Abrégé

The present invention relates to a method for measuring vibration of an internal structure of a small-scaled reactor vessel model, the method comprising the steps of: arranging a detachable sensor fixing unit on the internal structure; installing a vibration measurement sensor that is coupled to the sensor fixing unit and measures the vibration of the internal structure; evaluating a level of the vibration of the internal structure by using the vibration measurement sensor; and disassembling the sensor fixing unit and the vibration measurement sensor after the evaluation.

Classes IPC  ?

• G01H 1/00 - Mesure des vibrations dans des solides en utilisant la conduction directe au détecteur
• G01M 7/02 - Test de vibration
• G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires

Abrégé

The present technology relates to a system and a method for operating a generator. According to an implementation of the present embodiment, local information including generator distance adjacent to each of a plurality of generators and a transmission network condition, operation information including a generator capacity and characteristics of an energy source, and time information such as maintenance period and maintenance and accident history are reflected to optimize a backup generator and construct a learning model, and an optimal backup generator is selected on the basis of the learning model with respect to an accident failure generator that is input on the basis of the constructed learning model, and thus an optimal power backup generator can be selected.

Classes IPC  ?

• H02J 3/00 - Circuits pour réseaux principaux ou de distribution, à courant alternatif
• H02J 9/06 - Circuits pour alimentation de puissance de secours ou de réserve, p.ex. pour éclairage de secours dans lesquels le système de distribution est déconnecté de la source normale et connecté à une source de réserve avec commutation automatique
• H02J 3/38 - Dispositions pour l’alimentation en parallèle d’un seul réseau, par plusieurs générateurs, convertisseurs ou transformateurs
• G06Q 50/06 - Fourniture d'électricité, de gaz ou d'eau

Abrégé

The present invention relates to a supply device for supplying liquid waste to a low-temperature melting furnace. The supply device for supplying liquid waste to a low-temperature melting furnace comprises: a storage unit in which the liquid waste and a solvent are stored; a supply pipe through which the liquid waste and the solvent are supplied from the storage unit to a melting space in the low-temperature melting furnace; and a transfer unit which is at least partially located in the supply pipe and forcibly injects the liquid waste and solvent into the melting space via a spiral supply flow path.

Classes IPC  ?

• G21F 9/30 - Traitements
• F27D 3/08 - Chargeurs à vis; Déchargeurs à vis

Abrégé

Provided are a method for verifying validity of measurement/metering information for DPI-based packet filtering and a distributed energy resource gateway using same. The method for verifying validity of measurement/metering information comprises the steps of: collecting first measurement/metering information from a smart meter and collecting second measurement/metering information from a smart inverter; calculating an error between the first measurement/metering information and the second measurement/metering information and confirming whether or not the calculated error is within the maximum possible error range; and performing a deep packet inspection (DPI) function according to the result of the confirmation.

Classes IPC  ?

• H04L 9/40 - Protocoles réseaux de sécurité
• G01R 15/18 - Adaptations fournissant une isolation en tension ou en courant, p.ex. adaptations pour les réseaux à haute tension ou à courant fort utilisant des dispositifs inductifs, p.ex. des transformateurs
• G01R 31/40 - Tests d'alimentation
• G01R 19/165 - Indication de ce qu'un courant ou une tension est, soit supérieur ou inférieur à une valeur prédéterminée, soit à l'intérieur ou à l'extérieur d'une plage de valeurs prédéterminée
• G01R 21/00 - Dispositions pour procéder aux mesures de la puissance ou du facteur de puissance
• G01R 35/00 - Test ou étalonnage des appareils couverts par les autres groupes de la présente sous-classe

Abrégé

The present invention relates to a gamma spectrum separation system for whole body contamination test equipment for generating artificial neural network learning data, and to a gamma spectrum separation system for whole body contamination test equipment for generating artificial neural network learning data, the system having a single nuclide spectrum separated from a spectrum in which various nuclides are mixed. The present invention comprises: an efficiency calculation unit for calculating the efficiency of each of channels A, B, and C of the whole body contamination test equipment; a counting rate contribution amount calculation unit, which multiplies, by the efficiency of each channel, the value obtained by multiplying the gamma-ray emission rate of each nuclide and a mixed source for generating artificial neural network learning data, so as to calculate a counting rate contribution amount of each channel; and a normalization unit, which subtracts the counting rate contribution amount of each channel from the counting rate of each channel measured by means of the nuclide, and then performs normalization to obtain a normalized spectrum of the nuclide, thus the present invention has the effect of separating the spectrum of a single nuclide from the spectrum in which various nuclides are mixed so as to use same in the generation of synthetic spectra for artificial intelligence learning.

Classes IPC  ?

• G01T 1/163 - Compteurs pour le corps en entier
• G01T 1/167 - Mesure du contenu radioactif des objets, p.ex. contamination
• G01T 7/00 - MESURE DES RADIATIONS NUCLÉAIRES OU DES RAYONS X - Détails des instruments de mesure des radiations
• G06N 3/04 - Architecture, p.ex. topologie d'interconnexion
• G06N 3/08 - Méthodes d'apprentissage

Abrégé

The present invention relates to a method for processing anomalies that occur in power plant equipment and, particularly, to a method for anomaly signal processing and machine learning prediction based on an anomaly cumulative threshold and a method for machine learning prediction according thereto, the methods managing a cumulative history of anomalies in order to apply a signal processing and data based machine learning technique for discovering, in advance, failure anomalies, so as to establish basic learning reference data, and performing machine learning prediction therethrough in order to increase prediction performance of machine learning through a scheme of processing a signal of excellent quality when operation data of the power plant equipment is input.

Classes IPC  ?

• G06Q 50/06 - Fourniture d'électricité, de gaz ou d'eau
• G06Q 10/06 - Ressources, gestion de tâches, des ressources humaines ou de projets; Planification d’entreprise ou d’organisation; Modélisation d’entreprise ou d’organisation
• G06Q 10/04 - Prévision ou optimisation spécialement adaptées à des fins administratives ou de gestion, p. ex. programmation linéaire ou "problème d’optimisation des stocks"
• G06N 20/00 - Apprentissage automatique
• G06F 17/18 - Opérations mathématiques complexes pour l'évaluation de données statistiques
• G06Q 50/10 - Services
• G01D 21/02 - Mesure de plusieurs variables par des moyens non couverts par une seule autre sous-classe

Abrégé

The present invention may comprise: a state monitoring module for diagnosing the state of a power plant structure; a growth recognition module for calculating a growth rate; a maintenance management module for calculating maintenance according to the state of the power plant structure; a power generation monitoring module for managing the output state of the solar power generation; and an operation control module for calculating the operating state of the power plant and notifying the operation server of the calculated results. The present invention calculates an operation plan by monitoring each of the states of the power plant structure, crops, and power generation amount, and provides guidelines by which the solar power plant can be operated on the basis of the calculated data, and thus can maximize profits of a solar power plant.

Classes IPC  ?

• H02S 50/00 - Surveillance ou tests de systèmes PV, p.ex. équilibrage de charge ou identification des défauts
• G06V 10/10 - Acquisition d’images
• G06N 3/02 - Réseaux neuronaux
• G08B 21/18 - Alarmes de situation
• G06T 7/90 - Détermination de caractéristiques de couleur
• G01W 1/10 - Dispositifs pour la prévision des conditions météorologiques

Abrégé

The present disclosure relates to a method of calculating a future possible maximum typhoon for a nuclear power plant site, and the method includes analyzing historical typhoons to select a previous maximum typhoon as a reference typhoon, and calculating the future possible maximum typhoon by strengthening the reference typhoon using an ocean-atmosphere coupled model.

Classes IPC  ?

• G01W 1/10 - Dispositifs pour la prévision des conditions météorologiques

Abrégé

Disclosed is a sample collection system for collecting, as a sample, a portion of glass melt produced in a melting furnace of a radioactive waste vitrification facility for vitrifying radioactive wastes. The sample collection system according to an embodiment of the present invention collects, as a glass melt sample, a portion of the glass melt generated and discharged from a vitrification facility including a vitrification melting furnace and a glass solidification mold and vitrifying radioactive wastes, the sample collection system comprising a glass melt sample collection device. The glass melt sample collection device may comprise: a sample receiving portion that receives the glass melt sample discharged from the vitrification melting furnace; a transfer pipe which is connected to the sample receiving portion through which the received glass melt sample is transferred; and a sample solidification mold which is connected to the transfer pipe and solidifies the glass melt sample to generate a solid sample.

Classes IPC  ?

• G01N 1/10 - Dispositifs pour prélever des échantillons à l'état liquide ou fluide
• G21F 9/30 - Traitements
• G01N 1/00 - Echantillonnage; Préparation des éprouvettes pour la recherche

Abrégé

A glass melting furnace apparatus and a method for operating same are provided. The method for operating the glass melting furnace apparatus comprises the steps of: putting an object to be melted into a lower chamber unit of the glass melting furnace apparatus; and complexly monitoring, in an upper chamber unit of the glass melting furnace apparatus, the input state of the object to be melted, and the molten glass-related operating state of the lower chamber unit, wherein the upper chamber unit includes: an upper chamber; a main monitoring module which is mounted on the upper chamber, and which monitors, in an operating state for molten glass in the lower chamber unit, the state of the object to be melted; and a first auxiliary monitoring module which is mounted on the upper chamber, and which monitors, in an operating state for the molten glass in the lower chamber unit, the state of the object to be melted, and the first auxiliary monitoring module is operated in either a first mode of operating complexly with the main monitoring module, or a second mode of operating instead of the main monitoring module if the main monitoring module functionally fails.

Classes IPC  ?

• G21F 9/30 - Traitements
• C03B 5/00 - Fusion dans des fours; Fours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre
• C03B 5/235 - Chauffage du verre
• C03B 5/24 - Régulation automatique de la fusion

Abrégé

Provided are a melt discharge apparatus and method for a glass melting furnace in a nuclear power plant. The melt discharge apparatus for a glass melting furnace in a nuclear power plant comprises a discharge assembly which has a target receiving a melt positioned at the top thereof and is for continuously discharging the melt downward. The discharge assembly includes: a body module; a driving module for providing a driving force; a nozzle module for discharging the melt from the target; a heating module for heating the nozzle module by induction heating; a first temperature measurement module for obtaining first temperature information according to the heating of the nozzle module; and a second temperature measurement module for obtaining, separately from the first temperature information, second temperature information, which is temperature information according to the heating of the nozzle module, wherein the heating module maintains the nozzle module at a set temperature on the basis of the first temperature information and the second temperature information.

Classes IPC  ?

• G21F 9/30 - Traitements
• H05B 6/06 - Commande, p.ex. de la température, de la puissance
• C03B 5/00 - Fusion dans des fours; Fours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre

Abrégé

Provided is a vitrification device and method for a nuclear power plant. The vitrification device for a nuclear power plant comprises: an upper chamber unit; a driving unit for providing driving force; a lower chamber unit including an internal space in which molten glass is accommodated; and a hollow entry unit which enables entry into the internal space of the lower chamber unit through the upper chamber unit and through which an object is supplied to the molten glass, wherein the entry unit includes a bar-shaped body part and a plurality of branch parts branching off from the body part, and performs variable operation on the basis of the driving force from the driving unit while the object is distributed and injected into the molten glass via the body part or the branch parts.

Classes IPC  ?

• G21F 9/30 - Traitements
• C03B 3/00 - Enfournement
• C03B 5/187 - Agitateurs; Homogénéisation avec des éléments en mouvement

Abrégé

Provided are an automation system and automation method for nuclear power plant accident analysis. An automation method for nuclear power plant accident analysis comprises the steps in which: in a primary input information generation module, primary input information including user input information and event tree information regarding accident scenario information for accident analysis is loaded; in an accident scenario information generation module, accident scenario information of a nuclear power plant is generated on the basis of the primary input information; in a secondary input information generation module, secondary input information for accident analysis is generated on the basis of the accident scenario information; and in an accident analysis performance module, accident analysis information is generated by performing accident analysis for the nuclear power plant on the basis of the secondary input information.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G21C 17/00 - Surveillance; Tests
• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu
• G06F 119/02 - Analyse de fiabilité ou optimisation de fiabilité; Analyse de défaillance, p.ex. performance dans le pire scénario, analyse du mode de défaillance et de ses effets [FMEA]

Abrégé

An artificial intelligence (AI) feedback system is provided. The AI feedback system includes: a script extractor/executor receiving input 1, which includes basic materials for learning, and input 2, which includes key contents for learning, and generating initial conditions for popularity frequency values or ranking values of information related to input 2 from input 1; an AI connected to the script extractor/executor, the AI generating a two-dimensional (2D) information table in a matrix form with both axes for keywords and key information, respectively, based on popularity frequency values or ranking values derived from the initial conditions, adding the popularity frequency values or ranking values to corresponding coordinates of the 2D information table, and matching acquired knowledge to the corresponding coordinates; an output unit connected to the AI and outputting deep truth values derived by the AI from the 2D information table; and a repository connected to the AI, organizing and storing, by category, the context of knowledge formed by linking the deep truth values derived by the AI.

Classes IPC  ?

• G06N 5/022 - Ingénierie de la connaissance; Acquisition de la connaissance

Abrégé

A method for determining heat and reflected heat in a thermal image, according to the present invention, comprises the steps of: a) photographing a subject through a thermal imaging camera so as to collect a thermal image of the subject; b) analyzing features according to the thermal image temperature distribution of the thermal image; c) detecting the heat and the reflected heat in the thermal image according to the analysis in step b); and d) displaying, as heat and reflected heat regions in the thermal image, the heat and the reflected heat in the thermal image detected in step c).

Classes IPC  ?

• H04N 5/33 - Transformation des rayonnements infrarouges
• G01J 5/00 - Pyrométrie des radiations, p.ex. thermométrie infrarouge ou optique
• G01J 5/02 - Pyrométrie des radiations, p.ex. thermométrie infrarouge ou optique - Détails structurels
• G06F 18/23 - Techniques de partitionnement
• G06N 3/08 - Méthodes d'apprentissage
• G06T 7/11 - Découpage basé sur les zones

Abrégé

The present invention relates to a method for calculating a heat output by using an in-core instrument, the method comprising the steps of: measuring a core inlet temperature and a core exit temperature by using the in-core instrument; and calculating a heat output (Q) of a core by using the following equation, wherein the in-core instrument comprises: a first thermocouple for measuring the core inlet temperature; and a second thermocouple for measuring the core exit temperature. [Equation] Here, Q denotes heat quantity, C denotes specific heat, m denotes mass flow rate, Th denotes core exit temperature, and Tc denotes core inlet temperature.

Classes IPC  ?

• G21C 17/112 - Mesure de la température
• G21C 17/108 - Mesure du flux
• G01K 7/02 - Mesure de la température basée sur l'utilisation d'éléments électriques ou magnétiques directement sensibles à la chaleur utilisant des éléments thermo-électriques, p.ex. des thermocouples
• G01K 17/10 - Mesure d'une quantité de chaleur transportée par des milieux en écoulement, p.ex. dans les systèmes de chauffage basée sur la mesure d'une différence de température entre un point d'entrée et un point de sortie, combinée avec la mesure du débit de l'écoulement d'un milieu
• G01T 3/00 - Mesure de flux de neutrons

Abrégé

The present invention provides a method for testing a leakage rate of a nuclear reactor containment building, the method comprising: a partitioning step of separating the nuclear reactor containment building into an upper region and a lower region by using an isolation device; a measurement step of measuring a leakage rate of the containment building after pressurizing the inside of the containment building to a maximum pressure; and a determination step of determining whether the leakage rate measured in the measurement step satisfies a leakage rate allowance criterion of the containment building.

Classes IPC  ?

• G21C 17/003 - Inspection à distance des enceintes, p.ex. des cuves de pression
• G01M 3/32 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par mesure du taux de perte ou de gain d'un fluide, p.ex. avec des dispositifs réagissant à la pression, avec des indicateurs de débit pour récipients, p.ex. radiateurs

Abrégé

The present invention relates to an apparatus for removing dust discharged from a melting furnace and, particularly, to a melting apparatus comprising: an exhaust part which exhausts dust and moisture, discharged from a melting space of a melting furnace, to the outside; a filter which is disposed within the exhaust part and one surface of which is arranged to be opposite to the melting space; and a dust removal part which enhances the dust removal performance of the filter.

Classes IPC  ?

• G21F 9/02 - Traitement des gaz
• G21F 9/30 - Traitements
• G21F 9/32 - Traitements par incinération
• G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination
• B01D 46/66 - Régénération de la substance filtrante ou des éléments filtrants à l'intérieur du filtre
• B01D 53/75 - Procédés multi-étapes
• B01D 53/26 - Séchage des gaz ou vapeurs
• B01D 53/30 - Commande par appareil d'analyse des gaz

Abrégé

Disclosed are a high-voltage direct current (HVDC) cable partial discharge diagnosis system and method. The HVDC cable partial discharge diagnosis system according to one aspect of the present invention comprises: a sensor provided on an HVDC cable; a plurality of HVDC cable partial discharge measurement devices for acquiring measurement result information from the sensor and detecting a partial discharge signal from the measurement result information; and an HVDC cable partial discharge diagnosis device which receives the partial discharge signal from the HVDC cable partial discharge measurement devices and diagnoses whether partial discharge has occurred in the HVDC cable, through pattern analysis of the partial discharge signal.

Classes IPC  ?

• G01R 31/08 - Localisation de défauts dans les câbles, les lignes de transmission ou les réseaux

Abrégé

The present invention provides a combustion state prediction device for a power plant boiler and a method thereof. The combustion state prediction device for a power plant boiler of the present invention includes: an operation variable input module for receiving an operation variable for operation of the boiler; an operation information database for storing operation information of the boiler; an output module for displaying prediction data; and a processor operatively coupled to the operation variable input module, the operation information database, and the output module, wherein the processor operates an execution program to predict a combustion state of the boiler on the basis of a prediction model based on an operation variable input from the operation variable input module and operation information of the boiler stored in the operation information database, and output prediction data through the output module.

Classes IPC  ?

• G06F 30/27 - Optimisation, vérification ou simulation de l’objet conçu utilisant l’apprentissage automatique, p.ex. l’intelligence artificielle, les réseaux neuronaux, les machines à support de vecteur [MSV] ou l’apprentissage d’un modèle
• G06F 30/17 - Conception mécanique paramétrique ou variationnelle
• F22B 35/18 - Utilisation des machines à calculer pour la commande des chaudières à vapeur
• G06F 111/04 - CAO basée sur les contraintes
• G06F 119/08 - Analyse thermique ou optimisation thermique
• G06F 111/10 - Modélisation numérique

Abrégé

The present invention relates to a method for detecting a cavity in a structure using elastic waves, the method comprising the steps in which: a plurality of acceleration sensors capable of measuring acceleration in three axial directions are installed in the structure; a plurality of three-dimensional loads having elastic waves are applied near the acceleration sensors and three-dimensional accelerations are measured by the acceleration sensors; two-dimensional distributed load data is generated by superimposing the three-dimensional loads applied for each of the plurality of acceleration sensors; superimposed acceleration data is calculated by superimposing the measured three-dimensional accelerations; and the two-dimensional distributed load data and the superimposed acceleration data are applied to a two-dimensional elastic wave inverse analysis algorithm.

Classes IPC  ?

• G01N 29/04 - Analyse de solides
• G01N 29/44 - Traitement du signal de réponse détecté
• G01P 15/18 - Mesure de l'accélération; Mesure de la décélération; Mesure des chocs, c. à d. d'une variation brusque de l'accélération dans plusieurs dimensions

Abrégé

A vibration measurement error determination method according to an embodiment of the present invention comprises: a vibration data acquisition step for acquiring vibration data by measuring a vibration generated in a structure; a first determination step for determining, on the basis of a preset error data selection rule, whether the vibration data is data generated by a measurement error; a second determination step for using a machine-learning algorithm to determine whether the vibration data is data generated by a measurement error; and a final determination step for determining, on the basis of the results determined in the first determination step and the second determination step, whether the vibration data is data generated by a measurement error.

Classes IPC  ?

• G01H 1/00 - Mesure des vibrations dans des solides en utilisant la conduction directe au détecteur

Abrégé

Disclosed is a radioactive waste supplying device used in a radioactive waste vitrification facility for vitrifying radioactive waste. A radioactive waste supplying device according to an embodiment of the present invention supplies radioactive waste to a vitrification melting furnace. The radioactive waste supplying device may comprise: a main supply pipe including one end and the other end, the one end facing the vitrification melting furnace, and supplying the radioactive waste in the direction from the other end toward the one end; a sub-supply pipe including one side and the other side and disposed in the main supply pipe in such a manner that the one side is adjacent to the one end; and a scattering part positioned on one side of the sub-supply pipe and causing the radioactive waste passing through the sub-supply pipe to be scattered and input into the melting furnace.

Classes IPC  ?

• G21F 9/30 - Traitements
• C03B 5/00 - Fusion dans des fours; Fours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre

Abrégé

Disclosed is a liquid waste removal system for removing liquid waste remaining in a concrete drum that stores containers charged with concentrated waste liquid. The liquid waste removal system according to an embodiment of the present invention is for removing liquid waste remaining in a concrete drum that stores containers charged with radioactive waste, and may comprise: a fixed support that supports and fixes the concrete drum; and a transfer pipe that passes through one side of the concrete drum and discharges the liquid waste out of the concrete drum.

Classes IPC  ?

• G21F 9/16 - Traitements par fixation dans un milieu solide stable
• B01D 29/11 - Filtres à éléments filtrants stationnaires pendant la filtration, p.ex. filtres à aspiration ou à pression, non couverts par les groupes ; Leurs éléments filtrants avec des éléments filtrants en forme de sac, de cage, de tuyau, de tube, de manchon ou analogue
• B01D 29/92 - Filtres à éléments filtrants stationnaires pendant la filtration, p.ex. filtres à aspiration ou à pression, non couverts par les groupes ; Leurs éléments filtrants comportant des dispositifs d'alimentation ou d'évacuation d'évacuation du filtrat
• B23B 47/26 - Têtes de perçage ou poupées porte-broches pouvant effectuer un mouvement ascendant ou descendant; Agencements pour l'équilibrage de ces éléments

Abrégé

Disclosed is a system for inputting liquid radioactive waste into a vitrification melting furnace for vitrifying the radioactive waste. A liquid radioactive waste input system according to an embodiment of the present invention inputs liquid radioactive waste into a vitrification melting furnace for vitrifying the radioactive waste, and may comprise: a waste storage tank for storing the liquid radioactive waste; and a waste input device that receives the liquid radioactive waste from the waste storage tank and inputs the received liquid radioactive waste into the vitrification melting furnace.

Classes IPC  ?

• G21F 9/30 - Traitements
• C03B 5/00 - Fusion dans des fours; Fours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre

Abrégé

Disclosed are a radioactive waste immobilization device having radioactive waste storage safety reinforced by immobilizing radioactive waste contained in a high-integrity container, and a radioactive waste immobilization method using same. To prevent the possibility of radioactive waste charged into a high-integrity container from being released to the outside, the radioactive waste immobilization device according to an embodiment of the present invention is for immobilizing the upper portion of the radioactive waste in the high-integrity container, and may comprise: a polymer resin injection part that forms a polymer resin layer by injecting a polymer resin for immobilization into the radioactive waste contained in the high-integrity container; a polymer resin sensing part that adjusts the injection amount of the polymer resin by measuring the lamination thickness of the polymer resin layer; and a photocuring part that cures the polymer resin layer.

Classes IPC  ?

• G21F 9/16 - Traitements par fixation dans un milieu solide stable
• G01B 11/06 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer la longueur, la largeur ou l'épaisseur pour mesurer l'épaisseur

Abrégé

Disclosed is an apparatus for loading a heating element for heating molten glass, in order to restart a vitrification melting furnace, for vitrifying radioactive waste, when the vitrification melting furnace has an emergency shutdown. The apparatus for loading a heating element for a vitrification melting furnace, according to one embodiment of the present invention, is for loading a heating element into a glass melting furnace for vitrifying radioactive waste, and may comprise: a main frame; a universal joint positioned on one end of the main frame; at least one heating element coupling part rotatably connected to the universal joint; and a gripper positioned on an end of the heating element coupling part so as to grab a heating element.

Classes IPC  ?

• G21F 9/30 - Traitements
• C03B 3/02 - Enfournement combiné à un préchauffage, une préfusion ou un prétraitement des ingrédients vitrifiables, des granulés ou des groisils
• C03B 5/00 - Fusion dans des fours; Fours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre

Abrégé

The present invention relates to a method for estimating a strongest possible future typhoon for a nuclear power plant site, the method comprising the steps of: analyzing historical typhoons and selecting, as a reference typhoon, the strongest typhoon that previously occurred; and estimating the strongest possible future typhoon by strengthening the reference typhoon using a combined ocean-atmosphere model.

Classes IPC  ?

• G01W 1/06 - Instruments pour indiquer des conditions atmosphériques par mesure de plusieurs variables, p.ex. humidité, pression, température, nébulosité ou vitesse du vent donnant l'indication des conditions météorologiques par combinaison des variables mesurées
• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu

Abrégé

Provided is a system for detecting an object in an underground space. The system for detecting the object in the underground space includes a movable body moving in the underground space, a wide-angle camera mounted on the movable body to photograph an underground facility in the underground space, an object detection terminal configured to receive an image of the underground facility photographed by the wide-angle camera and correct a corresponding distorted image so as to detect the underground facility corresponding to an object set within the corrected image; and a communication network configured to enable network communication between the movable body and the object detection terminal. Thus, the system may have an effect of robustly detecting the object in an image with a large change in size of an object formed on an image according to the distortion and distance such as the wide-angle or omnidirectional camera.

Classes IPC  ?

• G06V 10/25 - Détermination d’une région d’intérêt [ROI] ou d’un volume d’intérêt [VOI]
• G06T 5/00 - Amélioration ou restauration d'image
• G06T 5/20 - Amélioration ou restauration d'image en utilisant des opérateurs locaux
• G06V 10/44 - Extraction de caractéristiques locales par analyse des parties du motif, p.ex. par détection d’arêtes, de contours, de boucles, d’angles, de barres ou d’intersections; Analyse de connectivité, p.ex. de composantes connectées
• G06V 10/764 - Dispositions pour la reconnaissance ou la compréhension d’images ou de vidéos utilisant la reconnaissance de formes ou l’apprentissage automatique utilisant la classification, p.ex. des objets vidéo
• G06V 20/56 - Contexte ou environnement de l’image à l’extérieur d’un véhicule à partir de capteurs embarqués
• H04N 23/698 - Commande des caméras ou des modules de caméras pour obtenir un champ de vision élargi, p. ex. pour la capture d'images panoramiques

Abrégé

A turbine blade erosion measurement system of the present invention comprises: a light irradiation device that irradiates light so as to generate difference in brightness in order to distinguish a measurement area during inspection of the turbine blade; an optical image acquisition device that generates an optically photographed image of the surface of the blade; and an image analysis and erosion calculation device that analyzes the image photographed by the optical image acquisition device and calculates the amount of erosion of the blade, wherein the light irradiation device and the optical image acquisition device face each other, having a blade to be analyzed stationed there-between, and move in parallel along the circumferential direction of the turbine, while taking images of the blade to be analyzed, and the image analysis and erosion calculation device may calculate the amount of erosion by adding up the amount of erosion at a plurality of measurement spots located inside the blade.

Classes IPC  ?

• G01N 21/88 - Recherche de la présence de criques, de défauts ou de souillures
• G06T 7/00 - Analyse d'image

Abrégé

Disclosed is a system capable of optimizing an early warning operation by introducing alarm filtering technology so that false alarms from abnormal signals due to signal noise are prevented. The system comprises: a data acquisition unit for selectively acquiring detail data resulting from the operation of power equipment through the selection of preset multivariate input tags; a recommendation unit for generating, from the detail data, on the basis of a preset similarity, training data that is a multivariate signal for machine learning; a compression unit, which compresses the training data so as to generate resampling data; a training unit, which uses the resampling data as input data for a pre-designed early warning training model so as to perform real-time monitoring; and a calculation unit for generating a final alarm if predefined schedule conditions are satisfied through the real-time monitoring.

Classes IPC  ?

• G08B 29/18 - Prévention ou correction d'erreurs de fonctionnement
• G08B 31/00 - Systèmes d'alarme à prédiction caractérisés par une extrapolation ou un autre type de calcul utilisant des données historiques mises à jour
• G06N 20/00 - Apprentissage automatique
• G08B 21/18 - Alarmes de situation
• G08B 29/20 - Etalonnage, y compris les dispositions d'auto-étalonnage

Abrégé

The present invention relates to a method of generating a word embedding library, including: receiving, by a processor, original text composed of Hangul through an input interface; segmenting, by the processor, the original text by morpheme, combining segmented morphemes step by step according to a preset rule, and matching a tag to a combination of step-by-step morphemes according to a morphological attribute or a syntactic attribute of the combination of step-by-step morphemes; and generating, by the processor, a word embedding library by classifying the morphemes included in the original text based on the tag matched to the combination of step-by-step morphemes.

Classes IPC  ?

• G06F 40/211 - Parsage syntaxique, p.ex. basé sur une grammaire hors contexte ou sur des grammaires d’unification
• G06F 40/129 - Maniement de caractères non latins, p.ex. conversion du kana vers le kanji
• G06F 40/268 - Analyse morphologique

Abrégé

An operation prediction system for multiple devices, according to one embodiment of the present invention, comprises: a control unit; a first device of which the operation state is changed by being controlled by the control unit; a second device which is linked to the first device; a prediction input unit which receives a prediction input which is an input for predicting the operation state to be changed of the first device; and a state prediction unit which predicts operation prediction information including information on the operation state of the first device, which is to be changed by the controlling of the control unit, and information on the impact on the second device as a result of the operation state to be changed of the first device.

Classes IPC  ?

• G05B 13/04 - Systèmes de commande adaptatifs, c. à d. systèmes se réglant eux-mêmes automatiquement pour obtenir un rendement optimal suivant un critère prédéterminé électriques impliquant l'usage de modèles ou de simulateurs
• G05B 23/02 - Test ou contrôle électrique

Abrégé

The present invention relates to a simulation system for simulating the behavior of a power plant, the system being characterized by: collecting all field values in the power plant at an nth point in time; simulating the behavior of the power plant at the nth point in time through a numerical analysis of a power plant model on the basis of the collected field values; providing, as a second initial condition, a field value obtained through the numerical analysis of the power plant model; and determining a simulation calculation method according to the result of comparing the power plant field values and a simulation calculation value.

Classes IPC  ?

• G05B 19/418 - Commande totale d'usine, c.à d. commande centralisée de plusieurs machines, p.ex. commande numérique directe ou distribuée (DNC), systèmes d'ateliers flexibles (FMS), systèmes de fabrication intégrés (IMS), productique (CIM)
• G05B 13/04 - Systèmes de commande adaptatifs, c. à d. systèmes se réglant eux-mêmes automatiquement pour obtenir un rendement optimal suivant un critère prédéterminé électriques impliquant l'usage de modèles ou de simulateurs
• G05B 23/02 - Test ou contrôle électrique

Abrégé

The present invention relates to an integrated nuclear reactor system including a double containment structure using liquid nitrogen, the nuclear reactor system comprising: a reactor vessel; a reactor core disposed in the reactor vessel; a steam generator disposed in the reactor vessel and located above the reactor core; a first containment vessel surrounding the reactor vessel with a first space interposed therebetween; a second containment vessel surrounding the first containment vessel with a second space interposed therebetween; and a liquid nitrogen supply unit supplying liquid nitrogen into the second space.

Classes IPC  ?

• G21C 9/012 - Suppression de la pression par accumulation thermique ou condensation de vapeur, p.ex. condenseurs à glace
• G21C 13/10 - Moyens pour prévenir la contamination dans le cas d'une fuite
• G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur

Abrégé

According to an embodiment, an RE100 energy transaction system using a blockchain is provided, the system comprising: a first blockchain node for generating power production information and sales information according to the production of renewable energy, and sharing the power production information and the sales information with a node participating in a blockchain network; a second blockchain node for generating power purchase information, and sharing the power purchase information with the node participating in the blockchain network; and a certification authority for performing authentication procedures of the first blockchain node and the second blockchain node participating in the blockchain network, wherein the first blockchain node and the second blockchain node store a first blockchain relating to the power production information and the sales information and a second blockchain relating to the power purchase information, and update the first blockchain and the second blockchain when a renewable energy transaction occurs.

Classes IPC  ?

• G06Q 50/06 - Fourniture d'électricité, de gaz ou d'eau
• G06Q 20/38 - Architectures, schémas ou protocoles de paiement - leurs détails

Abrégé

Disclosed is an intelligent health index calculation system capable of evaluating the health index of equipment on the basis of operation/maintenance/monitoring data. The health index calculation system comprises: first to nth sensor systems, which senses the state of equipment assets so as to generate sensing data; first to nth collection devices for collecting the sensing data from each of the first to nth sensor systems; a maintenance history server for providing, through a communication network, maintenance history data executed for the equipment assets; and a computer, which uses the sensing data and the maintenance history data so as to calculate an intelligent health index for state evaluation of the equipment assets.

Classes IPC  ?

• G05B 23/02 - Test ou contrôle électrique
• G06Q 50/06 - Fourniture d'électricité, de gaz ou d'eau
• G06Q 50/10 - Services
• G06Q 10/06 - Ressources, gestion de tâches, des ressources humaines ou de projets; Planification d’entreprise ou d’organisation; Modélisation d’entreprise ou d’organisation

Abrégé

A waste liquid treatment facility according to an exemplary embodiment of the present invention includes: a filter connected to a system of a nuclear power plant; a demineralizer connected to the filter; a reactor connected to the demineralizer and including a first lamp and a second lamp of different wavelengths connected in succession; a buffer tank connected to the filter, demineralizer, and reactor; and a circulation pipe portion connecting the filter, demineralizer, reactor, and buffer tank to form a circulation structure of a solution together with the system, wherein the solution sequentially passes through the first lamp and the second lamp.

Classes IPC  ?

• G21F 9/06 - Traitements
• G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination

Abrégé

Provided is a UV reaction apparatus for treating waste liquid caused by system decontamination in a nuclear power plant. The UV reaction apparatus comprises a UV irradiation unit for irradiating UV light as a bar-shaped body; and a transit unit accommodating the UV irradiation unit therein, and for passing organic waste liquid to be irradiated with the UV light, wherein the transit unit comprises, an input unit, into which the organic waste liquid is input a discharge unit, through which the organic waste liquid is discharged, and an intermediate unit located between the input unit and the discharge unit, and in which the UV irradiation unit is located.

Classes IPC  ?

• C02F 1/32 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par irradiation par la lumière ultraviolette

Abrégé

Provided is a device for monitoring degradation of wastewater from nuclear power plant decontamination. The device for monitoring degradation of wastewater from nuclear power plant decontamination comprises a UV reactor connected to a first flow path and for UV-treating introduced wastewater; a wastewater degradation flow path for supplying the wastewater discharged from the UV reactor to the first flow path; a wastewater degradation detecting unit for analyzing components of the wastewater supplied from the wastewater degradation flow path and detecting whether a set condition is satisfied; and a purification flow path for purifying and supplying the wastewater supplied from the UV reactor to the first flow path when the set condition is satisfied.

Classes IPC  ?

• G21F 9/06 - Traitements

Abrégé

33 aqueous solution into the reaction vessel in which the bicarbonate ions are generated so as to form a first buffer system; and a step (S300) of adding a medium to the first buffer system, inoculating microalgae, and then photoculturing the microalgae while supplying carbon dioxide.

Classes IPC  ?

• C12N 1/12 - Algues unicellulaires; Leurs milieux de culture
• C12M 1/00 - Appareillage pour l'enzymologie ou la microbiologie

Abrégé

A component interface module with enhanced user convenience, according to the present invention, is a component interface module for managing the interface between a control system, which generates component command signals, and components, which generates component feedback signals, wherein the components are classified into first to third component groups, the component interface module is formed from first to third component interface modules, each of the first to third component interface modules includes: an input port; a processor including a priority logic, a component logic and a diagnostic logic; and an output device, the priority logic is set using a four-contact rotary switch for selecting any one of four settings in order to set the priority for the component command signals, and the component logic is set using a control rotary switch of each of the first to third component interface modules.

Classes IPC  ?

• G05B 19/418 - Commande totale d'usine, c.à d. commande centralisée de plusieurs machines, p.ex. commande numérique directe ou distribuée (DNC), systèmes d'ateliers flexibles (FMS), systèmes de fabrication intégrés (IMS), productique (CIM)
• G21D 3/00 - Commande des installations à énergie nucléaire
• F16K 31/04 - Moyens de fonctionnement; Dispositifs de retour à la position de repos magnétiques utilisant un moteur
• H01F 7/18 - Circuits en vue d'obtenir des caractéristiques de fonctionnement souhaitées, p.ex. pour un fonctionnement lent, pour l'excitation successive des enroulements, pour l'excitation à grande vitesse des enroulements
• H02P 1/04 - Moyens de commande de la progression d'une séquence de démarrage en fonction du temps ou en fonction du courant, de la vitesse ou d'un autre paramètre du moteur

Abrégé

The present invention relates to a transport basket for defective spent nuclear fuel of a heavy water reactor and, more particularly, to a transport basket for defective spent nuclear fuel of a heavy water reactor that can reduce the burden of a personnel when handling spent nuclear fuel in a test facility by minimizing a storage space and maximizing a thickness such that only a predetermined amount of spent nuclear fuel for soundness evaluation in the test facility can be transported. To this end, provided is a transport basket for defective spent nuclear fuel of a heavy water reactor, comprising: a basket body having a storage space and an internal support that partitions the storage space; a fuel pocket that is installed on one side of each storage space partitioned through the internal support and is installed so as to be rotatable toward the other side of the storage space, and has a detachable groove open in an upward direction such that a fuel case containing the spent nuclear fuel can be detached therefrom; and a cover that opens and closes the storage space of the basket body and is screwed to the basket body.

Classes IPC  ?

• G21F 5/012 - Râteliers pour éléments combustibles dans le récipient
• G21F 5/12 - Dispositifs obturateurs pour récipients; Dispositions pour leur étanchéité
• G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p.ex. dispositifs de transport

Abrégé

Proposed is a cutting apparatus for a fuel basket accommodating spent nuclear fuel of a heavy water reactor, wherein the apparatus includes a base, a vertical support arranged on one side of the base; a turn table arranged to be reciprocated between one side and an opposite side of the base and be horizontally rotatable on the base; a horizontal support arranged to extend from an upper-end of the vertical support in a horizontal direction toward the turn table; a side-cutting means arranged on the vertical support protruding toward the turn table for cutting a side welding bead of the fuel basket mounted on the turn table; and an upper-cutting means arranged on the horizontal support protruding toward the turn table for cutting an upper welding bead of the fuel basket mounted on the turn table.

Classes IPC  ?

• B23C 1/14 - Machines à fraiser non conçues pour des pièces particulières ou des opérations spéciales avec une table porte-pièce rotative
• G21F 5/008 - Récipients pour éléments combustibles

Abrégé

A nuclear power plant virtualization system and an operating method therefor are provided. The nuclear power plant virtualization system comprises: virtual machine control parts; virtual machine network parts linked to the virtual machine control parts; and a virtualization platform switch linked to the virtual machine control parts and the virtual machine network parts, wherein the virtual machine control parts include a first MMI linkage driver module, the virtual machine network parts include a second MMI linkage driver module, and the virtual machine control parts and the virtual machine network parts modify, by means of the first MMI linkage driver module and the second MMI linkage driver module, an IP/MAC address in data communicating with the outside, so that the data communicating with the outside in the virtual machine control parts passes through the virtual machine network parts.

Classes IPC  ?

• G06F 9/455 - Dispositions pour exécuter des programmes spécifiques Émulation; Interprétation; Simulation de logiciel, p.ex. virtualisation ou émulation des moteurs d’exécution d’applications ou de systèmes d’exploitation
• G21D 3/00 - Commande des installations à énergie nucléaire
• H04L 45/76 - Routage dans des topologies définies par logiciel, p.ex. l’acheminement entre des machines virtuelles
• H04L 49/60 - Commutateurs définis sous forme de logiciel
• H04L 45/74 - Traitement d'adresse pour le routage
• H04L 41/122 - Découverte ou gestion des topologies de réseau des topologies virtualisées, p.ex. les réseaux définis par logiciel [SDN] ou la virtualisation de la fonction réseau [NFV]
• H04L 12/46 - Interconnexion de réseaux

Abrégé

The objective of the present invention is to provide a construction simulation system for nuclear power plant equipment, the system comprising: an information input unit into which nuclear power plant equipment installation information related to nuclear power plant equipment is inputted; a simulation implementation unit for generating a virtual reality simulation related to the nuclear power plant equipment on the basis of the nuclear power plant equipment installation information, and allowing the virtual reality simulation to be outputted through a nuclear power plant equipment installation simulation program; and a utilization unit for outputting the virtual reality simulation.

Classes IPC  ?

• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu
• G06Q 50/26 - Services gouvernementaux ou services publics

Abrégé

The present invention relates to a device for tracking the basis of an abnormal state determination by using a neural network model, comprising: an abnormality type classification unit for classifying an abnormal state into a plurality of failures in an abnormal operation scenario in which a plurality of scenarios related to the abnormal state are stored; an operation variable deriving unit for deriving operation variables affecting an abnormal state determination result for each of the plurality of classified failures; a power plant operation variable weighting unit for weighting the variable related to the abnormal state from among the operation variables; and an abnormal state determination basis generation unit for tracking the basis of an abnormal state determination from the abnormal state determination result generated through the weighted power plant operation variable.

Classes IPC  ?

• G06N 3/08 - Méthodes d'apprentissage

Abrégé

The present invention provides a method of operating a nuclear power plant, considering a fatigue state of a small modular nuclear reactor, the nuclear power plant including a plurality of small modular nuclear reactors, the method comprising: a monitoring step of monitoring a fatigue state of each of the small modular nuclear reactors; an analyzing step of, when a problematic small modular nuclear reactor, the fatigue state of which has been determined to be a predetermined level or more, is identified, analyzing whether the problematic small modular nuclear reactor is operable by considering the driving state of the problematic small modular nuclear reactor; a diagnosing step of diagnosing cumulative fatigue states of the remaining small modular nuclear reactors when the problematic small modular nuclear reactor has been determined to be inoperable; and a flexible operation step of adjusting outputs of the remaining small modular nuclear reactors on the basis of the accumulative fatigue state derived in the diagnosing step.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire
• G21C 1/32 - Réacteurs du type intégré, c. à d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p.ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur

Abrégé

The present invention relates to an apparatus for manufacturing petroleum coke slurry, comprising: a hopper part which includes a center hole at the upper portion thereof and has, at one side of the upper portion thereof, a first input hole into which water, coke and a surfactant are to be put and a second input hole into which slurry produced while agitation is performed is put, which includes, at the lower portion thereof, air supply holes for supplying air and a discharge hole through which objects to be agitated are discharged, and which is formed of a hopper having a cylindrical body and a portion below the body, of which the width narrows; an agitation part including an agitator motor positioned at the outer upper end of the hopper part so as to generate power for the operation of an agitator, a first rotary shaft having one side connected to the agitator motor in order to transmit the power generated by the agitator motor while passing through the center hole of the hopper part, a second rotary shaft orthogonally connected to the other side of the first rotary shaft, and agitation blades provided in the longitudinal direction of the second rotary shaft; a re-supply part including a first connection pipe, which is positioned outside the hopper so as to be connected between the discharge hole and the second input hole, and a circulation pump, which is positioned in the middle of the first connection pipe in order to re-supply, into the hopper through the second input hole, the objects to be agitated, discharged from the discharge hole; and a rail part positioned inside the hopper so as to be provided in a shape of encompassing the hopper along the inner wall surface thereof.

Classes IPC  ?

• B01F 27/90 - Mélangeurs à agitateurs tournant dans des récipients fixes; Pétrins avec des agitateurs tournant autour d'un axe sensiblement vertical avec des palettes ou des bras
• C10L 1/32 - Combustibles carbonés liquides consistant en suspensions charbon-huile ou émulsions aqueuses
• B01F 27/70 - Mélangeurs à agitateurs tournant dans des récipients fixes; Pétrins avec des agitateurs tournant autour d'un axe horizontal ou incliné avec des palettes, des lames ou des bras
• B01F 35/32 - Dispositions d’entraînement
• B01F 35/71 - Mécanismes d'alimentation
• B01F 25/50 - Mélangeurs de circulation, p.ex. dans lesquels au moins une partie du mélange est évacuée d'un récipient et réintroduite dans celui-ci
• B01F 23/23 - Mélange de gaz avec des liquides en introduisant des gaz dans des milieux liquides, p.ex. pour produire des liquides aérés
• B01F 35/21 - Mesure
• B01F 35/214 - Mesure caractérisée par les moyens pour mesurer

Abrégé

The present invention relates to a system and method for monitoring the aging state of a power cable, in which a measuring unit measures the elongation at break of at least one power cable, a data generation unit generates a relational expression on the basis of the elongation at break of each of a heated cable, to which voltage has been applied to raise the temperature thereof, and a non-heated cable, to which no voltage has been applied, from among the measured cables, and an aging state derivation unit derives the aging state of a target power cable by calculating the elongation at break of the target power cable, of which the aging state is to be monitored, by using the relational expression. Accordingly, it is possible to verify the aging state of a power cable quickly and efficiently and to improve the credibility of the aging state of the power cable.

Classes IPC  ?

• G01R 31/08 - Localisation de défauts dans les câbles, les lignes de transmission ou les réseaux
• H05B 3/56 - Câbles chauffants

Abrégé

A vitrification equipment starting method and starting unit are provided. The vitrification equipment starting method comprises the steps of: preparing an ignition module; putting the ignition module into a low-temperature melting furnace chamber; and linking the ignition module to a high-frequency heating means outside of a low-temperature melting furnace, thereby performing an ignition operation inside the low-temperature melting furnace chamber, wherein the ignition module is put into the low-temperature melting furnace chamber in an initial state in which the shape thereof has yet to be changed, and enters a deformed state in which the shape thereof is changed from that of the initial state when put into the low-temperature melting furnace chamber, and thus the ignition operation is performed.

Classes IPC  ?

• G21F 9/30 - Traitements
• C03B 5/00 - Fusion dans des fours; Fours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre

Abrégé

A water level measurement system according to an embodiment of the present invention includes a support pipe installed in a water tank filled with a fluid to measure a water level and extending in a depth direction of the water tank, a support rod disposed in an inner space of the support pipe and extending in the depth direction of the water tank, a plurality of ultrasonic probes attached to the support rod and generating ultrasonic waves, and a water level calculator connected to the plurality of ultrasonic probes and calculating the water level in the water tank, wherein the water level calculator calculates the water level of the water tank by using an order of the ultrasonic probes disposed at a highest position among the plurality of ultrasonic probes that detect a signal of a reflected wave reflected from the support pipe.

Classes IPC  ?

• G01F 23/296 - Ondes acoustiques
• G01D 11/30 - Supports spécialement adaptés à un instrument; Supports spécialement adaptés à un ensemble d'instruments
• G21C 19/07 - Râteliers de stockage; Piscines de stockage

Abrégé

A water level measurement system according to an embodiment includes a support pipe installed in a water tank filled with a fluid to measure a water level and extending in a depth direction of the water tank, a support rod disposed on one side of the support pipe based on a central axis of the support pipe and extending in the depth direction of the water tank, a plurality of ultrasonic probes attached to the support rod and generating ultrasonic waves, and a water level calculator connected to the plurality of ultrasonic probes and calculating the water level of the water tank.

Classes IPC  ?

• G01F 23/296 - Ondes acoustiques

Abrégé

A method of forming single crystal perovskite according to an exemplary embodiment of the present invention includes: forming a preliminary thin film by applying a perovskite precursor solution containing an additive on a substrate; exposing the preliminary thin film to a vacuum state by transferring the preliminary thin film to a vacuum chamber; and switching an internal pressure of the vacuum chamber to an atmospheric pressure, wherein the additive includes a substituted or unsubstituted C1 to C30 aliphatic ammonium salt, a substituted or unsubstituted C6 to C30 aromatic ammonium salt, a substituted or unsubstituted C1 to C30 aliphatic amine salt, a substituted or unsubstituted C6 to C30 aromatic amine salt, or a combination thereof.

Classes IPC  ?

• C30B 29/22 - Oxydes complexes
• C30B 19/10 - Commande ou régulation

Abrégé

A flow rate formation method for system decontamination of a heavy-water reactor nuclear power plant is provided. A nuclear power plant includes: a reactor; a first coolant pump disposed on one side of the reactor, a second coolant pump disposed on the other side of the reactor, and first coolant system piping passing through the reactor and connecting the first coolant pump and the second coolant pump; a first shutdown cooling pump disposed on one side of the reactor, and first shutdown cooling system piping branching from the first coolant system piping at a downstream end of the first coolant pump and connected to an upstream end of the first coolant pump through the first shutdown cooling pump; and a second shutdown cooling pump disposed on the other side of the reactor, and second shutdown cooling system piping branching from the first coolant system piping at a downstream end of the second coolant pump and connected to an upstream end of the second coolant pump through the second shutdown cooling pump, wherein the first coolant system piping, the first shutdown cooling system piping, and the second shutdown cooling system piping are decontaminated simultaneously by operating the first coolant pump and the second shutdown cooling pump and stopping the second coolant pump and the first shutdown cooling pump.

Classes IPC  ?

• G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination
• G21F 9/06 - Traitements

Abrégé

The present invention relates to a method for dealing with a loss of coolant accident in a nuclear power plant, and a system therefor. The method for dealing with a loss of coolant accident in a nuclear power plant, according to the present invention, comprises the steps of: determining a fracture size and a fracture position; determining an accident level on the basis of the determined fracture size and fracture position; and activating safeguards according to the accident level.

Classes IPC  ?

• G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur
• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation

Abrégé

The present invention relates to a method for dealing with anticipated transient without scram in a nuclear power plant, and a system therefor. The method for dealing with anticipated transient without scream in a nuclear power plant, according to the present invention, comprises the steps of: identifying the pressure of a pressurizer; determining an accident level on the basis of the determined pressure of the pressurizer; and activating safeguards related to the pressure, according to the accident level.

Classes IPC  ?

• G21C 9/004 - Suppression de la pression
• G21C 9/02 - Moyens pour effectuer une réduction très rapide du facteur de réactivité dans des conditions défectueuses, p.ex. fusible pour réacteur
• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation

Abrégé

Provided is a flow rate generation method for the decontamination of a heavy water nuclear power plant system. The nuclear power plant comprises: a nuclear reactor; a first coolant pump that is disposed on one side of the nuclear reactor; a second coolant pump that is disposed on the other side of the nuclear reactor; a first coolant system pipe that passes through the reactor and connects the first coolant pump and the second coolant pump; a first stop cooling pump that is disposed on one side of the nuclear reactor; a first stop cooling system pipe that is branched from the first coolant system pipe downstream of the first coolant pump and connected to the first coolant system pipe upstream of the first coolant pump via the first stop cooling pump; a second stop cooling pump disposed on the other side of the nuclear reactor; and a second stop cooling system pipe that is branched from the first coolant system pipe downstream of the second coolant pump and connected to the first coolant system pipe upstream of the second coolant pump via the second stop cooling pump. Here, the first coolant system pipe, the first stop cooling system pipe, and the second stop cooling system pipe are simultaneously decontaminated by running the first coolant pump and the second stop cooling pump and stopping the second coolant pump and the first stop cooling pump.

Classes IPC  ?

• G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination
• G21F 9/06 - Traitements

Abrégé

An artificial intelligence (AI) feedback method includes: providing input1 and input2 to a script extractor and executor, providing, by the script extractor and executor, an initial condition to an AI, generating, by the AI, a two-dimensional (2D) information table from the initial condition, adding the popularity frequency value or ranking value to corresponding coordinates in the 2D information table and matching knowledge by an interaction between the AI and the script extractor and executor, generating, by the AI, a 2D pseudolinear transformation table from the 2D information table, and performing, by the AI, pseudolinear transformation multiple times to form a 2D unique characteristic table and deriving information of coordinates whose characteristic vector is not changed as a deep truth value.

Classes IPC  ?

• G06N 20/00 - Apprentissage automatique

Abrégé

Proposed is a reactor cooling system for cooling down a reactor damaged by a disaster accident and a reactor cooling method using same using contaminated water generated at a nuclear reactor as a cooling water source for cooling the nuclear reactor after the accident, thereby maximally suppressing discharge of the contaminated water into the sea. To this end, the reactor cooling system prosed above includes a nuclear power generation facility, a seawater storage tank, a seawater inflow flow path for introducing the seawater into the seawater storage tank and a seawater discharge flow path for discharging the seawater from the seawater storage tank to the sea, connected to one end and another end of the seawater storage tank, respectively, a heat exchanger installed in a water storage space of the seawater storage tank, a contaminated water supply flow path, and a contaminated water discharge flow path.

Classes IPC  ?

• G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur
• G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides

Abrégé

An artificial intelligence (AI) feedback method includes: providing input 1 and input 2, providing an initial condition for a popularity frequency value or ranking value of information related to input 2 from input 1, generating a two-dimensional (2D) information table from the initial condition, adding the popularity frequency value or ranking value to corresponding coordinates in the 2D information table and matching knowledge, generating a 2D pseudolinear transformation table from the 2D information table, performing pseudolinear transformation multiple times to form a 2D unique characteristic table and deriving information of coordinates whose characteristic vector is not changed as a deep truth value, and organizing and storing a context of knowledge formed by connecting the deep truth value by category.

Classes IPC  ?

• G06N 5/02 - Représentation de la connaissance; Représentation symbolique

Abrégé

A method of dynamic control rod reactivity measurement for a reactor using a fission chamber as an out-of-reactor measuring instrument includes: maintaining the reactor in a critical state having a set output by inserting a reference control bank into a reactor core to a first depth; completely inserting the reference control bank into the reactor core from the first depth at a maximum allowable speed and immediately completely withdrawing the reference control bank from the reactor core at the maximum allowable speed, and measuring a first signal of the out-of-reactor measuring instrument from before the insertion of the reference control bank to after the withdrawal of the reference control bank; and determining static controllability of the reference control bank by adding residual controllability measurement value of the reactor to a first static reactivity of the reactor calculated using the first signal of the out-of-reactor measuring instrument.

Classes IPC  ?

• G21C 17/104 - Mesure de la réactivité

Abrégé

Provided are a cooling device and a cooling method for a small modular reactor. A cooling device for a small modular reactor includes: a nuclear reactor vessel in which cooling water circulates and flows along a fluid channel structure part; and a cooling water retention unit which is provided inside the nuclear reactor vessel and in which the cooling water is filled on the basis of the circulation and flowage, wherein, when a reactor core molten material is generated in the nuclear reactor vessel due to the occurrence of a serious accident, the cooling water retention unit comes into contact, by means of the cooling water filled therein, with the reactor core molten material to cool the reactor core molten material, thereby preventing outflow of the reactor core molten material to the outside.

Classes IPC  ?

• G21C 9/016 - Récupérateurs de cœur
• G21C 1/32 - Réacteurs du type intégré, c. à d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p.ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur

Abrégé

Provided are a small nuclear reactor apparatus and an operation method thereof. The small nuclear reactor apparatus comprises: a body unit that includes a nuclear reactor core therein; and an opening/closing unit that can be attached to or detached from the body unit in order to open and close the inside of the body unit. The opening/closing unit can be attached and detached on the basis of the downward placement inside the body unit, and a plurality of In-core instrument (ICI) modules for measuring the state of the small nuclear reactor are inserted and mounted in the opening/closing unit.

Classes IPC  ?

• G21C 1/32 - Réacteurs du type intégré, c. à d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p.ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
• G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p.ex. pour faciliter le chargement ou le déchargement des éléments combustibles
• G21C 19/34 - Procédés ou appareils de démantèlement du combustible nucléaire, p.ex. avant retraitement

Abrégé

A small nuclear reactor cooling system and cooling method are provided. The small nuclear reactor cooling system comprises a cooling unit in which a small nuclear reactor is positioned, and which performs, in the cooling system, in response to the occurrence of a serious accident of the small nuclear reactor, cooling corresponding to the serious accident, wherein the cooling unit provides a first cooling fluid so as to perform cooling in response to heat caused by the serious accident.

Classes IPC  ?

• G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur
• 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

Abrégé

Proposed is a system for utilizing unused heat-exchange water of a passive auxiliary feedwater system, and a reactor cooling control method utilizing the unused heat-exchange water of the passive auxiliary feedwater system and, more specifically, a system for utilizing unused heat-exchange water of a passive auxiliary feedwater system, and a reactor cooling control method utilizing the unused heat-exchange water of the passive auxiliary feedwater system, which may allow the unused heat exchange water remaining after heat exchange in the passive condensation tank to be used as cooling water, thereby increasing the efficiency of reactor cooling and increasing the efficiency of initial response in an event of a reactor accident. To this end, the proposed system includes a passive condensation tank, a condenser, a steam supply line, and a condensate water recovery line and is characterized by that a residual water discharge flow path is arranged at the inside thereof.

Classes IPC  ?

• 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 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur
• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation

Abrégé

The present invention relates to a method of providing a measure for a plant in an abnormal state by using artificial intelligence, and comprises the steps of: preparing measure data, for a plant in an abnormal state, to be analyzed; analyzing the measure data to be analyzed to identify expected measure information for the abnormal state; identifying a measure for a current operating state on the basis of the expected measure information; and notifying an operator of the measure.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G05B 23/02 - Test ou contrôle électrique
• G06N 3/02 - Réseaux neuronaux

Abrégé

The present invention relates to a small modular reactor including small fuel assemblies. The small modular reactor comprises: a reactor body; and a nuclear fuel material which is accommodated in the reactor body, includes a plurality of fuel assemblies, and has a section arrangement region. The section arrangement region includes a first arrangement region and a plurality of second arrangement regions that are located outside the first arrangement region and spaced apart from each other. The fuel assemblies include: first nuclear fuel assemblies that each have a first size and are closely arranged in the first arrangement region; and second nuclear fuel assemblies that each have a second size smaller than the first size and are arranged in the second arrangement region.

Classes IPC  ?

• G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
• G21C 11/06 - Ecrans réflecteurs, c. à d. pour minimiser la perte de neutrons

Abrégé

The present invention relates to a small modular reactor including small fuel assemblies. The small modular reactor comprises: a reactor body; and a nuclear fuel material which is accommodated in the reactor body, includes a plurality of fuel assemblies, and has a section arrangement region. The section arrangement region includes a first arrangement region and a plurality of second arrangement regions that are located outside the first arrangement region and spaced apart from each other. The fuel assemblies include: first nuclear fuel assemblies that each have a first size and are closely arranged in the first arrangement region; and second nuclear fuel assemblies that each have a second size smaller than the first size and are arranged in the second arrangement region.

Classes IPC  ?

• G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
• G21C 11/06 - Ecrans réflecteurs, c. à d. pour minimiser la perte de neutrons

Abrégé

The present invention relates to a catalyst tower used in the step of removing and recovering certain radioactive substances during a radioactive waste treatment process applied in a nuclear power plant, and in particular to a catalyst tower with a design improvement in the structure thereof, comprising a tower-type outer frame, a support installed at the bottom of the outer frame, a plurality of catalyst packings stacked one after the other on the support, and a disperser disposed at the upper or lower side of the catalyst packings, and being equipped with a pull-out cartridge having the catalyst packings stacked one after the other therein and forming an opening that is in communication with the outside, wherein the pull-out cartridge is drawn out when the catalyst packings are pulled out for the maintenance thereof, such that the plurality of the stacked catalyst packings are pulled out together in a stacked state inside the pull-out cartridge. The objective of the present invention is to provide a replaceable catalyst tower which, by having a structure that enables the replacement process of the catalyst packings to be carried out remotely and quickly, promotes the safety of the operator and further improves the process efficiency in the process of dismantling the catalyst tower and replacing the content thereof.

Classes IPC  ?

• G21F 9/06 - Traitements

Abrégé

Proposed is a passive condensation tank cooling system of a passive auxiliary feedwater system, the cooling system allowing a passive condensation tank to include an inner wall and an outer wall and a cooling means to be interposed between the inner wall and the outer wall, thereby suppressing the increase in the temperature of the heat exchange water in a condensation process in the passive condensation tank. To this end, proposed is the passive condensation tank cooling system of a passive auxiliary feedwater system, the cooling system including: a passive condensation tank having a water storage space to store heat-exchange water; and a condenser arranged to be immersed in the heat-exchange water in the passive condensation tank, wherein the passive condensation tank includes the outer and inner walls providing the water storage space and a cooling means interposed between the walls for absorbing heat of the heat-exchange water.

Classes IPC  ?

• G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur
• G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides

Abrégé

The present invention relates to a nuclear power plant which includes a small modular reactor (SMR), the nuclear power plant comprising a water tank, wherein the water tank comprises: a first water tank filled with cooling water and forming a first space in which spent nuclear fuel is disposed; and a second water tank forming a second space which is separated from the first space and in which the small modular reactor (SMR) is disposed.

Classes IPC  ?

• G21C 15/06 - 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 provenant du matériau fissile ou surrégénérateur dans les éléments combustibles
• G21C 1/32 - Réacteurs du type intégré, c. à d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p.ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur

Abrégé

The present invention relates to a method for analyzing a severe accident at a nuclear power plant by using a modular analysis code, comprising the step of: receiving the input of a nuclear power plant to be analyzed and an accident sequence; selecting, from a modular analysis code, an individual module for analyzing a severe accident that is triggered by the accident sequence; setting an accident simulation variable for simulating the severe accident from a nuclear power plant input model; determining whether the accident simulation variable is valid; and, if determined to be valid, analyzing the severe accident through the modular analysis code by using the accident simulation variable, wherein the individual module of the modular analysis code includes: a master module; a first module for analyzing in-core phenomena in the event of a severe accident; a second module for analyzing ex-core phenomena in the event of a severe accident; and a third module for analyzing behaviors of fission products in the event of a severe accident by using in-core thermal-hydraulic information and ex-core thermal-hydraulic information calculated by the first module and the second module, and information movement among the first module, the second module, and the third module is achieved through the master module.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G21D 3/00 - Commande des installations à énergie nucléaire
• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu

Abrégé

There is provided a method of dismantling a dousing tank of a heavy water reactor structure. The method of dismantling a dousing tank of a heavy water reactor structure includes: selecting a dousing tank of a heavy water reactor structure for dismantlement; dismantling a first structure inside the dousing tank; fixing the dousing tank to a dome structure portion provided above the dousing tank through a mounting port; positioning a cutting unit on a second structure including a concrete structure inside the dousing tank; and performing, by the cutting unit, cutting based on a forward or reverse rotation manner on an inner peripheral surface of the dousing tank.

Classes IPC  ?

• G21D 1/00 - ENSEMBLES DE PRODUCTION D'ÉNERGIE NUCLÉAIRE - Détails des installations à énergie nucléaire
• B28D 1/22 - Travail de la pierre ou des matériaux analogues p.ex. briques, béton, non prévu ailleurs; Machines, dispositifs, outils à cet effet par découpage, p.ex. exécution d'entailles
• G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur

Abrégé

The present invention relates to a systemic decontamination method of a heavy water reactor, the method comprising the steps of: performing decontamination of a moderator system; and performing decontamination of a coolant system after the decontamination of the moderator system, wherein the decontamination of the moderator system is performed by adjusting the temperature of a first system water of the moderator system to a first system water process temperature and sequentially conducting a moderator system oxidation process and a moderator system reduction process.

Classes IPC  ?

• G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination

Abrégé

Provided is a method for removing a dousing tank of a heavy water reactor structure. The method for removing a dousing tank of a heavy water reactor structure comprises: a step in which a dousing tank of a heavy water reactor structure is selected for removal; a step in which a first structure in the dousing tank is removed; a step in which the dousing tank is fixed, using mounting pieces, to a dome structure part provided thereabove; a step in which a cutting unit is positioned on a second structure, comprising a concrete structure, inside the dousing tank; and a step in which the cutting unit performs a cutting process, based on a forward rotation or reverse rotation method, on the inner circumferential surface of the dousing tank.

Classes IPC  ?

• G21D 1/00 - ENSEMBLES DE PRODUCTION D'ÉNERGIE NUCLÉAIRE - Détails des installations à énergie nucléaire
• G21C 15/18 - Dispositions pour le refroidissement d'urgence; Mise hors circuit de la chaleur
• B28D 1/22 - Travail de la pierre ou des matériaux analogues p.ex. briques, béton, non prévu ailleurs; Machines, dispositifs, outils à cet effet par découpage, p.ex. exécution d'entailles

Abrégé

The present invention relates to a systemic decontamination method of a heavy water reactor, the method comprising the steps of: performing decontamination of a moderator system; and performing decontamination of a coolant system after the decontamination of the moderator system, wherein the decontamination of the moderator system is performed by adjusting the temperature of a first system water of the moderator system to a first system water process temperature and sequentially conducting a moderator system oxidation process and a moderator system reduction process.

Classes IPC  ?

• G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination

Abrégé

Provided are a method and apparatus for decommissioning a nuclear power plant. The method for decommissioning a nuclear power plant comprises the steps of: selecting a nuclear reactor to be decommissioned; and performing a nuclear power plant decommissioning operation for the nuclear reactor by means of a nuclear reactor decommissioning apparatus. The nuclear reactor decommissioning apparatus includes: a frame unit which closes the nuclear reactor to prevent pollutants in the nuclear reactor from being discharged to the outside; a cutting module, provided on the frame unit, for performing a cutting operation for the nuclear reactor; a bar-shaped interlocking and fixing module which has a hollow region formed therein, and which enters the inner space of the nuclear reactor and interlocks the frame unit and the nuclear reactor; and a purging module which enters the hollow region of the interlocking and fixing module and purges the inside of the nuclear reactor in order to ensure the safety of the cutting operation.

Classes IPC  ?

• G21D 1/00 - ENSEMBLES DE PRODUCTION D'ÉNERGIE NUCLÉAIRE - Détails des installations à énergie nucléaire
• G21F 1/02 - Sélection de matériaux de blindage uniforme

Abrégé

The present invention comprises a method for dismantling a nuclear power plant, the method comprising the steps of: selecting a nuclear reactor to be dismantled; and performing a nuclear power plant dismantling operation for the nuclear reactor through a nuclear reactor dismantling apparatus, wherein the nuclear reactor dismantling apparatus comprises: a frame unit for preventing external discharge of contaminants from the nuclear reactor by shielding the nuclear reactor; a cutting processing module which is provided on the frame unit and performs a cutting operation on the nuclear reactor; and an extinguishing module which is provided on the frame unit, and is melted by a heat source based on the fire, when a fire occurs in the nuclear reactor, to automatically supply an internal extinguishing fluid to the outside.

Classes IPC  ?

• G21D 1/00 - ENSEMBLES DE PRODUCTION D'ÉNERGIE NUCLÉAIRE - Détails des installations à énergie nucléaire
• G21C 9/04 - Moyens pour combattre les incendies
• A62C 35/10 - Réservoirs se brisant ou s'ouvrant sous l'action des flammes ou de la chaleur

Abrégé

A remote restart system of a vitrification facility and a method for operating same are provided. The method for operating the remote restart system of the vitrification facility comprises: a step in which the vitrification facility is operated; and a step in which power loss with respect to the vitrification facility occurs. The power loss occurs during or before the operation of the vitrification facility, and the remote restart system assists in restarting the vitrification facility when the power loss occurs in the vitrification facility, wherein the remote restart system includes: a low-temperature melting furnace; a glass frit provided inside the low-temperature melting furnace; a titanium ring for heating the glass frit inside the low-temperature melting furnace; and a bar-shaped handling unit introduced into the low-temperature melting furnace to handle the glass frit so that the glass frit is in a state suitable for re-ignition thereof.

Classes IPC  ?

• G21F 9/30 - Traitements
• C03C 8/02 - Compositions en verre fritté, c. à d. broyées ou sous forme de poudre

Abrégé

A method for treating radioactive waste glass fibers is provided. The method for treating radioactive waste glass fibers comprises the steps in which: radioactive waste glass fibers are prepared; the radioactive waste glass fibers are loaded into a canister; the canister is heat-treated under a set condition by means of a heat-treatment unit; and the radioactive waste glass fibers are transferred with reduced volume through the heat-treatment.

Classes IPC  ?

• G21F 9/30 - Traitements
• G21F 5/005 - Récipients pour déchets radioactifs solides, p.ex. pour le stockage final
• G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p.ex. utilisant une circulation de fluide ou des ailettes de refroidissement

Abrégé

A device for imaging radiation source in a decommissioning area of a nuclear power plant includes a detecting unit including a plurality of pixels for detecting an X-ray spectrum generated from a decommissioning area of a nuclear power plant, a processing unit connected to the detecting unit and configured to analyze the X-ray spectrum detected from the plurality of pixels and fuse a first element image displaying first pixels from which a first characteristic X-ray energy of a first element, among the plurality of pixels, is detected and a second element image displaying second pixels from which a second characteristic X-ray energy of a second element, among the plurality of pixels, is detected, into a fused image, and a display unit connected to the processing unit and configured to display the fused image corresponding to the decommissioning area.

Classes IPC  ?

• G01T 1/16 - Mesure de l'intensité de radiation
• G01T 1/29 - Mesure effectuée sur des faisceaux de radiations, p.ex. sur la position ou la section du faisceau; Mesure de la distribution spatiale de radiations

Abrégé

An exposure dose measurement simulation device according to an embodiment of the present invention includes: a virtual work area generating portion that generates a virtual work area corresponding to a work area of a radiation facility; and an exposure dose prediction portion that predicts an exposure dose of a worker positioned in the virtual work area, wherein the exposure dose prediction portion includes a database portion that includes first data on a spatial dose rate of the radiation facility and second data on a position of a radiation source in the radiation facility, and a first exposure dose calculation portion that calculates the exposure dose of the worker positioned in the virtual work area using the first data and second data.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire
• G21D 3/04 - Dispositions de sécurité
• G06Q 10/04 - Prévision ou optimisation spécialement adaptées à des fins administratives ou de gestion, p. ex. programmation linéaire ou "problème d’optimisation des stocks"

Abrégé

The present invention comprises the steps of: (a) classifying bottom ash powder, which is a by-product of thermal power generation, according to particle size and collecting same; (b) preparing a cement mortar composition or concrete composition including the collected bottom ash powder in an unwashed state; and (c) forming a plain concrete structure using the cement mortar composition or the concrete composition.

Classes IPC  ?

• C04B 18/06 - Résidus de combustion, p.ex. produits d'épuration des fumées, des émanations ou des gaz d'échappement
• C04B 20/00 - Emploi de matières comme charges pour mortiers, béton ou pierre artificielle prévu dans plus d'un groupe et caractérisées par la forme ou la répartition des grains; Traitement de matières spécialement adapté pour renforcer leur propriétés de charge dans les mortiers, béton ou pierre artificielle prévu dans plus d'un groupe de ; Matières expansées ou défibrillées
• C04B 40/02 - Choix de l'environnement pour le durcissement
• C04B 28/02 - Compositions pour mortiers, béton ou pierre artificielle, contenant des liants inorganiques ou contenant le produit de réaction d'un liant inorganique et d'un liant organique, p.ex. contenant des ciments de polycarboxylates contenant des ciments hydrauliques autres que ceux de sulfate de calcium
• B28B 11/24 - Appareillages ou procédés pour le traitement ou le travail des objets façonnés pour faire prendre ou durcir

Abrégé

The present invention relates to a swastika-shaped artificial reef using industrial by-products, the swastika-shaped artificial reef comprising: a pillar member having a preset height; first, second, and third protruding members respectively protruding from the upper end, the lower end, and the middle portion between the upper and lower ends of the pillar member to be connected in four directions including front and back and left and right directions; first, second, and third extension members extending respectively from front ends of the first, second, and third protruding members to be connected to one side; and first and second support members which are connected between the first and second extension members facing each other from upper and lower directions, and connected perpendicularly to the second and third extension members.

Classes IPC  ?

• A01K 61/73 - Berges ou récifs artificiels pour la pêche assemblés à partir de composants
• A01K 61/78 - Leurs agencements de mise sous eau ou d’ancrage
• E02B 3/04 - Ouvrages, appareils ou procédés pour la protection des berges, des côtes ou des ports

Abrégé

A method and a system for monitoring a state of a nuclear power plant capable of reducing a state prediction error of a sensor during startup, full power, shut down operation of a nuclear power plant, and of providing an early warning, without an error alarm includes remotely and automatically diagnosing the state of a sensor, device, system and power plant. The method and comprises: a first layer that compares a sensor measurement value and a device measurement value with predicted values so as to detect anomalies of the sensor and the device; a second layer that classifies a type of the sensor and diagnoses the presence or absence of an anomaly of the sensor on the basis of an anomaly value of the sensor provided from the first layer.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité

Abrégé

A radioactive isotope production method using a light-water reactor type nuclear reactor is provided. The radioactive isotope production method using a light-water reactor type nuclear reactor comprises the steps of: preparing a nuclear fuel rod; preparing a nuclear fuel bundle on the basis of the nuclear fuel rod; providing the nuclear fuel bundle in a light-water reactor; and operating the light-water reactor for radioactive isotope production, wherein the nuclear fuel rod includes a body part in which an inner space is formed in the longitudinal direction, and a target material provided inside the body part, and the target material can be provided to be stacked inside the body part.

Classes IPC  ?

• G21G 1/00 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs
• G21G 1/02 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p.ex. production d'isotopes radioactifs dans les réacteurs nucléaires
• G21C 3/334 - Assemblage des faisceaux
• G21C 1/04 - Réacteurs thermiques

Abrégé

A device for measuring large-area radioactive surface contamination can simultaneously obtain a plurality of detection values. The measurement device includes a frame body having a plurality of holes; a mover that is connected to, and moves, the frame body; and a plurality of radiation detectors that rest in the plurality of holes. The detectors detect one or more of: alpha rays, beta rays, or gamma rays. The location and level of radioactive contamination are accurately identified according to a comparison of the detection values of the plurality of radiation detectors.

Classes IPC  ?

• G01T 1/169 - Exploration, localisation de surfaces contaminées
• G01T 1/167 - Mesure du contenu radioactif des objets, p.ex. contamination
• G01T 7/08 - Moyens pour transporter les échantillons reçus

Abrégé

An artificial intelligence feedback system is provided. An artificial intelligence feedback system may comprise: a script extractor and launcher which receives input 1 including a basic material for learning and input 2 including a key content for learning, and generates an initial condition for a popularity frequency value or a rank value of information related to input 2 from input 1; an artificial intelligence which is connected to the script extractor and launcher, generates a two-dimensional information table in the form of a matrix in which key words and key information based on the popularity frequency value or the rank value derived from the initial condition are configured as both axes respectively, adds the popularity frequency value or the rank value to corresponding coordinates of the two-dimensional information table, and matches knowledge acquired by the artificial intelligence to the corresponding coordinates; an output unit which is connected to the artificial intelligence and outputs deep truth values derived by the artificial intelligence from the two-dimensional information table; and a storage connected to the artificial intelligence, in which the context of knowledge formed by connecting the deep truth values derived by the artificial intelligence is organized and stored by category.

Classes IPC  ?

• G06N 20/00 - Apprentissage automatique
• G06N 5/02 - Représentation de la connaissance; Représentation symbolique

Abrégé

The present invention relates to a high-wave wave dissipation block having improved constructability, the high-wave wave dissipation block comprising: a main body formed in a rectangular parallelepiped shape; a protrusion portion which protrudes from each of the vertical surfaces of the main body while forming a trapezoidal cross-section; a leg portion which is extended from the end portion of the protrusion in the lengthwise direction and is arranged radially on the basis of the main body; and a first chamfered portion which protrudes from each end portion of the leg portion and includes a pair of inclined surfaces that face each other and are vertically symmetrical with each other with respect to the horizontal center axis of the leg portion, wherein the leg portion has upper and lower surfaces which include inclined surfaces that are inclined toward the end portion of the leg portion.

Classes IPC  ?

• E02B 3/14 - Blocs préfabriqués; Disposition de ces blocs
• E02B 3/12 - Revêtement de berges, barrages, lits de cours d'eau ou analogues
• E02B 3/06 - Môles; Jetées; Quais; Murs de quai; Epis; Brise-lames

Abrégé

A method for determining heat and reflected heat in a thermal image, according to the present invention, comprises the steps of: a) photographing a subject through a thermal imaging camera so as to collect a thermal image of the subject; b) analyzing features according to the thermal image temperature distribution of the thermal image; c) detecting the heat and reflected heat in the thermal image according to the analysis in step b); and d) displaying, as heat and reflected heat regions in the thermal image, the heat and reflected heat in the thermal image detected in step c).

Classes IPC  ?

• G06T 7/00 - Analyse d'image
• G06T 7/11 - Découpage basé sur les zones
• G06K 9/62 - Méthodes ou dispositions pour la reconnaissance utilisant des moyens électroniques
• G06N 3/08 - Méthodes d'apprentissage

Abrégé

Disclosed are a high-voltage direct current (HVDC) cable partial discharge diagnosis system and method. The HVDC cable partial discharge diagnosis system according to one aspect of the present invention comprises: a sensor provided on an HVDC cable; a plurality of HVDC cable partial discharge measurement devices for acquiring measurement result information from the sensor and detecting a partial discharge signal from the measurement result information; and an HVDC cable partial discharge diagnosis device which receives the partial discharge signal from the HVDC cable partial discharge measurement devices and diagnoses whether partial discharge has occurred in the HVDC cable, through pattern analysis of the partial discharge signal.

Classes IPC  ?

• G01R 31/12 - Test de la rigidité diélectrique ou de la tension disruptive
• G01R 31/14 - Circuits à cet effet
• G01R 23/16 - Analyse de spectre; Analyse de Fourier
• G01R 23/00 - Dispositions pour procéder aux mesures de fréquences; Dispositions pour procéder à l'analyse de spectres de fréquences

Abrégé

A vibration measurement error determination method according to an embodiment of the present invention comprises: a vibration data acquisition step for acquiring vibration data by measuring a vibration generated in a structure; a first determination step for determining, on the basis of a preset error data selection rule, whether the vibration data is data generated by a measurement error; a second determination step for using a machine-learning algorithm to determine whether the vibration data is data generated by a measurement error; and a final determination step for determining, on the basis of the results determined in the first determination step and the second determination step, whether the vibration data is data generated by a measurement error.

Classes IPC  ?

• G05B 23/02 - Test ou contrôle électrique
• G06N 20/00 - Apprentissage automatique
• G01H 1/08 - Amplitude
• G06K 9/62 - Méthodes ou dispositions pour la reconnaissance utilisant des moyens électroniques

Abrégé

The present invention is to provide a pipe evaluation robot and a pipe evaluation method, in which a robot may be injected into a pipe to generate a reverberation sound and to determine soundness of the pipe on the basis of the reverberation sound, wherein the pipe evaluation robot comprises: a body injected into a pipe; a transfer module which transfers the body inside the pipe; a striking unit provided in the body to strike the pipe; a plurality of acoustic measurement modules provided in the body to measure a striking sound generated when the striking unit strikes the pipe; and a reverberation sound analysis module which converts striking sound information provided through the acoustic measurement modules into analysis data and applies the converted analysis data to a convolutional neural network (CNN) to determine soundness of the pipe.

Classes IPC  ?

• B25J 9/16 - Commandes à programme
• B25J 11/00 - Manipulateurs non prévus ailleurs
• B25J 5/00 - Manipulateurs montés sur roues ou sur support mobile
• G21C 17/017 - Inspection ou maintenance de tuyaux ou de tubes dans des installations nucléaires
• G06Q 50/06 - Fourniture d'électricité, de gaz ou d'eau
• G01H 1/06 - Fréquence

Abrégé

Provided is a UV reaction apparatus for treating a waste liquid caused by system decontamination in a nuclear power plant. The UV reaction apparatus comprises: a UV irradiation part which irradiates UV light as a bar shape; and a passing-through part in which the UV irradiation part is accommodated, and which allows an organic waste liquid to pass through to be irradiated to the UV light, wherein the passing-through part may include: an input part into which the organic waste liquid is inputted; a discharge part through which the organic waste liquid is discharged; and an intermediate part which is positioned between the input part and the discharge part and in which the UV irradiation part is located.

Classes IPC  ?

• G21F 9/06 - Traitements
• C02F 1/32 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par irradiation par la lumière ultraviolette

Abrégé

Provided is a device for monitoring degradation of a wastewater from nuclear power plant decontamination. The device for degrading a wastewater from nuclear power plant decontamination may comprise: a UV reactor tank which is connected to a first channel and is for UV-treating a wastewater being input; a wastewater degradation channel for supplying the wastewater, which is discharged from the UV reactor tank, to the first channel; a wastewater degradation detection unit for detecting whether or not a setting condition is satisfied, by analyzing the components of the wastewater being supplied from the wastewater degradation channel; and a purification channel for purifying the wastewater, which is supplied from the UV reactor tank, and supplying same to the first channel, if the setting condition is satisfied.

Classes IPC  ?

• G21F 9/06 - Traitements
• G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination

Abrégé

A plasma torch has a torch body provided with a plurality of stacked torch body segments disposed between a rear electrode unit and a front electrode unit. The torch body forms a circular channel through which gas flows in an axial direction. Each torch body segment has a circular disc shape in which a central circular through-hole is formed to form the channel. Each segment includes gas supply ports defining a spiral-shaped flow path along the through hole on a first side of the segment so as to introduce a reactive gas, a cooling flow path, a cooling water supply flow path, a cooling water discharge flow path, a gas supply flow path, a gas branch flow path, a cooling water supply branch flow path, and a cooling water discharge branch flow path.

Classes IPC  ?

• H05H 1/28 - Dispositions pour le refroidissement

Abrégé

An electric car charging apparatus using a pad-mounted transformer according to one embodiment of the present invention may include a first port configured to supply power to an electric car, a second port electrically connected to the first port and configured to receive power from a pad-mounted transformer, and a breaking unit configured to switch between connection and disconnection of the first port and the second port.

Classes IPC  ?

• H02J 7/00 - Circuits pour la charge ou la dépolarisation des batteries ou pour alimenter des charges par des batteries
• B60L 53/62 - Surveillance et commande des stations de charge en réponse à des paramètres de charge, p.ex. courant, tension ou charge électrique
• B60L 53/66 - Transfert de données entre les stations de charge et le véhicule
• H02J 7/14 - Circuits pour la charge ou la dépolarisation des batteries ou pour alimenter des charges par des batteries pour la charge de batteries par des générateurs dynamo-électriques entraînés à vitesse variable, p.ex. sur véhicule

Abrégé

A system for charging an electric vehicle according to an exemplary embodiment of the present disclosure may include a transformer connected to a distribution line, a converter converting power converted by the transformer into charging power and a charging apparatus separated from the converter and installed on a utility pole to receive the charging power from the converter and supply the charging power to the electric vehicle.

Classes IPC  ?

• B60L 53/31 - Colonnes de charge spécialement adaptées aux véhicules électriques
• B60L 53/18 - Câbles spécialement adaptés pour recharger des véhicules électriques
• H02J 7/00 - Circuits pour la charge ou la dépolarisation des batteries ou pour alimenter des charges par des batteries

Abrégé

Facilities for waste liquid treatment according to an embodiment of the present invention comprise: a filter connected to a system of a nuclear power plant; a demineralizer connected to the filter; a reactor connected to the demineralizer and including a first lamp and a second lamp which have wavelengths different from each other and are connected in series; a buffer tank connected with the filter, the demineralizer, and the reactor; and a circulation pipe which connects the filter, the demineralizer, the reactor, and the buffer tank to each other to form a circulation structure for a solution together with the system, wherein the solution sequentially passes through the first lamp and the second lamp.

Classes IPC  ?

• G21F 9/06 - Traitements
• C02F 1/32 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par irradiation par la lumière ultraviolette
• C02F 1/66 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par neutralisation; Ajustage du pH
• C02F 1/72 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par oxydation
• B01D 35/02 - Filtres adaptés à des endroits particuliers, p.ex. conduites, pompes, robinets
• C02F 1/42 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par échange d'ions
• C02F 1/70 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par réduction
• G21D 1/00 - ENSEMBLES DE PRODUCTION D'ÉNERGIE NUCLÉAIRE - Détails des installations à énergie nucléaire
• G21F 9/00 - Traitement des matériaux contaminés par la radioactivité; Dispositions à cet effet pour la décontamination