled to the gasket and measures the flange surface pressure. The surface pressure sensor is configured to be capable of measuring the pressure distribution of the flange surface pressure in at least the circumferential direction among the circumferential direction and the radial direction.
Provided are a nuclear power plant, a control device for the nuclear power plant, and a control method for the nuclear power plant that can be utilized for power supply-demand balance adjustment when a large amount of renewable energy is connected to a system. This nuclear power plant is configured to supply steam generated in a nuclear reactor to a high-pressure turbine through a main steam control valve and supply a portion of the steam generated in the nuclear reactor to a moisture separation heater through an adjustment valve to heat exhaust steam from the high-pressure turbine. The nuclear power plant is characterized in that the reactor pressure is controlled by adjusting the amount of steam to the moisture separation heater.
G21D 3/08 - Régulation de différents paramètres dans l'installation
G21D 3/12 - Régulation de différents paramètres dans l'installation par ajustement du réacteur en réponse uniquement aux changements se produisant dans la demande du moteur
16.
Fuel Assembly for Sodium-Cooled Metal Fuel Fast Reactor, Reactor Core, and Manufacturing Method of Fuel Assembly
Provided are a fuel assembly for a sodium-cooled metal fuel fast reactor, a reactor core, and a manufacturing method of the fuel assembly. Compared with conventional techniques, the fuel assembly and the reactor core can subject more MA to nuclear transmutation by allowing to increase the weight of MA to be loaded in the reactor core. One or more of an upper axial blanket fuel or lower axial blanket fuel in an inner core fuel assembly or outer core fuel assembly, or a radial blanket fuel in a radial blanket fuel assembly is a U—Pu-MA-Zr alloy of a low Pu enrichment lower in Pu enrichment than a core fuel, and has a MA enrichment and a Pu enrichment satisfying a relationship of 0 wt %
G21C 3/326 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant des éléments combustibles de différentes compositionsFaisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant, en plus des éléments combustibles, d'autres éléments en forme d'aiguille, de barre ou de tube, p. ex. barres de commande, barres de support de grilles, barres fertiles, barres à poison ou barres factices
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
An ancillary services supply facility (306) includes: a first power conversion device (first semiconductor power conversion device (301)) that is connected to an internal circuit in a nuclear power plant and that converts AC power into DC power; a power storage device (storage battery (106)) that is connected to the first power conversion device, that stores power, and that supplies ancillary services power to a power system; a second power conversion device (second semiconductor power conversion device (302)) that is connected to the power storage device and that converts DC power of the power storage device into AC power; and a control device (110) that controls the first power conversion device and the second power conversion device. The AC side of the second power conversion device is connected to the internal circuit. When a request from a central power supply instructing office exceeds the specification of a generator, the control device (110) determines the power of the power storage device as the ancillary services power required by the power system, and supplies the power to the power system via a main circuit of the nuclear power plant, whereas when the request from the central power supply instructing office does not exceed the specification of the generator, the control device charges the power storage device with power.
The supply amount of reactive power can be expanded while the soundness of a nuclear reactor and a BOP. A control apparatus of a power generation plant connected to a power system including a power system stability degree previous evaluation unit that evaluates a stability degree at the time of the predicted failure of the power system, a nuclear power safety evaluation unit, and a current day power generation control instruction unit that corrects a required power supply amount given from the outside according to the evaluation result of the power system stability degree previous evaluation unit and the evaluation result of the nuclear power safety evaluation unit, in which the generated power of the power generation plant is adjusted by a signal from the current day power generation control instruction unit.
An organic iodine trapping apparatus and method efficiently traps organic iodine in a nuclear reactor container vessel. A liquid vessel contains a non-volatile liquid (e.g., ionic liquid or interfacial active agent solution) capable of decomposing organic iodine. An introduction pipe introduces a fluid containing organic iodine in the nuclear reactor container vessel to the non-volatile liquid. The non-volatile liquid is heated by heat in the nuclear reactor container vessel or reaction heat of the fluid in the nuclear reactor container vessel. Then, the trapping apparatus decomposes and traps the organic iodine. The organic iodine trapping method includes heating a non-volatile liquid capable of decomposing organic iodine by heat in the nuclear reactor container vessel or reaction heat of fluid in the nuclear reactor container vessel; making the fluid containing organic iodine pass through the heated non-volatile liquid; and decomposing and trapping the organic iodine in the non-volatile liquid.
A pipe inspection method includes a first process of disposing an outside coil and a camera outside a thermal insulator, a second process of measuring the thickness of a pipe at a position of an ultrasonic sensor fixed in advance to an inside of the thermal insulator and to the outer surface of the pipe, by using the ultrasonic sensor, an inside coil, the outside coil, and a controller, a third process of photographing the thermal insulator with the camera, a fourth process of removing the thermal insulator from the pipe when judging an abnormality in the thickness of the pipe at the position of the ultrasonic sensor or in the appearance of the thermal insulator, a fifth process of disposing another ultrasonic sensor on the outer surface of the pipe, and a sixth process of measuring the thickness of the pipe at the position of the other ultrasonic sensor.
A coordinated control system (300) for nuclear power plants comprises: a plurality of nuclear power plants (e.g., plant A (PA), plant B (PB), and plant C (PC)), and a control device (plant instruction device (202)) that gives control instructions to the plurality of nuclear power plants. The control device has a storage unit that stores the maximum output change rates of the plurality of nuclear power plants. When performing output adjustment required in a grid, the control device gives instructions to cause the plurality of nuclear plants to share the load on the basis of the ratio of the maximum output change rates of the respective nuclear plants. Conditions, under which the load is to be shared by the plurality of nuclear power plants when performing the output adjustment required in the grid, include the degree of depreciation of each of plants, the degree of deterioration of a control valve, and the degree of deterioration in a water supply and condensation system.
G21D 3/12 - Régulation de différents paramètres dans l'installation par ajustement du réacteur en réponse uniquement aux changements se produisant dans la demande du moteur
H02J 3/46 - Dispositions pour l’alimentation en parallèle d’un seul réseau, par plusieurs générateurs, convertisseurs ou transformateurs contrôlant la répartition de puissance entre les générateurs, convertisseurs ou transformateurs
22.
FLUID CONTACT MEMBER AND METHOD OF MANUFACTURING FLUID CONTACT MEMBER
To provide a fluid contact member whose corrosion resistance is particularly further improved than that in the related art. In order to solve this problem, a fluid contact member 10 includes a fluid contact portion 1 configured to be in contact with a fluid, the fluid contact portion 1 has a cobalt-based alloy phase 2 having a dendrite, and a compound phase 3 formed in an arm space of the dendrite and containing chromium carbide, and among a plurality of secondary arms 5 extending from one primary arm 4 constituting the dendrite, an average interval between adjacent secondary arms 5 is 5 μm or less. At this time, the average interval is preferably 3 μm or less. Further, the compound phase 3 is preferably formed discontinuously in the dendrite arm space.
B33Y 40/20 - Posttraitement, p. ex. durcissement, revêtement ou polissage
B33Y 80/00 - Produits obtenus par fabrication additive
C22C 19/07 - Alliages à base de nickel ou de cobalt, seuls ou ensemble à base de cobalt
C22F 1/10 - Modification de la structure physique des métaux ou alliages non ferreux par traitement thermique ou par travail à chaud ou à froid du nickel ou du cobalt ou de leurs alliages
F16K 3/30 - Robinets-vannes ou tiroirs, c.-à-d. dispositifs obturateurs dont l'élément de fermeture glisse le long d'un siège pour l'ouverture ou la fermeture Détails
An ultrasonic inspection apparatus includes a control device 12 that outputs a pulse signal for making an ultrasonic probe 11A transmit an ultrasonic wave to the ultrasonic probe 11A and that is supplied with a waveform signal obtained by converting the received ultrasonic wave from an ultrasonic probe 11B, and that computes a thickness reduction depth of a pipe 1 between the ultrasonic probe 11A and the ultrasonic probe 11B. The control device 12 computes the thickness reduction depth of the pipe 1 by selectively using a reception time of the ultrasonic wave transmitted from the ultrasonic probe 11A, reflected once by an inner surface 3 of the pipe 1, and received by the ultrasonic probe 11B, and a reception time of the ultrasonic wave transmitted from the ultrasonic probe 11A, reflected twice by the inner surface 3 of the pipe 1, and received by the ultrasonic probe 11B.
A radioactive iodine adsorbent is obtained by supporting silver on a high-silica zeolite in which a hydroxyl nest present inside the high-silica zeolite is converted into a Si—O—Si bond, and the high-silica zeolite is at least any selected from the group consisting of a chabazite (CHA)-type zeolite, a mordenite (MOR)-type zeolite, and a clinoptilolite (CLP)-type zeolite.
B01J 20/02 - Compositions absorbantes ou adsorbantes solides ou compositions facilitant la filtrationAbsorbants ou adsorbants pour la chromatographieProcédés pour leur préparation, régénération ou réactivation contenant une substance inorganique
B01J 20/30 - Procédés de préparation, de régénération ou de réactivation
In a steam separator including a plurality of stages of separating mechanisms, a separating mechanism in a second or subsequent stage includes vertical plates and that divide a second stage annular flow passage or a third stage annular flow passage in a circumferential direction, and eliminate a swirl component of a mixed flow continuously occurring from a second stage inner cylinder or a third stage inner cylinder to the second stage annular flow passage or the third stage annular flow passage.
Disclosed are fuel assemblies that are loaded in the core of a fast reactor including first fuel assemblies and second fuel assemblies being different from the first fuel assemblies. The reactor core has an axially heterogeneous core structure in which an internal blanket region containing depleted uranium fuel is placed around an axially middle section of the core. The first fuel assemblies are loaded in an outer core fuel region extending toward the periphery of the reactor core in a radial direction and the second fuel assemblies are loaded in an inner core fuel region extending around the center of the reactor core in a radial direction. Thickness of an internal blanket in each of the first fuel assemblies in an axial direction of the reactor core is thicker than thickness of an internal blanket in each of the second fuel assemblies in the axial direction of the reactor core.
G21C 3/326 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant des éléments combustibles de différentes compositionsFaisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant, en plus des éléments combustibles, d'autres éléments en forme d'aiguille, de barre ou de tube, p. ex. barres de commande, barres de support de grilles, barres fertiles, barres à poison ou barres factices
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 3/20 - Détails de structure à l'intérieur de l'enveloppe avec revêtement sur le combustible ou sur l'intérieur de l'enveloppeDétails de structure à l'intérieur de l'enveloppe avec une intercouche non active entre l'enveloppe et le matériau actif
27.
NUCLEAR POWER PLANT, AND POWER GENERATION METHOD FOR NUCLEAR POWER PLANT
In a nuclear power plant provided with a nuclear reactor, the nuclear power plant comprising an output control unit 70 that controls the opening degree of an air bleed valve 13 in accordance with a load request, and an energy storage unit that stores renewable energy, the output control unit 70 controls the temperature of water supplied to the nuclear reactor on the basis of the opening degree of the air bleed valve 13 and the amount of energy stored in the energy storage unit. The load following performance of the nuclear power generation plant can thereby be improved, and a nuclear power plant and power generation method for the nuclear power plant that can better stabilize the nuclear reactor output are provided.
G21D 3/08 - Régulation de différents paramètres dans l'installation
G21D 3/12 - Régulation de différents paramètres dans l'installation par ajustement du réacteur en réponse uniquement aux changements se produisant dans la demande du moteur
G21D 5/16 - Agent de travail liquide vaporisé par le réfrigérant du réacteur surchauffé par une source de chaleur séparée
G21C 7/32 - Commande de la réaction nucléaire par variation du courant de réfrigérant à travers le cœur
To provide an electrical penetration capable of being used in nuclear power plants which are designed assuming operation under conditions of the severe accident. An electrical penetration includes: a tubular sleeve member 10; two or more insulating seal members 20A and 20B arranged inside the sleeve member 10 so as to be spaced from each other; wiring members 60, 60 disposed along the longitudinal direction of the sleeve member 10 so as to extend across two insulating seal members of the two or more insulating seal members 20A and 20B; and outer seal members provided inside the sleeve member 10 and at the outermost portions of the two insulating seal members 20A and 20B. The wiring members 60, 60 are each covered with an insulator made of the same material as those of the outer seal members 21A and 21B.
A core of a fast reactor including a sodium plenum installed above a core fuel, which is capable of reliably reducing a void reactivity, and an operation method thereof are provided. The core of a fast reactor including the sodium plenum installed above the core fuel is characterized in that a tip of a primary control rod is inserted into a core fuel region, and a tip of a backup control rod is arranged above an upper end of the core fuel region for operation.
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 3/28 - Éléments combustibles avec un matériau fissile ou surrégénérateur sous forme solide à l'intérieur d'une enveloppe non active
30.
Chemical Decontamination Method and Chemical Decontamination Apparatus
Provided is a chemical decontamination method that shortens the decomposition time of a reduction decontamination agent. An oxidization decontamination, a decomposition of an oxidization decontamination agent, and reduction decontamination using an oxalic acid aqueous solution are performed on a target piping of a BWR plant. After that, the oxalic acid is decomposed (S7). That is, a part of the oxalic acid is decomposed by irradiating the oxalic acid aqueous solution with ultraviolet rays upstream of a decomposition device (S8), and Fe3+ in the aqueous solution is converted to Fe2+. Hydrogen peroxide is supplied to the decomposition device (S9). In the decomposition device, the oxalic acid is decomposed by a catalyst and hydrogen peroxide, Fe2+ and hydrogen peroxide react to produce Fe3+ and OH*, and the oxalic acid is decomposed by OH*. A corrosion potential of the aqueous solution flowing out from the decomposition device is measured (S11). A concentration ratio calculation device obtains Fe3+/Fe2+ (concentration ratio) based on the corrosion potential (S12), and A control device controls the supply amount of hydrogen peroxide to the decomposition device based on Fe3+/Fe2+ (S14 and S16).).
A core of a fast reactor having arranged therein at least one gas expansion module each of which being a hollow tubular structure with one end closed and the other end opened, the core including at least one neutron absorber that absorbs neutron, or, at least one neutron moderator that slows down neutron, arranged so as to adjoin the outer face, in the radial direction of the core, of the gas expansion module.
A filtered containment venting system includes a filtered containment venting tank having: an organic iodine remover for collecting organic iodine; scrubbing water for collecting inorganic iodine; and an alkalizing agent for adding an action of buffering a pH value to the scrubbing water.
B01D 53/14 - Séparation de gaz ou de vapeursRécupération de vapeurs de solvants volatils dans les gazÉpuration chimique ou biologique des gaz résiduaires, p. ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par absorption
There is provided a core of a fast reactor capable of achieving a sodium-cooled metal fuel fast reactor with high adaptability to a molten salt heat storage system, by flattening the output distribution and raising the coolant outlet temperature while suppressing deterioration of the core characteristic. A core of a fast factor is a fuel assembly obtained by densely disposing fuel rods within a wrapper tube, the fuel rod storing, within a cladding tube, hollow fuel in which Pu-enrichment is made to be a predetermined value within a range of 11 to 13 wt %. In the core of a fast factor, a first fuel assembly including a fuel rod with a large hollow diameter of the hollow fuel is loaded on the center side of the core, and a second fuel assembly including a fuel rod with a hollow diameter smaller than the hollow diameter of the hollow fuel of the first fuel assembly is loaded on the circumferential side of the core.
The present invention provides a nickel-based alloy that has excellent aging resistance and in which hardening and embrittlement due to thermal aging are not prone to occur in a high-temperature environment. This nickel-based alloy contains Cr as an essential component and optionally contains one or more of Fe, Nb, Mn, and Mo as optional components, the remainder comprising Ni and unavoidable impurities, the atomic concentration ratio [%Ni]/[%Cr] of Ni and Cr being 1.8-2.2, and the nickel-based alloy satisfying the expression [%Fe] + 0.49[%Nb] + 0.63[%Mn] + 0.05[%Mo] ≥ 14, where [%Ni], [%Cr], [%Fe], [%Nb], [%Mn], and [%Mo] are the atomic concentrations of each element.
In order to ensure the structural integrity of a hood against a load such as pressure exerted from the outside of the hood, the present invention provides a steam dryer for a boiling water-type light-water reactor which ensures the stiffness of the hood without making the hood plate itself thicker, and which avoids lengthening the fabrication time or complicating the fabrication procedure. This steam dryer for a boiling water-type reactor comprises: a hood for guiding, to a steam dryer unit, steam separated by a gas-water separator installed above a reactor core made of a plurality of fuel assemblies disposed inside a nuclear reactor pressure vessel; a support ring; a skirt; and the steam dryer unit having a corrugated plate therein, the steam dryer being characterized in that the hood is made of a first hood plate disposed in the vertical direction, a reinforcing plate mounted on the first hood plate, a second hood plate disposed vertically above the first hood plate and the reinforcing plate, and a side plate disposed between the first hood plate and the steam dryer unit, and the reinforcing plate is formed such that the cross-section thereof is a concavo-convex shape.
G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p. ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
G21C 15/16 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques comprenant des moyens de séparation du liquide et de la vapeur
36.
CONSUMABLE MANAGEMENT DEVICE AND CONSUMABLE MANAGEMENT METHOD
This consumable management device (100) is for managing consumables used in apparatuses that constitute system functions in a nuclear power generating plant, and includes: a consumable importance determination unit (11) that determines the importance of consumables; a consumable performance monitoring unit (12) that monitors the performance and reliability of the consumables on the basis of the importance of the consumables; a consumable soundness evaluation unit (13) that predicts the remaining life of each consumable from state information about the consumable and evaluates the soundness on the basis of the assumed remaining life of the consumable; and a preventive maintenance planning unit (14) that plans preventive maintenance on the basis of the evaluation by the consumable soundness evaluation unit.
The present invention comprises a step for creating a degradation prediction model in which FT-IR spectra and mechanical properties of polymeric materials are correlated, and a step for acquiring the FT-IR spectrum and the mechanical properties of a polymeric material for actual use. The degradation prediction model is obtained by finding a correlation with the mechanical properties of the polymeric material for actual use from a weighted regression analysis using the intensities or areas of a plurality of peaks in an FT-IR spectrum which change due to degradation of a polymeric material and do not affect one another. In this way, a polymeric material remaining life assessment method and remaining life assessment device are provided which are capable of assessing the remaining life of a polymeric material more accurately than was conventionally possible.
A radioactive noble gas removal filter, a filter unit, and a nuclear reactor containment vessel vent system with improved durability are provided. The radioactive noble gas removal filter according to the present invention includes a polyimide film including a structural unit represented by general formula (1).
A radioactive noble gas removal filter, a filter unit, and a nuclear reactor containment vessel vent system with improved durability are provided. The radioactive noble gas removal filter according to the present invention includes a polyimide film including a structural unit represented by general formula (1).
B01D 53/22 - Séparation de gaz ou de vapeursRécupération de vapeurs de solvants volatils dans les gazÉpuration chimique ou biologique des gaz résiduaires, p. ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par diffusion
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
B01D 71/64 - PolyimidesPolyamide-imidesPolyester-imidesPolyamide-acides ou précurseurs similaires de polyimides
Provided is, inter alia, a power supply system that contributes to the stability of a power system. The power supply system (E1) comprises a control means (7) for using, as on-site power to be used in a motor (5a) or other load (5b) during the ordinary operation of a nuclear power plant (100) that generates power by using a main power generator (1), which is a synchronous power source, at least some power generated at a solar power plant or wind power plant that generates power by using an asynchronous power source. The control means (7) uses at least some of the power generated at a solar power plant or wind power plant for the on-site power during the ordinary operation of the nuclear power plant (100), thereby reducing the on-site consumption rate of the nuclear power plant (100).
H02J 3/46 - Dispositions pour l’alimentation en parallèle d’un seul réseau, par plusieurs générateurs, convertisseurs ou transformateurs contrôlant la répartition de puissance entre les générateurs, convertisseurs ou transformateurs
40.
NUCLEAR POWER GENERATION EQUIPMENT AND METHOD FOR OPERATING NUCLEAR POWER GENERATION EQUIPMENT
This nuclear power generation equipment (1) is used as a black start power source when a station blackout occurs. The nuclear power generation equipment (1) comprises: a nuclear power plant (2) that can supply hydrogen to the outside; and a gas turbine plant (3) that can supply power to a load of the nuclear power plant (2) using hydrogen generated by the nuclear power plant (2) as fuel.
The present invention improves the reliability of an apparatus through inspection during the time the apparatus is in service. This plant reliability evaluation system (S) comprises: a detection unit (511) which detects environmental information about a plant (P) in operation; and a soundness monitoring unit (514) which continuously monitoring the soundness of apparatuses that constitute the plant (P) on the basis of the environmental information during operation and importance information about the apparatuses that constitute the plant (P).
This plant instrumentation device (1) used in a power plant for measuring the conditions of equipment or measuring instruments of the plant is provided with: a measured value input unit (21) into which an actual measured value from a measuring instrument installed in the plant is input as a measurement value of a measurement variable; a virtual variable setting unit (22) that sets measurement information of a virtual measuring instrument virtually installed in the plant as a virtual variable; a constraint condition setting unit (23) that sets a conservation law or a balance law pertaining to the measurement variable or the virtual variable as a constraint condition; and a true value estimation unit (10) that calculates estimated true values for the measurement variable and the virtual variable from the measurement variable (11), the virtual variable (12), and the constraint condition (13), using a least-squares method with the uncertainty of the measurement variable as a weight, such that the deviation between the measurement variable and the virtual variable is minimized. Thereby, a high-accuracy plant instrumentation device having a wide range of applications is provided.
A nuclear power plant includes: a nuclear reactor; a steam turbine that is driven by main steam that has been generated by the nuclear reactor; and a gland steam supply device that supplies gland steam to a gland of the steam turbine. The gland steam supply device includes a gland steam generator that heats external water, and generates the gland steam. The external water is independent of the main steam and condensate of the main steam.
G21D 5/06 - Réacteur et moteur non structurellement combinés dont l'agent intermédiaire de travail du moteur circule à travers le cœur du réacteur
F22B 37/00 - Détails ou parties constitutives des chaudières à vapeur
F01K 7/16 - Ensembles fonctionnels de machines à vapeur caractérisés par l'emploi de types particuliers de machines motricesEnsembles fonctionnels ou machines motrices caractérisés par un circuit de vapeur, un cycle de fonctionnement ou des phases particuliersDispositifs de commande spécialement adaptés à ces systèmes, cycles ou phasesUtilisation de la vapeur soutirée ou de la vapeur d'évacuation pour le réchauffage de l'eau d'alimentation les machines motrices étant uniquement du type turbine
44.
MEASURING INSTRUMENT INACCURACY ASSESSMENT SYSTEM AND MEASURING INSTRUMENT INACCURACY ASSESSMENT METHOD
The present invention quantitatively assesses the inaccuracy of measuring instruments installed at a plant. A measuring instrument inaccuracy assessment system (1) comprises a plurality of flowmeters for measuring the water supply flow rate of a plant (3), and has, in a measurement system in which at least one of the flowmeters has a calibration record, a relative bias component calculation unit (13) for calculating a relative bias component from a time average value of measurement values by the flowmeters, a time delay compensation unit (14) for calculating a time delay of the measurement values between the measuring instruments, a water supply fluctuation removal unit (15) for removing a physical time change component of the measurement values, a relative random component calculation unit (16) for calculating a relative random component from a component from which the physical time change of the measurement values is removed, a normality determination unit (17) for determining the normality of the relative random component of the measurement values, and a first output means (181) and a second output means (182) corresponding to the presence and absence of normality of the relative random component of the measurement values.
G21C 17/032 - Mesure ou surveillance du débit de réfrigérant
G01K 1/00 - Détails des thermomètres non spécialement adaptés à des types particuliers de thermomètres
G01F 1/00 - Mesure du débit volumétrique ou du débit massique d'un fluide ou d'un matériau solide fluent, dans laquelle le fluide passe à travers un compteur par un écoulement continu
45.
PLANT MONITORING SYSTEM AND PLANT MONITORING DEVICE
This plant monitoring system monitors plant equipment including at least one of a load circuit, a main circuit, and a breaker which are installed in a plurality of plants. The system comprises a monitoring device having a signal receiving unit and a determination unit. An electric quantity meter is installed in the load circuit and in the main circuit. An electric quantity meter or an operating signal detector is installed in the breaker. The signal receiving unit receives an electric measurement signal including a current measured by the electric quantity meter and/or an operating signal of the breaker detected by the operating signal detector. The determination unit makes a comparison between two or more of the plants among the plurality of plants with regard to the electric measurement signal and/or the operating signal, and determines that the load circuit, the main circuit, or the breaker has an abnormality if the difference between the signal values is at or above a prescribed value. Due to this configuration, it is possible to provide the function of automatic remote monitoring of abnormalities in the electrical circuits, reduce the burden on operators and the like, and also improve the reliability of power source systems through early detection of failures.
The present invention addresses the problem of reducing the working time required to change the fuel assembly or inspect an in-reactor structure to which in-reactor piping is connected, the inside of a nuclear reactor pressure vessel, and other in-reactor structures in normal periodic inspection of a nuclear reactor facility. In order to solve the abovementioned problem, the in-reactor piping structure for a nuclear reactor according to the present invention is characterized in that a pipe connected to a nuclear reactor pressure vessel and a pipe connected to an in-reactor structure are connected in a detachable insertion structure, and specifically, by comprising a first pipe connected to the nuclear reactor pressure vessel, a second pipe connected to the in-reactor structure, and a third pipe for connecting the first pipe and the second pipe, the first pipe and the third pipe being connected, and the second pipe and the third pipe being connected in a detachable insertion structure.
A core performance calculation apparatus includes: a nuclear constant storage device that stores nuclear constants that have been evaluated in advance in analysis of a fuel assembly; and a three-dimensional core nuclear thermal-hydraulic characteristics analysis device that obtains core characteristics including a power of the fuel assembly. The nuclear constant storage device stores, as the nuclear constants, response relationships between a neutron that flows into a fuel assembly cell and fuel assembly nuclear characteristics, and response relationships between a neutron that is produced from a fuel rod and the fuel assembly nuclear characteristics. The three-dimensional core nuclear thermal-hydraulic characteristics analysis device obtains a neutron effective multiplication factor by using the response relationships that have been stored in the nuclear constant storage device, and obtains the power of the fuel assembly by using the neutron effective multiplication factor.
An integrated component management device (10) according to the present invention is a device for integrated management of a component of an apparatus that is used in a nuclear power-related facility. The integrated component management device comprises: a component information storage unit (1) that stores limit test results indicating life characteristics of a component that has a decisive influence on the integrity of the apparatus; a cost information storage unit (2) that stores cost information including component replacement work, component price, and loss due to apparatus shutdown; a life prediction unit (3) that predicts the remaining life of the component on the basis of condition information of the apparatus by referring to the limit test results in the component information storage unit; and a component selection unit (4) that, on the basis of the remaining life of the component, the life of the apparatus, and the cost information, selects a replacement component with which the maintenance cost of the apparatus based on a maintenance plan is minimized. Thus, the present invention provides an integrated component management device and an integrated component management method for an apparatus in a nuclear power-related facility that take into account component remaining life, component cost, and replacement cost.
To provide is a fuel assembly capable of easily adjusting average MA enrichment in an inner blanket region. An inner core fuel assembly 7 loaded in an inner core region 2 of a core of a fast reactor includes a plurality of fuel rods 10 and a plurality of fuel rods 19. Each of the fuel rods 10 includes a lower core fuel region 12, an inner blanket region 11, and an upper core fuel region 13. A U—Pu—Zr metal fuel is disposed in the lower core fuel region 12 and the upper core fuel region 13, and a U—Zr metal fuel is disposed in the inner blanket region 11. Each of the fuel rods 19 includes a lower core fuel region 12, an inner blanket region 20, and an upper core fuel region 13. A U—Pu—Zr metal fuel is disposed in the lower core fuel region 12 and the upper core fuel region 13 of the fuel rod 19, and a MA-Zr metal fuel is disposed in the inner blanket region 20. By adjusting the number of the fuel rods 10 and the number of the fuel rods 19, MA enrichment in the inner blanket region 9 of the fuel assembly 7 can be easily adjusted.
A boiling-water reactor (11) comprises: a square cylindrical channel box (22) disposed so as to surround the side faces of a fuel assembly (20); and a disk-shaped lattice plate (17) that supports upper portions of the side faces of the channel box. The top surface of the entirety or a portion of an outer periphery section of the lattice plate (17) is at a higher height than an inner periphery section (30) thereof provided with a plurality of holes (33) into which the upper portions of the channel box (22) are inserted.
A boiling-water reactor (11) comprises: a square cylindrical channel box (22) disposed so as to surround the side faces of a fuel assembly (20); and a disk-shaped lattice plate (17) that supports upper portions of the side faces of the channel box. The channel box has a structure in which the horizontal width of an upper portion thereof is thicker than the horizontal width of a lower portion thereof by a thickness equivalent to the thickness of a channel spacer, and a plate spring (41) is added to the thicker portion.
G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
An organic iodine remover is a remover for removing organic iodine and is a substance composed of a cation and an anion, and the cation (for example, a phosphonium cation, an ammonium cation, or a sulfonium cation) has a molecular structure in which an electron donating group (for example, a phosphino group, an amino group, a sulfanyl group, a hydroxy group, or an alkoxy group) is bonded to a phosphorus atom, a nitrogen atom or a sulfur atom. An organic iodine removing apparatus includes: a vessel into which the organic iodine remover for removing the organic iodine is charged; and introduction pipes through which a fluid containing organic iodine is introduced into the organic iodine remover.
B01D 53/14 - Séparation de gaz ou de vapeursRécupération de vapeurs de solvants volatils dans les gazÉpuration chimique ou biologique des gaz résiduaires, p. ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par absorption
B01J 20/22 - Compositions absorbantes ou adsorbantes solides ou compositions facilitant la filtrationAbsorbants ou adsorbants pour la chromatographieProcédés pour leur préparation, régénération ou réactivation contenant une substance organique
This ultrasonic flaw detection method involves: a step for controlling transmission and receiving of ultrasonic waves from low-frequency elements 107 and high-frequency elements 108 of an ultrasonic array probe 101; a step for finding the boundary between a wedge 102 and a test body 106 on the basis of the received waveform of ultrasonic waves which, of the two or more types of low-frequency elements 107 and high-frequency elements 108 in the arranged ultrasonic array probe 101, are received by the high-frequency elements 108 on the high vibration frequency side; and a step for imaging the inside of the test body 106 on the basis of the received waveform of ultrasonic waves which, in the arranged ultrasonic array probe 101, are received by the low-frequency elements 108 on the low vibration frequency side. This makes it possible to facilitate both extracting the surface shape and detecting flaws inside of the test body, which was conventionally difficult.
Provided is an ultrasonic flaw detection device that is capable of acquiring the position of a defect in a test target without having to use another sensor for detecting the position of an ultrasonic sensor. An ultrasonic flaw detection device according to the present invention is provided with: an ultrasonic sensor 1 having a plurality of piezoelectric elements 6 and having a variable ultrasonic-wave transmission range; a wedge 2 interposed between the ultrasonic sensor 1 and a duct 100; a control device 3 that controls transmission and reception of ultrasonic waves by the ultrasonic sensor 1; and a computer 4 that acquires information concerning a defect 101 in the duct 100 on the basis of the result of reception by the ultrasonic sensor 1. The wedge 2 has a reflection source 7 that is formed inside the wedge 2 and that reflects ultrasonic waves. The computer 4, on the basis of the result of reception by the ultrasonic sensor 1, computes the positional relationship between the reflection source 7 and the defect 101 in a relative coordinate system defined with respect to the ultrasonic sensor 1, and on the basis of the positional relationship and the position of the reflection source 7 in an absolute coordinate system defined with respect to the duct 100, computes the position of the defect 101 in the absolute coordinate system.
Provided is a highly reliable power system. The power system (100) comprises a synchronous phase modifier (11) that has: an armature winding (11a) electrically connected to a power grid (P1); and a field winding (11b) that functions as a magnetic excitation circuit. The power system is configured such that: power is supplied from the power grid (P1) to the field winding (11b) when the power grid (P1) is operating normally; and the source of power supply to the field winding (11b) is switched from the power grid (P1) to a power grid (P2) when the power grid (P1) has an error.
A radioactive iodine adsorbent that is obtained by having a high-silica zeolite, within which a hydroxyl nest is converted into an Si-O-Si bond, support silver, wherein the high-silica zeolite is composed of at least one zeolite that is selected from the group consisting of a chabazite (CHA) type zeolite, a mordenite (MOR) type zeolite and a clinoptilolite (CLP) type zeolite.
A reactor containment vessel vent system continuously releases steam generated in a reactor containment vessel to the atmosphere even when a power supply is lost. In the reactor containment vessel vent system, the noble gas filter that allows steam to pass through but does not allow radioactive noble gases to pass through among vent gas discharged from the reactor containment vessel is provided at a most downstream portion of the vent line. An immediate upstream portion of the noble gas filter and the reactor containment vessel are connected to each other by the return pipe via the intermediate vessel. When the radioactive noble gases having pressure equal to or higher than predetermined pressure stay in the immediate upstream portion of the noble gas filter, the staying radioactive noble gases flows into the intermediate vessel by the relief valve. Thus, steam permeability is maintained and the system continuously releases the steam.
A reactor building includes a spent fuel pool, spent fuel racks, and traveling rails. The spent fuel racks are located in the spent fuel pool and are configured to store nuclear spent fuel. A protection slab is located above the spent fuel racks. The traveling rails are fixed to a lower surface of the protection slab. The rails are parallel to each other. The spent fuel racks are located between the rails. A fuel transfer machine is suspended from the rails.
G21C 19/07 - Râteliers de stockagePiscines de stockage
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21C 19/40 - Dispositions pour prévenir l'apparition de conditions critiques, p. ex. pendant le stockage
The invention provides a piping wall thinning prediction system, a piping soundness evaluation system, and a method which can evaluate a wall thinning amount, a wall thinning rate, and a remaining life at a high speed based on limited actual measurement results, and identify a location requiring monitoring in a piping in a plant. The wall thinning prediction system includes: a first AI evaluation unit configured to evaluate a fluid characteristic value of a piping based on an input value including piping shape information and information of a fluid in the piping; and a second AI evaluation unit configured to evaluate an index related to wall thinning of the piping based on an input value including the fluid characteristic value. The wall thinning prediction system is configured to predict the index related to the wall thinning of the piping.
This safety system for a nuclear power plant comprises: an IC cooling water pool installed outside a reactor container; an intermediate tank positioned inside the reactor container and lower than the IC cooling water pool, the intermediate tank receiving and being capable of storing cooling water discharged from the IC cooling water pool; a drain line that leads cooling water from the IC cooling water pool to the intermediate tank; a drain valve provided on the drain line; a pressure reduction line, one side of which is connected to a reactor pressure vessel, and the other side of which opens at a position lower than the water level assumed when cooling water from the IC cooling water pool is stored in the intermediate tank; and a pressure reduction valve provided on the pressure reduction line. The drain valve and the pressure reduction valve open in accordance with the degree of pressure in the reactor pressure vessel.
Provided is a chemical decontamination method whereby the time of decomposition of a reduction decontamination agent can be reduced. Oxidization decontamination of a pipe of interest in a BWR plant, the decomposition of an oxidization decontamination agent, and reduction decontamination using an aqueous oxalic acid solution are performed. Subsequently, oxalic acid is decomposed (S7). That is, a portion of oxalic acid is decomposed by the irradiation of the aqueous oxalic acid solution with ultraviolet ray in an upstream of a decomposition device (S8) to convert Fe3+in the aqueous solution to Fe2+. Hydrogen peroxide is supplied into the decomposition device (S9). In the decomposition device, oxalic acid is decomposed by the action of a catalyst and hydrogen peroxide, Fe2+is reacted with hydrogen peroxide to produce Fe3+and OH*, and oxalic acid is decomposed by OH*. The corrosion potential of the aqueous solution flowing out from the decomposition device is measured (S11). A concentration ratio reading device determines a Fe3+/Fe2+ratio (concentration ratio) on the basis of the corrosion potential (S12), and a control device controls the amount of hydrogen peroxide to be supplied into the decomposition device on the basis of the Fe3+/Fe2+ value (S14 and S16).
A construction assistance system (9) comprises a simulator (100) which creates work plan data for defining operation data of a work robot (22) for a work environment representing states of an object (21) to be worked and the work robot (22) in the work environment through a first simulation process based on a local planning environment that is the work environment in a planning step, and updates the work plan data through a second simulation process based on the local execution environment, when the difference is generated from the local planning environment as a result of measuring the local planning environment that is the work environment in an execution step.
G06Q 10/06 - Ressources, gestion de tâches, des ressources humaines ou de projetsPlanification d’entreprise ou d’organisationModélisation d’entreprise ou d’organisation
63.
CONSTRUCTION SUPPORT DEVICE, CONSTRUCTION SUPPORT METHOD, AND CONSTRUCTION SUPPORT PROGRAM
A construction support system (9) includes a simulator (100) which, regarding a work environment showing the state of a work object (21) and a work robot (22) at a work site, creates work plan data to specify operation data on the work robot (22) via a first simulation process based on an on-site planning environment that is a working environment at a planning stage, and when a difference occurs from the on-site planning environment as a result of measuring an on-site execution environment that is a work environment at an execution stage, updates the work plan data via a second simulation process based on the on-site execution environment.
G06Q 10/06 - Ressources, gestion de tâches, des ressources humaines ou de projetsPlanification d’entreprise ou d’organisationModélisation d’entreprise ou d’organisation
64.
STEAM WATER SEPARATION FACILITY AND NUCLEAR REACTOR
Among steam water separators of this steam water separation facility, the vertical height position of a steam water separation part (gap 71) at the first stage from the bottom of a steam water separator 10 disposed to a center portion of a nuclear reactor 100 is set lower than the vertical height position of a steam water separation part (gap 71A) at the first stage from the bottom of a steam water separator 10A disposed to the outermost circumferential portion of the nuclear reactor 100. Accordingly, provided are: a steam water separation facility that can realize low carry-over and low carry-under as the entirety of steam water separators; and a nuclear reactor provide with same.
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p. ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
G21C 15/16 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques comprenant des moyens de séparation du liquide et de la vapeur
65.
NUCLEAR REACTOR CORE DESIGN ASSISTANCE SYSTEM AND NUCLEAR REACTOR CORE DESIGN ASSISTANCE METHOD
A nuclear reactor core design assistance system 100 comprises a regular inspection plan creation unit 120 that uses reactor core design information and regular inspection information to determine, for each operating cycle, the location of a reactor-internal device under regular inspection, said reactor core design information including information that relates to the positioning of reactor-internal devices, and said regular inspection information including information that relates to the degradation condition of the reactor-internal device under regular inspection or the frequency at which regular inspections should be performed. Thus, provided are a nuclear reactor core design assistance system and a nuclear reactor core design assistance method with which it is possible optimize a regular inspection plan for a device, such as for device inspections or device replacement tasks.
An excess pressure protection device (100) comprises: an emergency condenser (5) that is positioned outside of a nuclear reactor housing vessel (4) housing a nuclear reactor pressure vessel (1) therein, and causes steam produced in a reactor core to cool, condense, and revert to water; and an emergency condenser pool (9) that immerses the emergency condenser in water. The emergency condenser has a plurality of heat transmission pipes (15), an upper section header (14) that brings the upper end sides of the heat transmission pipes together, a lower section header (16) that brings the lower end sides of the heat transmission pipes together, a lower section header vent pipe (17a), one end section thereof being positioned near a bottom section within the emergency condenser pool and the other end section thereof being connected to the lower section header, and a lower section header vent (18a) that is positioned on the path of the lower section header vent pipe and is released when there is a decrease in water level that surpasses expectation within the nuclear reactor pressure vessel, or when there is an increase in pressure that surpasses expectation within the nuclear reactor housing vessel.
A reactor control apparatus comprising: a control rod drive control device for controlling extraction operation of a control rod inserted in a reactor core, on the basis of the output of a plurality of neutron detectors provided in the reactor core; a reactor simulator for predicting and computing a time change in the output of the neutron detectors on the basis of information of the control rod extraction operation performed by the control rod drive control device and a plurality of parameters that affect the output of the neutron detectors; and a simulator adjustment device for correcting at least one of the plurality of parameters on the basis of the output of the plurality of neutron detectors.
G21C 7/08 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c.-à-d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion par déplacement des éléments de commande solides, p. ex. barres de commandes
As an organic iodine remover that removes organic iodine in a containment vessel of a nuclear reactor, an organic agent (for example, an ionic liquid, an interfacial active agent, a quaternary salt, or a phase transfer catalyst) having a function of dissolving and decomposing the organic iodine and retaining iodine is used. The organic iodine remover is a substance composed of a cation and an anion. The organic iodine remover is, in particular, an organic iodine remover in which, in a structure of the cation of the organic agent, carbon or oxygen is bonded to, via a single bond, to a phosphorus element, a sulfur element or a nitrogen element, the number of carbon chains is 2 or more, and an anionic structure is configured with a substance with high nucleophilicity. By using such an organic agent, the organic iodine is removed with an efficiency of 99% or more.
B01D 53/02 - Séparation de gaz ou de vapeursRécupération de vapeurs de solvants volatils dans les gazÉpuration chimique ou biologique des gaz résiduaires, p. ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par adsorption, p. ex. chromatographie préparatoire en phase gazeuse
To provide an iodine trapping apparatus capable of trapping organic iodine in a wide temperature range with high efficiency. The iodine trapping apparatus includes a first trapping agent 2 capable of trapping organic iodine in a gas in a nuclear power structure main body. The first trapping agent 2 contains a generating and trapping component which generates an iodide ion (I−) from organic iodine (RI) and traps the generated iodide ion, and a generating component which is different from the generating and trapping component, generates an iodide ion from the organic iodine at least at 100° C. to 130° C., and traps the generated iodide ion in the generating and trapping component.
B01D 53/78 - Procédés en phase liquide avec un contact gaz-liquide
G21C 19/303 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteurDispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p. ex. par extraction des produits de fission spécialement adaptés pour des gaz
70.
PLANT DEMOLITION MANAGEMENT DEVICE, PLANT DEMOLITION MANAGEMENT METHOD, AND PLANT DEMOLITION MANAGEMENT PROGRAM
A plant demolition management device (1) according to the present invention is characterized by being provided with: a disposal plan creation unit (21) that plans, on the basis of design information of waste discharged from a plant and the radiation dose of the waste, processes to be performed until the waste is reused or finally disposed of after the waste is discharged from the plant; and a history providing unit (23) that transmits history information of the waste to a terminal device of a person concerned in response to a request from the person concerned during the processes.
A chemical decontamination method capable of improving the decontamination efficiency of chemical decontamination of a steam dryer in the RPV is provided. In particular, the decontamination method includes feeding a chemical decontamination aqueous solution into a reactor pressure vessel in which a steam dryer is arranged, and after chemical decontamination of the steam dryer, the water level of the chemical decontamination aqueous solution existing in the reactor pressure vessel is lowered to a first water level below the lower end of the steam dryer.
Turbine equipment (100) comprises a low-pressure turbine (30) and a plurality of shields that cover the low-pressure turbine (30), and each of the plurality of shields has a layered structure with respect to the other shields. Preferably, the shields are concrete shields (1A), (1B) that cover a casing of the low-pressure turbine (30), and the shields also each have a key structure protrusion (8A), a key structure recess (8B), or a bolt hole (9A). Thus, there are provided turbine equipment and a method for inspecting the turbine equipment with which it is possible to make a building smaller than before.
To provide a fluid contact member whose corrosion resistance is particularly further improved than that in the related art. In order to solve this problem, a fluid contact member 10 includes a fluid contact portion 1 configured to be in contact with a fluid, the fluid contact portion 1 has a cobalt-based alloy phase 2 having a dendrite, and a compound phase 3 formed in an arm space of the dendrite and containing chromium carbide, and among a plurality of secondary arms 5 extending from one primary arm 4 constituting the dendrite, an average interval between adjacent secondary arms 5 is 5 μm or less. At this time, the average interval is preferably 3 μm or less. Further, the compound phase 3 is preferably formed discontinuously in the dendrite arm space.
C22C 19/07 - Alliages à base de nickel ou de cobalt, seuls ou ensemble à base de cobalt
B22F 10/64 - Traitement de pièces ou d'articles après leur formation par des moyens thermiques
B33Y 40/20 - Posttraitement, p. ex. durcissement, revêtement ou polissage
B33Y 80/00 - Produits obtenus par fabrication additive
C22F 1/10 - Modification de la structure physique des métaux ou alliages non ferreux par traitement thermique ou par travail à chaud ou à froid du nickel ou du cobalt ou de leurs alliages
F16K 25/04 - Dispositions pour empêcher l'usure, non prévues ailleurs
B22F 10/28 - Fusion sur lit de poudre, p. ex. fusion sélective par laser [FSL] ou fusion par faisceau d’électrons [EBM]
F16K 3/30 - Robinets-vannes ou tiroirs, c.-à-d. dispositifs obturateurs dont l'élément de fermeture glisse le long d'un siège pour l'ouverture ou la fermeture Détails
A drive mechanism (K1) for an air-operated valve (B) according to the present invention comprises: an open/closed state maintenance means (d1, d2, 1, 2, 3, 4) which, upon the occurrence of an abnormality, maintains the open/closed state of the air-operated valve (B) that is operated by operating air (10); and a first closed state switching means (d2) which switches the air-operated valve (B) from an open/closed state maintenance mode to a closed state mode.
Provided are a filter that is for removing radioactive noble gas and that has improved durability; a filter unit; and a reactor containment vent system. This filter for removing radioactive noble gas is provided with a polyimide membrane having structural units represented by general formula (1).
A boiling water-type natural circulation furnace (R) according to the present invention comprises: an atomic furnace pressure vessel (5) in which a reactor core (7) is stored; an intra-furnace structure (8) provided inside the atomic furnace pressure vessel (5) and provided around or above the reactor core (7); and a bracket (15) fixed inside the atomic furnace pressure vessel (5), wherein the intra-furnace structure (8) is configured so as to be attachable/detachable to/from the bracket (15).
G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p. ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
In a lagging material, which covers a periphery of a structure that becomes hot, in the present invention, a member that converges a magnetic field line in the lagging material is provided. The member includes a magnetic body and has magnetic permeability equal to or higher than 1×10−4 H/m.
Intended is to improve the corrosion resistance of an overlay used in a nuclear power plant, and to reduce dissolution of cobalt from an overlay. The corrosion and wear resistant overlay 7 is formed along a surface of a base 2 by laser lamination modeling, and is configured from a plurality of metal layers 1a, 1b, 1c, and 1d of a Co-base alloy. The thickness of carbide eutectics that precipitate in the metal layers 1a, 1b, 1c, and 1d is the largest in the metal layer 1a closest to the base 2, and is gradually smaller in the metal layers 1b, 1c, and 1d farther away from the base 2. The intensity of the laser beam applied to form layers by laser lamination modeling is adjusted so that the carbide eutectics that precipitate in at least the outermost metal layer 1d have a controlled size of 10 μm or less.
B23K 20/12 - Soudage non électrique par percussion ou par une autre forme de pression, avec ou sans chauffage, p. ex. revêtement ou placage la chaleur étant produite par frictionSoudage par friction
C22F 1/10 - Modification de la structure physique des métaux ou alliages non ferreux par traitement thermique ou par travail à chaud ou à froid du nickel ou du cobalt ou de leurs alliages
F16K 15/02 - Soupapes, clapets ou valves de retenue à corps de soupapes rigides guidés
F16K 25/00 - Détails constitutifs relatifs au contact entre corps de soupapes ou de clapets et leurs sièges
F16K 3/12 - Robinets-vannes ou tiroirs, c.-à-d. dispositifs obturateurs dont l'élément de fermeture glisse le long d'un siège pour l'ouverture ou la fermeture à faces d'obturation planesGarnitures d'étanchéité à cet effet à faces d'obturation en forme de coin
F16K 3/02 - Robinets-vannes ou tiroirs, c.-à-d. dispositifs obturateurs dont l'élément de fermeture glisse le long d'un siège pour l'ouverture ou la fermeture à faces d'obturation planesGarnitures d'étanchéité à cet effet
C22C 1/04 - Fabrication des alliages non ferreux par métallurgie des poudres
C23C 24/10 - Revêtement à partir de poudres inorganiques en utilisant la chaleur ou une pression et la chaleur avec formation d'une phase liquide intermédiaire dans la couche
B22F 3/115 - Fabrication de pièces ou d'objets à partir de poudres métalliques, caractérisée par le mode de compactage ou de frittageAppareils spécialement adaptés à cet effet par pulvérisation de métal fondu, c.-à-d. frittage par pulvérisation, moulage par pulvérisation
C22C 19/07 - Alliages à base de nickel ou de cobalt, seuls ou ensemble à base de cobalt
F01L 3/02 - Emploi de matériaux spécifiques pour corps de soupapes ou leurs siègesCorps de soupapes ou sièges de soupapes composés de plusieurs matériaux différents
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
C23C 28/02 - Revêtements uniquement de matériaux métalliques
F01L 3/08 - Guides de soupapesÉtanchéité des tiges de soupapes, p. ex. étanchéité par lubrification
There is provided an organic iodine trapping apparatus that can efficiently trap an organic iodine without using complicated or large equipment. An organic iodine trapping apparatus 30 is an apparatus that traps an organic iodine, including: a trapping vessel 1 through which gas containing an organic iodine is passed; an organic iodine remover 2 (Example: trihexyl (tetradecyl) phosphonium chloride, or the like) that is disposed in or injected into the trapping vessel 1 and decomposes the organic iodine; and a trapping material 3 that is disposed in or injected into the trapping vessel 1 and traps iodine ions generated by decomposition of the organic iodine, in which the trapping material 3 is a metal (Example: silver or the like) or a metal compound (Example: silver chloride, silver oxide, or the like).
B01D 53/14 - Séparation de gaz ou de vapeursRécupération de vapeurs de solvants volatils dans les gazÉpuration chimique ou biologique des gaz résiduaires, p. ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par absorption
B01D 53/18 - Unités d'absorptionDistributeurs de liquides
Provided are a chemical decontamination method and a chemical decontamination apparatus capable of preventing deterioration of a metal ion exchange resin and performing decontamination at a low cost in a short time.
The chemical decontamination method of the invention includes: a reduction decontamination step of supplying a reduction decontamination solution to a decontamination target portion and performing reduction decontamination on a surface of a member constituting the decontamination target portion; a hydrogen peroxide decomposition step of decomposing hydrogen peroxide contained in the reduction decontamination solution after the reduction decontamination step; and a metal ion removing step of removing a metal ion contained in the reduction decontamination solution after the hydrogen peroxide decomposition step.
G21F 9/00 - Traitement des matériaux contaminés par la radioactivitéDispositions à cet effet pour la décontamination
B01D 15/12 - Adsorption sélective, p. ex. chromatographie caractérisée par des caractéristiques de structure ou de fonctionnement relatives à la préparation de l'alimentation
B01D 15/36 - Adsorption sélective, p. ex. chromatographie caractérisée par le mécanisme de séparation impliquant une interaction ionique, p. ex. échange d'ions, paire d'ions, suppression d'ions ou exclusion d'ions
A fast reactor core includes a sodium plenum installed above the fuel. The sodium plenum is capable of reducing a void reactivity. During operation, a tip of a primary control rod is inserted in a core fuel region, and a tip of a backup control rod is arranged near an upper end of the sodium plenum.
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 3/28 - Éléments combustibles avec un matériau fissile ou surrégénérateur sous forme solide à l'intérieur d'une enveloppe non active
G21C 7/28 - Commande de la réaction nucléaire par déplacement du réflecteur ou de parties de celui-ci
G21C 7/32 - Commande de la réaction nucléaire par variation du courant de réfrigérant à travers le cœur
G21C 7/08 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c.-à-d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion par déplacement des éléments de commande solides, p. ex. barres de commandes
Desired is a work integration management system in which an initial plan is formulated by using an OR method, and corrections, to a work plan that uses variable elements, are emphasized even if work employing document 1 is carried out. The work integration management system is characterized by comprising at least one function from among: a work plan correction function which corrects an initial work plan for the purpose of obtaining a more favorable optimum solution after having subjected the plan and results of the initial work plan to comparative evaluation; a three-axis evaluation function which, in addition to two-axis evaluation using two constraint functions, derives and presents an optimum solution by taking into account one more constraint function; and a mid-to-long-term resource arrangement planning function which formulates an optimum short-term resource arrangement during work as well as an optimum resource arrangement plan from the perspective of mid-to-long-term.
G06Q 10/06 - Ressources, gestion de tâches, des ressources humaines ou de projetsPlanification d’entreprise ou d’organisationModélisation d’entreprise ou d’organisation
83.
VALVE DRIVE SYSTEM AND EMERGENCY CONDENSATE SYSTEM
The purpose of this invention is to enable a valve to be appropriately driven in a valve drive system. To achieve this purpose, a valve drive system (S1) is provided with a gas-actuated valve (71) that forms a flow channel for a fluid (F1) when a gas (G1) having at least a designated pressure is supplied to a first pipe (106), first gas supply sources (42, 44, 50, 60) that cause the gas (G1) having at least a designated pressure to be generated, a rupture disc (30) that forms a channel that supplies gas (G1) flowing in from the first gas supply sources (42, 44, 50, 60) to a second pipe (104) when broken, a switching valve (21) that allows continuity between the first pipe (106) and the second pipe (104) when the gas (G1) is supplied to the second pipe (104) from the first gas supply sources (42, 44, 50, 60), and a breakage operation part (23) that breaks the rupture disc (30) when the pressure of the fluid (F1) exceeds a designated pressure.
F15B 11/06 - Systèmes de servomoteurs dépourvus d'asservissement comportant des moyens particuliers pour l'utilisation d'un agent compressible, p. ex. de l'air, de la vapeur d'eau
F16K 17/40 - Soupapes ou clapets de sûretéSoupapes ou clapets d'équilibrage avec élément de rupture, p. ex. un diaphragme de rupture, un joint fusible
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
84.
RADIOACTIVE WASTE LIQUID TREATMENT SYSTEM AND METHOD FOR TREATING RADIOACTIVE WASTE LIQUID
Provided is a radioactive waste liquid treatment system whereby an α-nuclide remover for removing α nuclides contained in radioactive waste liquid can be made compact. Crud included in radioactive organic waste containing a positive ion exchange resin is dissolved using an organic acid aqueous solution (S1). The organic acid aqueous solution is exposed to ozone to decompose the organic acid (S4). α nuclides adsorbed on the radioactive organic waste in which crud has been dissolved are eluted by an organic acid salt aqueous solution (S2). The organic acid salt aqueous solution is exposed to ozone to decompose the organic acid salt (S4). A pH adjuster (acid, alkali, reducing agent, oxidizing agent for water conditioning) is poured into the radioactive waste liquid containing the α nuclides, generated in S4 (S5). A colloid of the α nuclides is formed in the radioactive waste liquid, which has been pH-adjusted to a range of no less than 4 to less than 8 by the pH adjuster. The colloid is removed using a filter (S6). Ions of the α nuclides contained in the radioactive waste liquid discharged from the filter are removed by an α-nuclide remover (S7).
More accurate prediction of reactor water quality of a nuclear reactor is implemented. A device for prediction of reactor water quality of a nuclear reactor in a nuclear power plant is disclosed. The device stores a reactor water quality prediction model which is learned using learning data, and with which future reactor water quality is predicted. An explanatory variable of the reactor water quality prediction model includes a value in a predetermined period unit that is generated from data acquired in an operating nuclear power plant. The device generates the value in a predetermined period unit from data acquired in a target operating nuclear power plant, and acquires a predicted value of the reactor water quality in the target nuclear power plant based on the reactor water quality prediction model and the value in a predetermined period unit.
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
The present invention provides an organic iodine removal agent and an organic iodine removal device using the same, which are capable of removing effectively an organic iodine in a fluid. The organic iodine removal agent (120) is a substance constituted from a cation and an anion and serves to remove organic iodine, wherein the cation (for example, a phosphonium cation, an ammonium cation, a sulfonium cation, or the like) has a molecular structure comprising an electron-donor group (for example, a phosphino group, an amino group, a sulfanyl group, a hydroxy group, an alkoxy group, or the like) bonded to a phosphorus atom, a nitrogen atom, or a sulfur atom. The organic iodine removal device (100) comprises a container (1) into which the organic iodine removal agent (120) for removing the organic iodine is placed, and introduction pipes (3, 4, 7) for introducing into the organic iodine removal agent (120) a fluid containing the organic iodine.
B01D 53/14 - Séparation de gaz ou de vapeursRécupération de vapeurs de solvants volatils dans les gazÉpuration chimique ou biologique des gaz résiduaires, p. ex. gaz d'échappement des moteurs à combustion, fumées, vapeurs, gaz de combustion ou aérosols par absorption
B01J 20/22 - Compositions absorbantes ou adsorbantes solides ou compositions facilitant la filtrationAbsorbants ou adsorbants pour la chromatographieProcédés pour leur préparation, régénération ou réactivation contenant une substance organique
A nuclear reactor isolation nozzle (3) that is welded to a nuclear reactor pressure vessel (1) incorporates a valve structure (9), and by closing a valve body (9a) of the valve structure (9), isolates fluid inside the nuclear reactor pressure vessel (1) from the outside of the nuclear reactor pressure vessel (1). A nozzle main body (8) of the nuclear reactor isolation nozzle (3) has a seamless integrated structure. The nozzle main body (8) is manufactured by forging.
An ultrasonic inspection method in which a pulse signal is output to an ultrasonic sensor to generate and transmit ultrasonic waves, the ultrasonic waves reflected or scattered by an object are received and converted into a waveform signal by the ultrasonic sensor, and the waveform signal is digitized to acquire waveform data, includes: executing modulation processing for modulating a plurality of waveform data acquired in multiple inspections and under the same inspection conditions by a phase modulation method to generate composite waveform data; and executing demodulation processing for demodulating the composite waveform data to generate compressed waveform data.
A reactor water radioactivity concentration of a nuclear power plant can be predicted with high accuracy. First, a plant state quantity prediction value is calculated by using a physical model that describes plant state quantities of the power plant including a flow rate of feedwater and a metal corrosion product concentration in feedwater of the reactor water is calculated. Next, data for supervised learning is created, and the data for supervised learning includes the previously calculated plant state quantity prediction value and a plant state quantity such as the flow rate of feedwater, the metal corrosion product concentration in feedwater, a metal corrosion product concentration in reactor water, and a radioactive metal corrosion concentration of the reactor water in the reactor as input data and includes a radioactive metal corrosion concentration in the reactor water which is an actual measured value as output data, and a predictive model is trained.
G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes
G21D 3/10 - Régulation de différents paramètres dans l'installation par une combinaison d'une variable dérivée du flux de neutrons avec d'autres variables de commande, p. ex. dérivées de la température, du flux du réfrigérant, de la pression
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 1/08 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p. ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
G21C 5/12 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par la composition, p. ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
A nuclear power plant according to the present invention comprises: a nuclear reactor pressure vessel; a pressure vessel supporting structure that supports the nuclear reactor pressure vessel; a nuclear reactor containment vessel that accommodates the nuclear reactor pressure vessel supported by the pressure vessel supporting structure; and piping that is connected to a side peripheral wall of the nuclear reactor pressure vessel at a location further upward than the center of gravity of the nuclear reactor pressure vessel, and that is fixed to the nuclear reactor containment vessel. The pressure vessel supporting structure supports the nuclear reactor pressure vessel at a location further upward than the center of gravity of the nuclear reactor pressure vessel.
Regarding a technology for monitoring the state of a rotary machine by using an AE, provided is a technology enabling detection of a change in state of a mechanical seal at high sensitivity and improvement of operation/maintenance of the rotary machine. This state monitoring system is for monitoring the state of a rotary machine 1 having a mechanical seal 4, the state monitoring system being provided with: an AE sensor 5 that is disposed in a container 2 of the rotary machine 1; a signal acquisition circuit for acquiring an AE signal from the AE sensor 5; and a state monitoring device 10 for, on the basis of information acquired at the signal acquisition circuit, determining the state regarding the mechanical seal 4, including whether or not the mechanical seal 4 is normal, and for performing output control including movement control of the rotary machine 1 or alert output in accordance with the state. The state monitoring device 10 compares time-frequency response of a frequency spectrum of the AE signal being monitored with a signal during a normal time in the past, and determines the state on the basis of judgement on increase of a signal component in a range of not less than 0.7 MHz as a predetermined frequency range that has been set.
G01M 99/00 - Matière non prévue dans les autres groupes de la présente sous-classe
F16J 15/3296 - Agencements pour la surveillance de l’état physique ou du fonctionnement des joints élastiquesAgencements pour le contrôle des joints élastiques, p. ex. de leur géométrie ou rigidité
F16J 15/34 - Joints d'étanchéité entre deux surfaces mobiles l'une par rapport à l'autre par bague glissante pressée contre la face plus ou moins radiale d'une des deux parties
The invention provides a method of manufacturing a transition piece that has a high degree of freedom in adjustment of a length, a shape, or the like, can carry out a dissimilar metal welding easily, and is easy to perform, and a transition piece. The transition piece includes one end having the same composition as one material to be welded, another end having the same composition as another material to be welded, and an intermediate layer formed between the one end and the other end. The composition of the one end and the composition of the other end become the same as approaching a center. In the method of manufacturing the transition piece according to the invention, at least the intermediate layer among the one end, the other end, and the intermediate layer is formed by a additive manufacturing method.
B22F 7/06 - Fabrication de couches composites, de pièces ou d'objets à base de poudres métalliques, par frittage avec ou sans compactage de pièces ou objets composés de parties différentes, p. ex. pour former des outils à embouts rapportés
B23K 26/00 - Travail par rayon laser, p. ex. soudage, découpage ou perçage
B22F 7/08 - Fabrication de couches composites, de pièces ou d'objets à base de poudres métalliques, par frittage avec ou sans compactage de pièces ou objets composés de parties différentes, p. ex. pour former des outils à embouts rapportés avec une ou plusieurs parties non faites à partir de poudre
B33Y 80/00 - Produits obtenus par fabrication additive
B22F 5/10 - Fabrication de pièces ou d'objets à partir de poudres métalliques caractérisée par la forme particulière du produit à réaliser d'articles avec des cavités ou des trous, non prévue dans les sous-groupes précédents
The fuel element of the present invention includes a cladding tube and a metal fuel contained in the cladding tube, in which a gas plenum region is formed above the metal fuel and inside the cladding tube and has a small-diameter portion in the gas plenum region. Further, the fuel assembly of the present invention includes the fuel element of the present invention and a wrapper tube surrounding the fuel element, in which a coolant material passage is formed between the fuel element and the fuel element. Further, the core of the present invention includes an inner core fuel region loaded with the fuel assembly according to the present invention, and an outer core fuel region loaded with the fuel assembly of the present invention.
G21C 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p. ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
G21C 5/18 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par l'installation de plus d'une zone active
b) via the intermediate vessel (100). Further, when the radioactive noble gases having pressure equal to or higher than predetermined pressure stays in the immediate upstream portion of the noble gas filter (23), the staying radioactive noble gases flows into the intermediate vessel (100) by the relief valve (25). Thus, the noble gas filter (23) does not lose steam permeability, and the reactor containment vessel vent system (15) can continuously release the steam to the atmosphere.
Provided is an organic iodine remover for removing organic iodine inside a reactor container, the remover using an organic agent (for example, an ionic liquid, a surfactant, a quaternary salt, a phase transfer catalyst, or the like) which exhibits the function of dissolving, breaking down and retaining the organic iodine. The organic iodine remover is a substance comprising a cation and an anion. The organic iodine remover is characterized in that the cation structure in the organic agent thereof has carbon or oxygen bonded via a single bond to elemental phosphorus, elemental sulfur or elemental nitrogen, and has two or more carbon chains, and the anion structure thereof is composed of a substance which has high nucleophilicity. Using an organic agent having such a configuration makes it possible to remove organic iodine with an efficiency of at least 99%.
The objective of the present invention is to provide a moving body mounting device with which it is possible for a moving body such as an inspection device to be operated efficiently. To this end, a moving body mounting device (S) is provided with: a movable track (5) which is to be linked to a fixed track (1) extending in a lateral direction and which guides a moving body (4); and a raising and lowering device (100) which is configured to be capable of being attached to and removed from the fixed track (1), and which raises and lowers the movable track (5) in a vertical direction in a state in which the movable track (5) is joined to the moving body (4). In addition, the raising and lowering device (100) is preferably provided with: a first guide member (120) which is configured to be capable of being attached to and removed from the fixed track (1), and which restricts movement of the movable track (5) in the lateral direction while permitting movement of the movable track (5) in the vertical direction; and a suspending mechanism (150) which is mounted on the first guide member, for suspending the movable track.
The problem is to provide a fluid-contacting member particularly having further improved corrosion resistance than ever before. For solving the problem, a fluid-contacting member 10 is provided with a fluid-contacting part 1 that comes into contact with a fluid, wherein the fluid-contacting part 1 has a cobalt-based alloy phase 2 having a dendrite and a compound phase 3 formed in dendrite spaces and containing chromium carbide, and the average of the distances between adjacent pairs of secondary arms 5, among a plurality of secondary arms 5 extending from one primary arm 4 constituting the dendrite, is 5 μm or less. In this regard, it is preferred that the average of the above-mentioned distances is 3 μm or less. It is also preferred that the compound phase 3 is formed discontinuously in the dendrite spaces.
B22F 3/105 - Frittage seul en utilisant un courant électrique, un rayonnement laser ou un plasma
B22F 3/16 - Compactage et frittage par des opérations successives ou répétées
F16K 25/00 - Détails constitutifs relatifs au contact entre corps de soupapes ou de clapets et leurs sièges
C22C 19/07 - Alliages à base de nickel ou de cobalt, seuls ou ensemble à base de cobalt
C22F 1/00 - Modification de la structure physique des métaux ou alliages non ferreux par traitement thermique ou par travail à chaud ou à froid
C22F 1/10 - Modification de la structure physique des métaux ou alliages non ferreux par traitement thermique ou par travail à chaud ou à froid du nickel ou du cobalt ou de leurs alliages
This pipe connection method includes: a step for connecting one side of a connection member (7) and an end portion (2t) of a first pipe (2) having a flange surface (8), by means of a first lap joint flange (3, 3a) inserted into the first pipe (2) and a flange (3b) on the one side of the connection member, such that the flange surface (8) is sandwiched therebetween; and a step for connecting the other side of the connection member (7) and an end portion (5t) of a second pipe (5) having a flange surface (9), by means of a second lap joint flange (6, 6a) inserted into the second pipe (5) and a flange (6b) on the other side of the connection member, such that the flange surface (9) is sandwiched therebetween, while deforming the connection member (7) to absorb deflection.
An ultrasonic flaw detection method and device identifies echoes appearing in flaw detection images. By selecting and controlling combinations of transmitting elements and receiving elements, plural waveform signals c are recorded. For each position in an inspection object, intensities of plural waveform signals are extracted based on the propagation time of ultrasonic waves and are totalized. A flaw detection image showing distribution of totalized intensities is generated. By selectively using at least three sound velocities for calculating propagation time of ultrasonic waves, at least three flaw detection images are generated. The areas of at least three echoes respectively appearing in the flaw detection images are calculated and the echo area which is the smallest is identified according to whether or not the flaw detection image showing the echo is one generated using one of a longitudinal sound velocity, a transverse sound velocity and a medium sound velocity.
The present invention provides an organic iodine collection device and an organic iodine collection method which can efficiently collect organic iodine in a nuclear reactor container. An organic iodine collection device (100), which collects organic iodine in a nuclear reactor container (10), is provided with: a liquid container (1) which contains a non-volatile liquid (L1) (for example, ionic liquid, surfactant solution) that can decompose organic iodine; and an introduction pipe (2a) for introducing, into the non-volatile liquid (L1), an organic iodine-containing fluid in the nuclear reactor container (10), wherein the non-volatile liquid (L1) is heated by heat in the nuclear reactor container (10) or by reaction heat of the fluid in the nuclear reactor container (10), and then decomposes organic iodine, thereby collecting the organic iodine. The organic iodine collection method involves heating a non-volatile liquid (L1), which can decompose organic iodine, by heat in a nuclear reactor container (10) or by reaction heat of a fluid in the nuclear reactor container (10), causing the fluid containing the organic iodine to pass through the non-volatile liquid (L1), and decomposing and collecting the organic iodine in the non-volatile liquid (L1).
brevets
