Abrégé

Disclosed is a reactor vessel surveillance capsule assembly. Such reactor vessel surveillance capsule assembly is a surveillance capsule assembly which is formed so as to be capable of receiving a specimen therein in a state of corresponding to a core region side in a reactor vessel, and comprises: side receiving portions disposed on respective side portions facing each other in the receiving vessel, with the core region interposed therebetween; and a lower receiving portion disposed on the lower side in the reactor vessel in a state of connecting the lower sides of the side receiving portions to each other.

Classes IPC  ?

• G21C 17/01 - Inspection des surfaces internes des enceintes
• 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
• G01N 1/02 - Dispositifs pour prélever des échantillons
• G01N 24/00 - Recherche ou analyse des matériaux par l'utilisation de la résonance magnétique nucléaire, de la résonance paramagnétique électronique ou d'autres effets de spin
• G01N 25/00 - Recherche ou analyse des matériaux par l'utilisation de moyens thermiques

Abrégé

The present invention provides a method for controlling the reactivity of a boric acid-free reactor in a secondary system of a pressurized light-water reactor, wherein: a turbine and a main water feeding system of a pressurized light-water reactor comprise a steam generator (S/G), a high-pressure turbine, a low-pressure turbine, a high-pressure feedwater heater, and a low-pressure feedwater heater; the high pressure turbine is provided with extracted steam ① and ② capable of heating feedwater, the low pressure turbine is provided with extracted steam ③ and ④ capable of heating feedwater, the high-pressure feedwater heater is provided with high pressure heaters ① and ② for receiving extracted steam from the turbines to heat feedwater, and a low-pressure feedwater heater is provided with low pressure heaters ③ and ④ for receiving extracted steam from the turbines to heat feedwater; and when operated with constant reactivity and temperature set as default values, the high-pressure heater ① receives extracted steam ② of the high-pressure turbine to heat feedwater, the high-pressure heater ② receives extracted steam ① of the high-pressure turbine to heat feedwater, the low-pressure heater ③ receives extracted steam ④ of the low-pressure turbine to heat feedwater, and the low-pressure heater ④ receives extracted steam from the low-pressure turbine ③ to heat feedwater.

Classes IPC  ?

• G21D 3/16 - Régulation de différents paramètres dans l'installation par ajustement du réacteur en réponse uniquement aux changements se produisant dans la demande du moteur en variant la réactivité
• G21D 5/14 - Agent de travail liquide vaporisé par le réfrigérant du réacteur et aussi surchauffé par le réfrigérant du réacteur

Abrégé

A coast-down apparatus for a reactor coolant pump (RCP) of a small modular nuclear reactor of the present invention comprises: a solenoid valve; a rotor including an impulse blade and installed on a rotary shaft; and an energy storage unit for rotation-driving the impulse blade, wherein: the rotary shaft of a nuclear reactor coolant pump (RCP) is provided with a rotation detection unit for detecting whether to rotate; the rotor installed on the rotary shaft is provided with a motor, an impeller, and the impulse blade for receiving energy from the energy storage unit to rotate; when power of the nuclear reactor coolant pump (RCP) is lost, the solenoid valve performs a fail-open operation; a power supply unit supplies, when power is not supplied to the reactor coolant pump (RCP), power to each of the motor and the solenoid valve through a power supply line, and when the solenoid valve is opened, receives energy for rotating the impulse blade of the reactor coolant pump (RCP) from the energy storage unit through an energy supply pipe and a nozzle.

Classes IPC  ?

• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
• G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
• 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 system and a method for removing residual heat of an integrated nuclear reactor, capable of removing residual heat of the integrated nuclear reactor by constantly maintaining a water level of an ultimate heat sink tank (hereinafter, referred to as an "UHS tank") to be passive without external power even in case that water of the UHS tank is completely depleted when an accident exceeding a design standard of the integrated nuclear reactor occurs.

Classes IPC  ?

• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
• 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 nuclear power plant with improved steam explosion mitigation performance, the nuclear power plant comprising: an integrated reactor including a hemispherical first portion inside which a core and a steam generator are positioned and a cylindrical second portion positioned above the first portion; a containment vessel for accommodating the integrated reactor, having a cooling space surrounding the integrated reactor, and including a first containment portion facing the first portion and a second containment portion facing the second portion; and a lower structure which is located in the cooling space and is located under the integrated reactor, wherein the lower structure comprises a first plate and a second plate disposed below the first plate, and the first plate and the second plate are arranged in a horizontal direction and face each other.

Classes IPC  ?

• G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
• 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 testing a protection system for multiple nuclear reactors using a bypass channel. The multiple nuclear reactors include a first nuclear reactor and a second nuclear reactor. The protection system receives state signals of each of the nuclear reactors and determines whether the nuclear reactors have stopped or an operation system device of an engineering safety facility is in operation. Each of the first reactor and the second reactor includes a first operation channel, a second operation channel, and a bypass channel. Each of the operation channels and the bypass channel includes a bistable processor and a coincidence processor. The method includes the steps of: testing the first operation channel while bypassing the first operation channel; and operating using the bypass channel during the test of the first operation channel.

Classes IPC  ?

• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation
• G05B 9/03 - Dispositions de sécurité électriques avec une boucle à canal multiple, c.-à-d. systèmes de commande redondants
• 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
• G06F 9/38 - Exécution simultanée d'instructions, p. ex. pipeline ou lecture en mémoire

Abrégé

The present invention relates to a method for testing a protection system for multiple reactors, wherein the multiple reactors include a first reactor and a second reactor, the protection system receives a state signal of each of the reactors and determines whether to shut down the reactor or whether to operate an engineered safety feature actuation system device, each of the first reactor and the second reactor includes a first operation channel and a second operation channel, each of the operation channels includes a comparison logic processor and a coincidence logic processor, and the method comprises the steps of: indicating an operator to perform a test for the first operation channel of the first reactor; receiving an input of the operator's test performance task performed for the first operation channel of the first reactor; and performing the input operator's test performance task in the same manner for the first operation channel of the second reactor.

Classes IPC  ?

• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation
• 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 modular casing for a low-pressure turbine of a power plant. The modular casing for a low-pressure turbine of a power plant comprises: an inner casing accommodating a rotor of the low-pressure turbine and extending lengthwise in one direction; and an outer casing accommodating the inner casing, wherein the outer casing comprises: a rectangular module for forming a rectangular parallelepiped-shaped first accommodation space; and a semicircular module for forming a semicylindrical second accommodation space communicating with the first accommodation space, wherein a first through hole corresponding to one end of the inner casing and a second through hole corresponding to the other end of the inner casing are formed in the outer casing.

Classes IPC  ?

• F01D 25/24 - Carcasses d'enveloppeÉléments de la carcasse, p. ex. diaphragmes, fixations

Abrégé

The present invention relates to a diverse protection system and a diverse-component control system for reactors and, more specifically, to a diverse protection system (DPS) and a diverse-component control system (D-CSS) satisfying single failure criterion requirements. The present invention comprises: a diverse protection system including a plurality of logic controllers that uses, as inputs, at least some of a diverse protection system sensor, a plant protection system sensor, and an ex-core neutron flux monitoring system sensor, and output at least four reactor trip signals and signals corresponding to the diverse-component control system; and a diverse-component control system including component control logic processors configured in a redundant structure, wherein the component control logic processors perform selective 2/4 logic by receiving signals, which correspond to the input of the diverse-component control system and are output from the diverse protection system.

Classes IPC  ?

• G21C 3/04 - Détails de structure
• G05B 9/03 - Dispositions de sécurité électriques avec une boucle à canal multiple, c.-à-d. systèmes de commande redondants
• H02H 3/05 - Circuits de protection de sécurité pour déconnexion automatique due directement à un changement indésirable des conditions électriques normales de travail avec ou sans reconnexion Détails avec des moyens pour accroître la fiabilité, p. ex. dispositifs redondants

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  ?

• G01N 29/12 - Analyse de solides en mesurant la fréquence ou la résonance des ondes acoustiques
• F16L 55/40 - Caractéristiques de structure du corps
• F16L 101/30 - Vérification, mesure ou test
• G01N 29/22 - Recherche ou analyse des matériaux par l'emploi d'ondes ultrasonores, sonores ou infrasonoresVisualisation de l'intérieur d'objets par transmission d'ondes ultrasonores ou sonores à travers l'objet Détails
• G01N 29/265 - Dispositions pour l'orientation ou le balayage en déplaçant le capteur par rapport à un matériau fixe
• G01N 29/34 - Génération des ondes ultrasonores, sonores ou infrasonores
• G01N 29/44 - Traitement du signal de réponse détecté
• G01N 29/46 - Traitement du signal de réponse détecté par analyse spectrale, p. ex. par analyse de Fourier

Abrégé

The present invention relates to a nuclear power plant considering defense-in-depth levels, comprising: a plurality of reactors; common facilities that are jointly used by the plurality of reactors; and a measurement control system including a plurality of measurement control platforms corresponding to various operating conditions, wherein the measurement control system separately measures and controls the respective reactors and the common facilities.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire
• G21D 3/04 - Dispositions de sécurité
• 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

A noise reduction apparatus for a control rod position includes a control rod driving shaft connected to a control rod and configured to move in an up-and-down direction, a drive unit configured to move the control rod driving shaft and including a driving coil surrounding an outside of the control rod driving shaft, a solenoid spaced apart from the drive unit and surrounding the outside of the control rod driving shaft, wherein inductance of the solenoid changes due to a movement of the control rod driving shaft, and a reduction coil configured to reduce noise transmitted from the driving coil to the solenoid.

Classes IPC  ?

• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes
• G01D 5/20 - Moyens mécaniques pour le transfert de la grandeur de sortie d'un organe sensibleMoyens pour convertir la grandeur de sortie d'un organe sensible en une autre variable, lorsque la forme ou la nature de l'organe sensible n'imposent pas un moyen de conversion déterminéTransducteurs non spécialement adaptés à une variable particulière utilisant des moyens électriques ou magnétiques influençant la valeur d'un courant ou d'une tension en faisant varier l'inductance, p. ex. une armature mobile

Abrégé

The present invention relates to a method for designing a reactor protection system for individual state signals. The reactor protection system receives an input of the individual state signals, determines an operation condition of a reactor shutdown or a safety device, and has a basic number of channels for the input and the determination. The method comprises the steps of: designing the number of channels according to whether to apply at least one from among a malfunction consideration requirement, a single failure requirement, and an online maintenance requirement; designing the multiplexing of the channels according to whether to apply a reliability improvement requirement; and designing the application of a heterogeneous device to the channels according to whether to apply an inherent diversity implementation requirement.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
• G06F 9/38 - Exécution simultanée d'instructions, p. ex. pipeline ou lecture en mémoire

Abrégé

The present invention relates to a nuclear reactor protection system. According to one embodiment of the present invention, a nuclear reactor protection system using heterogeneous processors comprises: M channels that equally receive N different input signals, where M and N are integers greater than 1; and a pair of protection logic processors arranged on each of the M channels, which receive the N different input signals, perform protection logic, and generate a trip signal, wherein the pair of protection logic processors is configured within a single board in each of the M channels.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
• G06F 9/38 - Exécution simultanée d'instructions, p. ex. pipeline ou lecture en mémoire

Abrégé

The present invention relates to a reactor protection system. A reactor protection system using a heterogeneous processor according to an embodiment of the present invention includes: M channels for equally receiving input signals of N different items, wherein M and N are an integer greater than 1; at least two bistable logic processors which are arranged in each of the M channels and perform bistable logic by receiving the input signals of the N different items; and at least two coincidence logic processors which are arranged in each of the M channels, and receive a processing result of the at least two bistable logic processors to perform coincidence logic and generate a trip signal, wherein the at least two bistable logic processors and the at least two coincidence logic processors are implemented in a single board in each of the M channels.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
• G06F 9/38 - Exécution simultanée d'instructions, p. ex. pipeline ou lecture en mémoire

Abrégé

The present invention relates to a reactor protection system. The reactor protection system using a heterogeneous bistable/coincidence logic integrated processor according to an embodiment of the present invention comprises: M channels that equally receive input signals of N different items; M signal separators that are disposed in the M channels, respectively, and receive the input signals of the N different items to physically separate and transmit each of the input signals of the N different items, wherein M and N are integers greater than 1; and coincidence logic/bistable integration processors that are disposed in the M channels respectively, receive all the input signals of the N different items separated from each other from the M signal separators, and integrate the coincidence logic/bistable.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
• G06F 9/38 - Exécution simultanée d'instructions, p. ex. pipeline ou lecture en mémoire

Abrégé

The present invention relates to a reactor protection system, and the reactor protection system using multiple coincidence processors, according to an embodiment of the present invention, comprises: M channels equally receiving input signals of N mutually different items, wherein M and N are integers greater than 1; M coincidence processors that are respectively arranged in the M channels and receive the input signals of the N mutually different items; and bistable processors that are respectively arranged in the M channels and generate trip signals by receiving the processing results of the coincidence processors and performing bistable logic.

Classes IPC  ?

• G21D 3/04 - Dispositions de sécurité
• G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
• G06F 9/38 - Exécution simultanée d'instructions, p. ex. pipeline ou lecture en mémoire

Abrégé

The present invention relates to a system for producing hydrogen while interworking with a nuclear power plant, the system comprising: a water electrolysis facility for producing hydrogen and oxygen by using vapor supplied from a nuclear power plant; and a power supply controller for selecting at least one reactor module from multiple reactor modules for hydrogen production by the water electrolysis facility, and selecting at least one from multiple generators or power grids such that power is supplied therefrom to the water electrolysis facility. According to an embodiment, power and hydrogen can be simultaneously produced. Particularly, hydrogen can be produced continuously in an economical and effective manner by selecting an optimal reactor module from multiple reactor modules for hydrogen production and by selecting an optimal power supply source from various power sources.

Classes IPC  ?

• C25B 1/042 - Hydrogène ou oxygène par électrolyse de l'eau par électrolyse de la vapeur
• G21D 5/12 - Agent de travail liquide vaporisé par le réfrigérant du réacteur
• H02J 3/00 - Circuits pour réseaux principaux ou de distribution, à courant alternatif

Abrégé

A core catcher system according to an embodiment of the present invention, which prevents unnecessary supply of cooling water from a cooling water tank, comprises: a core molten material monitoring sensor assembly including an expansion sensor and a stress sensor which are attached to the outer wall of the lower portion of a nuclear reactor, an infrared sensor which measures a temperature of a reactor cavity, and a wind pressure-wind velocity sensor for measuring an air flow in the reactor cavity; a determination unit for determining whether the outputs of the expansion sensor and the stress sensor are equal to or greater than a predetermined value and whether the outputs of the infrared sensor and the wind pressure-wind velocity sensor are equal to or greater than a predetermined value in the core molten material monitoring sensor assembly; and a control unit for operating a valve unit of the cooling water tank for supplying cooling water to a core catcher when the determination unit determines that any one of the output values of the expansion sensor and the stress sensor is equal to or greater than the predetermined value and any one of the output values of the infrared sensor and the wind pressure-wind velocity sensor is equal to or greater than the predetermined value.

Classes IPC  ?

• G21C 9/016 - Récupérateurs de cœur
• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes

Abrégé

An SMR core lower flow optimization system according to one embodiment of the present invention comprises: a reactor vessel which accommodates a core; a plurality of steam generators which are arranged at the upper part of the core inside the reactor vessel and generate steam by heat exchange between cooling water and a reactor coolant circulating inside the reactor vessel; and a lower flow optimization unit which is disposed at the lower portion of the core and optimizes the internal flow of the reactor coolant discharged from the plurality of steam generators, wherein the lower flow optimization unit changes the shape of a flow path control hole through which the reactor coolant moves according to changes in flow conditions of the lower portion of the core according to the changes in the overall flow characteristics when proceeding from an initial high-temperature shutdown state to start-up and finally to full-power normal-state operation.

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 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

The present invention relates to a core catcher which can improve cooling performance. The core catcher, according to the present invention, comprises: a main body container formed to accommodate a molten core material which has descended from the nuclear reactor pressure vessel and having sloped surfaces, which correspond to each other, in the lower part thereof; and a lower structure spaced apart from the lower part of the main body container to form a cooling channel therebetween and having a coolant inlet for supplying the coolant to the cooling channel along the central part of the lower structure, wherein the bottom surface of the main body container is formed in a wavy shape so as to increase the contact surface area with the coolant.

Classes IPC  ?

• G21C 9/016 - Récupérateurs de cœur

Abrégé

A molten core material handling system for an SMR in the event of a severe accident, according to an embodiment of the present invention, comprises: a U-shaped wall unit attached to a lower outer wall of a reactor vessel at a predetermined interval to transfer heat generated from nuclear fuel of a core disposed in a lower portion of the reactor vessel; a U-shaped cooling water storage space in which cooling water is filled between the lower outer wall of the reactor vessel and the U-shaped wall unit; and a pressure release valve configured to open and close the U-shaped cooling water storage space at the upper end of the U-shaped wall unit, and thus the core molten material handling system can perform initial in-vessel retention (IVR) in the event of a severe SMR accident, and can secure a time in which, in the event of a severe accident, a molten core material is caught, by means of the cooling water tank that surrounds the lower part of the reactor provided with a PRD, in the lower part of the reactor or the inside of the cooling water tank, and shutdown cooling can be smoothly performed by other passive or active safety equipment.

Classes IPC  ?

• G21C 9/016 - Récupérateurs de cœur
• G21C 9/004 - Suppression de la pression
• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
• 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

In a natural circulation SMR nuclear reactor according to one embodiment of the present invention, an inner plate heat exchanger having an elongated plate shape is compactly connected to the inside of a nuclear reactor vessel in the vertical direction in an integral or assembled manner in place of a conventional independent helical steam generator, an outer plate heat exchanger is compactly connected to the outside of the nuclear reactor vessel in the vertical direction in an integral or assembled manner, and an outer steam generator containing the outer plate heat exchanger is installed on the outer periphery of the nuclear reactor vessel, thereby facilitating internal flow. Thus, the need to drill holes for supplying water to and discharging steam from the steam generator into the nuclear reactor vessel may be reduced.

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
• G21D 1/00 - Détails 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

Disclosed is a concrete structure drilling method for post-installed anchor construction. The concrete structure drilling method for post-installed anchor construction is for drilling an anchor hole of a post-installed anchor on a concrete structure side in a state in which the expansion of a concrete fracture failure section can be induced, the method comprising the steps of: forming an anchor hole vertically on a concrete structure side; and forming an expansion locking groove horizontally on the lower side of the anchor hole.

Classes IPC  ?

• B28D 1/14 - Travail de la pierre ou des matériaux analogues p. ex. briques, béton, non prévu ailleursMachines, dispositifs, outils à cet effet par forage ou perçage

Abrégé

The present invention relates to a composite water electrolysis system using nuclear power plant heat and electrical energy, and, to a composite water electrolysis system for receiving heat energy and electrical energy generated in each of a plurality of SMRs, the system comprising: a heat energy storage hub for storing the heat energy generated in each of the plurality of SMRs; an electrical energy storage hub for storing electrical energy generated in each of the plurality of SMRs; and a composite hydrogen production unit, which receives heat and electricity from the heat energy storage hub and the electrical energy storage hub so as to generate hydrogen and oxygen. According to one embodiment, technologies such as hydrogen production through high-temperature water electrolysis, low-temperature water electrolysis, and ammonia decomposition are diversified, hydrogen and oxygen produced through high-temperature water electrolysis are in a high-temperature state, and the waste heat energy discarded when hydrogen and oxygen are cooled to a low temperature in order to be stored can be used as an additional heat source of low-temperature water electrolysis and ammonia hydrogen decomposition devices.

Classes IPC  ?

• C25B 1/02 - Hydrogène ou oxygène
• C25B 1/042 - Hydrogène ou oxygène par électrolyse de l'eau par électrolyse de la vapeur
• C25B 15/08 - Alimentation ou vidange des réactifs ou des électrolytesRégénération des électrolytes
• C25B 9/65 - Dispositifs pour l'alimentation en courantConnexions d'électrodesConnexions électriques intercellulaires
• G21D 1/00 - Détails des installations à énergie nucléaire

Abrégé

The present invention relates to an operating system for a small modular reactor (SMR) using energy storage equipment in an independent power grid, the operating system comprising: an SMR (110); an electricity/steam regulation unit (120) that regulates and discharges electricity and steam generated from the SMR (110); a pumped-storage power plant (130) for pumped-storage power generation using the electricity from the electricity/steam regulation unit (120); a hydrogen production facility (140) that produces and stores hydrogen by using the electricity and steam from the electricity/steam regulation unit; and a phase change material energy storage unit (150) that stores energy in a phase change material by using the steam from the electricity/steam regulation unit (120).

Classes IPC  ?

• G21D 5/08 - Réacteur et moteur non structurellement combinés dont l'agent intermédiaire de travail du moteur est chauffé par le réfrigérant du réacteur dans un échangeur de chaleur
• 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 passive cooling system of a small modular reactor, and to the passive cooling system of the small modular reactor, the system comprising: a reactor building having an inner space; an integral reactor which is located in the reactor building and which includes a reactor core and a steam generator; a containment vessel, which is located in the reactor building, accommodates the integral reactor and has a cooling space encompassing the integral reactor; a first heat exchanger which is formed in the cooling space, and which cools and condenses the steam discharged from the integral reactor; and a passive cooling unit, which condenses, by means of passive heat exchange, the steam discharged from the steam generator, re-supplies the condensed steam to the steam generator, and passively removes the heat generated in the first heat exchanger.

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 15/16 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques comprenant des moyens de séparation du liquide et de la vapeur
• 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 provides a control simulation system for a nuclear power plant facility, wherein an operator can be trained to control an emergency diesel generator (EDG) installed in a nuclear power plant by using a control panel model and augmented reality regarding control panel manipulation. According to the present invention, the control simulation system for a nuclear power plant facility comprises: a control part provided to perform control training on a nuclear power plant facility; a utilization part comprising a processing unit and a display unit, the processing unit generating augmented reality related to guidance about the manipulation of the control part, and the display unit being provided to photograph the control part, acquire an image of the control part, recognize the control part from the image, receive the augmented reality from the processing unit to map the augmented reality to the recognized control part, and output the mapped augmented reality; and a monitoring part which generates a simulation measurement value of the nuclear power plant facility on the basis of manipulation data generated by manipulating the control part, and provides the simulation measurement value and a normal measurement value that is acquired when the nuclear power plant facility operates normally. Accordingly, the present invention has the effect of enabling pre-training on control panel manipulation, thereby enhancing the operator's operational ability.

Classes IPC  ?

• G09B 9/00 - Simulateurs pour l'enseignement ou l'entraînement
• G09B 19/00 - Enseignement non couvert par d'autres groupes principaux de la présente sous-classe
• G06F 3/01 - Dispositions d'entrée ou dispositions d'entrée et de sortie combinées pour l'interaction entre l'utilisateur et le calculateur
• G06F 3/048 - Techniques d’interaction fondées sur les interfaces utilisateur graphiques [GUI]
• G06T 19/00 - Transformation de modèles ou d'images tridimensionnels [3D] pour infographie
• G02B 27/01 - Dispositifs d'affichage "tête haute"

Abrégé

The present invention relates to a depressurization system for a containment vessel of a nuclear power plant, the system comprising: a reactor vessel for accommodating a reactor core, a steam generator and a primary coolant; a containment vessel which has a free space and which accommodates the reactor vessel in the free space; a steam discharge part which is disposed at the upper portion of the reactor vessel and which discharges the steam of the primary coolant; a storage vessel which is connected to the steam discharge part and which stores a secondary coolant; and a spray part connected to the storage container so as to spray the secondary coolant into the free space.

Classes IPC  ?

• G21C 9/008 - Suppression de la pression par des disques ou des diaphragmes de rupture
• G21D 3/04 - Dispositions de sécurité

Abrégé

The present invention relates to a small module reactor capable of increasing operation reliability of an emergency recirculation valve for recirculation of cooling water in an emergency core cooling system, wherein an emergency recirculation valve (240) provided in the emergency core cooling system of the small module reactor including a reactor vessel (210) and a containment vessel (220), comprises: a valve body (241) provided in the reactor vessel (210) and provided with a disk (242) which is opened and closed by a differential pressure between the reactor vessel (210) and the containment vessel (220) to regulate the flow of coolant; a first elastic body (245) which elastically supports the disk (242) in the valve body (241); a stopper member (246) provided in the driving direction of the disk (242) to limit the driving of the disk (242); and a chamber (243) in which a diaphragm (244) connected to the stopper member (246) is accommodated and control pressure is supplied to one space partitioned by the diaphragm (244).

Classes IPC  ?

• F16K 31/126 - Moyens de fonctionnementDispositifs de retour à la position de repos actionnés par un fluide le fluide agissant sur un diaphragme, un soufflet ou un organe similaire
• F16K 31/122 - Moyens de fonctionnementDispositifs de retour à la position de repos actionnés par un fluide le fluide agissant sur un piston
• F16K 1/34 - Parties d'obturation
• F16K 31/06 - Moyens de fonctionnementDispositifs de retour à la position de repos électriquesMoyens de fonctionnementDispositifs de retour à la position de repos magnétiques utilisant un aimant
• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
• 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 system supporting voice operation using fatigue measurements of nuclear power plant operators, and the system carries out the following: a stress index calculation step of calculating a stress index by comparing received biometric information with prestored biometric information of a normal state; a determination step of determining the operator's state as one of normal, observational, and dangerous on the basis of whether the calculated stress index exceeds a preset threshold value; a haptic function driving unit activation step of activating a chatbot operating unit and a haptic function driving unit if the determined state indicates that the observational state has been entered; and a success determination step of determining whether the stress index has been successfully reduced after the haptic function driving unit activation step. According to an embodiment, dynamic responses to fatigue of the operators can start at the observational state, thereby preventing entry into the dangerous state.

Classes IPC  ?

• G06Q 10/10 - BureautiqueGestion du temps
• G06Q 10/06 - Ressources, gestion de tâches, des ressources humaines ou de projetsPlanification d’entreprise ou d’organisationModélisation d’entreprise ou d’organisation
• H04L 51/02 - Messagerie d'utilisateur à utilisateur dans des réseaux à commutation de paquets, transmise selon des protocoles de stockage et de retransmission ou en temps réel, p. ex. courriel en utilisant des réactions automatiques ou la délégation par l’utilisateur, p. ex. des réponses automatiques ou des messages générés par un agent conversationnel
• A61B 5/0533 - Mesure de la réaction cutanée galvanique
• A61B 5/16 - Dispositifs pour la psychotechnieTest des temps de réaction
• G08B 21/18 - Alarmes de situation
• G08B 3/10 - Systèmes de signalisation audibleSystèmes d'appel sonore de personnes utilisant une transmission électriqueSystèmes de signalisation audibleSystèmes d'appel sonore de personnes utilisant une transmission électromagnétique
• G08B 5/22 - Systèmes de signalisation optique, p. ex. systèmes d'appel de personnes, indication à distance de l'occupation de sièges utilisant une transmission électriqueSystèmes de signalisation optique, p. ex. systèmes d'appel de personnes, indication à distance de l'occupation de sièges utilisant une transmission électromécanique
• G21D 3/00 - Commande des installations à énergie nucléaire

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 1st 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 2nd 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  ?

• G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
• B28D 1/22 - Travail de la pierre ou des matériaux analogues p. ex. briques, béton, non prévu ailleursMachines, dispositifs, outils à cet effet par découpage, p. ex. exécution d'entailles
• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur

Abrégé

The present invention relates to an apparatus for transporting a nuclear fuel assembly, the apparatus, which transports a nuclear fuel assembly within a nuclear power plant, comprising: a hoist box; a driving unit for moving the hoist box horizontally and vertically; a grip unit arranged on the bottom of the hoist box and connected thereto to allow gripping the nuclear fuel assembly; a lattice-like support unit positioned above the nuclear fuel assembly and corresponding to the placement of the nuclear fuel therein; and a centering unit disposed in at least one among the hoist box, grip unit, and support unit, and used to adjust the alignment of the nuclear fuel assembly and grip unit.

Classes IPC  ?

• G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
• H01F 7/20 - Électro-aimantsActionneurs comportant des électro-aimants sans armature
• H01F 7/02 - Aimants permanents
• G01S 17/06 - Systèmes déterminant les données relatives à la position d'une cible
• G01S 15/06 - Systèmes déterminant les données relatives à la position d'une cible

Abrégé

The present invention relates to an apparatus for transporting a nuclear fuel assembly, the apparatus, which transports a nuclear fuel assembly within a nuclear power plant comprising small modular reactors (SMRs), comprising: a hoist box that can move within the nuclear power plant, moving between the SMRs and nuclear fuel assembly; a fixing part partially attached to the nuclear fuel assembly to fix same; first and second wires connecting the hoist box and fixing part, the first wire supporting the fixing part during the lowering stage; and a stiffness adjustment part for adjusting the stiffness of the second wire.

Classes IPC  ?

• G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
• G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
• 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 vitrification equipment starting method and starting unit. The vitrification equipment starting method includes: preparing an ignition module; putting the ignition module into a chamber of a low-temperature melting furnace; and performing an ignition operation inside the chamber of the low-temperature melting furnace using the ignition module connected to a high-frequency heating unit outside the low-temperature melting furnace, wherein the ignition module is put into the chamber of the low-temperature melting furnace in an initial state before a form thereof is changed and, when put into the chamber of the low-temperature melting furnace, becomes a variable state in which the form thereof is changed from the initial state and performs the ignition operation.

Classes IPC  ?

• C03B 5/00 - Fusion dans des foursFours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre
• F23Q 13/00 - Allumage non prévu ailleurs

Abrégé

The present invention relates to a temperature raising system for a small modular nuclear power plant, comprising: a nuclear reactor assembly unit including a plurality of integrated nuclear reactors; a turbine unit which operates through steam supplied from an operating nuclear reactor being in operation in the reactor assembly unit; and a steam storage unit in which at least part of the steam supplied to the turbine unit is extracted and stored, and which supplies the steam to a starter nuclear reactor requiring to be started in the nuclear reactor assembly unit.

Classes IPC  ?

• G21D 5/02 - Réacteur et moteur structurellement combinés, p. ex. portatifs
• G21D 1/02 - Dispositions d'équipement auxiliaire
• 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

A small modular reactor cooling device and cooling method are provided. A small modular reactor cooling device includes: a reactor vessel in which a coolant circulates along a flow path structure; and a coolant storage unit provided inside the reactor vessel and charged with the coolant inside based on the circulating flow, wherein the coolant storage unit is in contact with a core melted material through the coolant charged therein when the core melted material is generated in the reactor vessel in the event of a serious accident and performs a cooling treatment on the core melted material to prevent the core melted material from leaking out to the outside.

Classes IPC  ?

• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
• G21C 9/016 - Récupérateurs de cœur

Abrégé

There are provided a small nuclear reactor cooling system and cooling method. The small nuclear reactor cooling system includes: a cooling unit in which a small nuclear reactor is positioned and which performs cooling processing corresponding to a severe accident in the cooling system when the severe accident occurs in the small nuclear reactor, wherein the cooling unit provides a 1st cooling fluid so as to perform the cooling processing in response to heat generated by the severe accident.

Classes IPC  ?

• G21C 15/12 - 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 de l'enceinte sous pressionAménagement 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 de l'enceinte d'enveloppe
• G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur

Abrégé

The present invention relates to a nuclear reactor system using a multi-layered rail. The nuclear reactor system according to the present invention comprises: a plurality of integrated nuclear reactors in which nuclear fuel is loaded; a containment structure having a plurality of accommodation spaces formed therein and accommodating the integrated nuclear reactors one by one in the accommodation spaces; a first rail formed across the plurality of accommodation spaces along a first direction; a second rail formed separately in each of the accommodation spaces along the first direction; a reloader configured to move on the first rail and the second rail and to draw out the nuclear fuel; and a moving unit configured to move the reloader from one of the first rail and the second rail to the other.

Classes IPC  ?

• G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
• G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles

Abrégé

The present invention relates to an improved reactivity calculator employing a method of abnormal signal removal and signal normalization and, more specifically, to an improved reactivity calculator which employs a method of distinguishing abnormal signals from an ex-core detector to remove the abnormal signals and perform signal normalization. According to the present invention, the calculator comprises: a data acquisition unit which collects raw signal data from an ex-core detector to normalize, to an average value of a predetermined time period, ex-core detector signals of data obtained from the measurement of a zero-power characteristic test range or the measurement of an initial critical point before a zero-power characteristic test; and a reactivity calculation unit which selects and excludes abnormal signals from measured ex-core detector signals to calculate reactivity by using the remaining signals. Therefore, the calculator can distinguish abnormal signals from an ex-core detector and remove same by normalizing ex-core detector signals to an average value of a predetermined time period.

Classes IPC  ?

• G21C 17/104 - Mesure de la réactivité

Abrégé

This waste control rod decontamination apparatus comprises: a cylindrical support body including a first seating groove in which a waste control rod with both ends cut off is seated and which is recessed from a surface and extends in a first direction, wherein the cylindrical support body rotates about a rotation axis in a second direction intersecting the first direction; a surface dose rate measurement unit positioned on the cylindrical support body and moving along the first direction; a non-destructive inspection unit neighboring the surface dose rate measurement unit and moving along the first direction on the cylindrical support body; and a first decontamination unit inserted into the waste control rod through one of both ends of the waste control rod seated in the first seating groove, and chemically decontaminating the inside of the waste control rod.

Classes IPC  ?

• G21F 9/00 - Traitement des matériaux contaminés par la radioactivitéDispositions à cet effet pour la décontamination
• G01T 1/02 - Dosimètres
• G01N 22/00 - Recherche ou analyse des matériaux par l'utilisation de micro-ondes ou d'ondes radio, c.-à-d. d'ondes électromagnétiques d'une longueur d'onde d'un millimètre ou plus

Abrégé

A nuclear power plant virtualization system and an operation method thereof are provided. A nuclear power plant virtualization system includes: virtual machine control parts; virtual machine network parts linked to the virtual machine control parts; and a virtualization platform switch linked with the virtual machine control parts and the virtual machine network parts, wherein the virtual machine control parts include a first MMI linked driver module, the virtual machine network parts include a second MMI linked driver module, and the virtual machine control parts and the virtual machine network parts modify an IP/MAC address in data communicated with the outside and allow the data communicated with the outside from the virtual machine control parts to pass through the virtual machine network parts, via the first MMI linked driver module and the second MMI linked driver module.

Classes IPC  ?

• G06F 9/455 - ÉmulationInterprétationSimulation de logiciel, p. ex. virtualisation ou émulation des moteurs d’exécution d’applications ou de systèmes d’exploitation

Abrégé

A method for dismantling a waste control rod assembly including a spider body and a plurality of waste control rods supported by the spider body comprises the steps of: supporting the spider body on a support body including a plurality of through-holes through which the plurality of waste control rods extends; cutting the upper ends of the plurality of waste control rods adjacent to the spider body to separate the plurality of waste control rods from the spider body; and cutting the spider body supported by the support body into a plurality of pieces to dismantle same.

Classes IPC  ?

• G21C 19/37 - Séparation du combustible et des chemisages ou des gaines par mise en pièces à la fois de l'élément combustible et de son gainage ou de son chemisage, p. ex. par découpage ou cisaillage
• G21D 1/00 - Détails des installations à énergie nucléaire

Abrégé

Disclosed is a multi-column structure for reducing a vertical seismic load, which disperses a seismic load applied in the vertical direction. The multi-column structure for reducing a vertical seismic load of the present invention comprises: a plurality of columns installed between a lower layer and an upper layer; a vertical load reduction portion which is installed between the plurality of columns and the lower layer or between the plurality of columns and the upper layer; and a plurality of side vertical load reduction portions which are installed to connect the plurality of columns to side surfaces of another, separate plurality of columns arranged adjacent thereto to disperse the seismic load applied to the vertical load reduction portion.

Classes IPC  ?

• F16F 15/02 - Suppression des vibrations dans les systèmes non rotatifs, p. ex. dans des systèmes alternatifsSuppression des vibrations dans les systèmes rotatifs par l'utilisation d'organes ne se déplaçant pas avec le système rotatif
• F16F 15/04 - Suppression des vibrations dans les systèmes non rotatifs, p. ex. dans des systèmes alternatifsSuppression des vibrations dans les systèmes rotatifs par l'utilisation d'organes ne se déplaçant pas avec le système rotatif utilisant des moyens élastiques

Abrégé

The present invention relates to: a jig for creating a non-oxidizing environment; and a mechanical high-temperature physical property testing apparatus and method using same. The jig for creating a non-oxidizing environment and the mechanical high-temperature physical property testing apparatus using same of the present invention comprise: upper and lower connection members disposed on upper and lower portions, respectively; a weight disposed to surround the upper connection member to fix a specimen; an air-cooled cooling engine for air-cooling a tester; a cover part installed at the upper and lower portions; and an inert gas supply line at the lower end of a high-temperature quartz pipe and through which inert gas lighter than air is supplied, wherein the cover part made of a heat-resistant lightweight alloy has a rubber sealing installed between an outer cover and an inner cover, a furnace is installed outside the high-temperature quartz pipe to be movable from Fmin (lowest point) to Fmax (highest point), and the furnace is moved to Fmax to uniformly heat the high-temperature quartz pipe.

Classes IPC  ?

• G01N 3/18 - Exécution de tests à des températures élevées ou basses
• G01N 3/04 - Mandrins

Abrégé

The present invention provides a process for disposing of a composite structure containing radioactive waste, the process being for containing and solidifying a high-dose concentrated waste liquid in a drum, and disposing of a composite structure, which is a large concrete loading container in which the drum is contained. The process for disposing of a composite structure containing radioactive waste, of the present invention, comprises the steps of: providing a support structure at the lower portion of the composite structure in which radioactive waste is contained; forming a penetration part by perforating the lower portion of a concrete container forming the composite structure after the step of providing the support structure; performing a separation process of separating out the radioactive waste contained therein through the penetration part after the step of forming the penetration part; and cutting and disassembling the composite structure after the step of performing the separation process.

Classes IPC  ?

• G21F 9/30 - Traitements
• G21F 9/00 - Traitement des matériaux contaminés par la radioactivitéDispositions à cet effet pour la décontamination
• G21F 1/04 - BétonsAutres matériaux durcis hydrauliquement
• G01T 1/167 - Mesure du contenu radioactif des objets, p. ex. contamination
• G21F 5/002 - Récipients pour déchets radioactifs fluides

Abrégé

The present invention provides: a radioactive waste drum in which high-dose concentrated waste liquid is contained; a loading container for containing a radioactive waste drum, the loading container enabling collection of a sample of internal waste in order to evaluate physicochemical and radiological properties of the concentrated waste liquid in the loading container in which the drum is stored; and a method for collecting a sample of internal waste therefrom. According to the present invention, the loading container for storing a radioactive waste drum includes a radioactive waste drum in which radioactive waste is contained, and a concrete loading container storing the radioactive waste drum. The concrete loading container includes a sample collecting unit for collecting a sample of concentrated waste liquid contained in the radioactive waste drum. The sample collecting unit is configured as a pipe having a predetermined length and passing through the concrete loading container and the radioactive waste drum, and has a gradient.

Classes IPC  ?

• G21F 5/06 - Détails ou accessoires des récipients
• G21F 5/002 - Récipients pour déchets radioactifs fluides
• G21F 1/04 - BétonsAutres matériaux durcis hydrauliquement
• G01N 1/10 - Dispositifs pour prélever des échantillons à l'état liquide ou fluide

Abrégé

The present invention relates to a large concrete container for treating radioactive waste configured such that the large concrete container in which radioactive waste is accommodated can be moved precisely, and radioactive waste samples stored in drums can be collected easily and quickly. The present invention provides a large concrete container for treating radioactive waste, wherein multiple drums that contain radioactive waste can be accommodated therein and stored in a storage facility, the large concrete container has penetration parts formed on both sides thereof in corresponding directions, and penetration parts are provided with insertion structures used when collecting samples of the radioactive waste contained in the drums.

Classes IPC  ?

• G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p. ex. dispositifs de transport
• G21F 5/12 - Dispositifs obturateurs pour récipientsDispositions pour leur étanchéité
• G21F 1/04 - BétonsAutres matériaux durcis hydrauliquement

Abrégé

The present invention relates to a pad for preventing the diffusion of radioactive liquid waste, the pad being capable of preventing liquid waste from being diffused to the outside if a large concrete container accommodating the radioactive waste is cut and disassembled. The provided pad for preventing the diffusion of radioactive liquid waste, of the present invention, is a diffusion prevention pad that supports the lower part of a container when treating the large concrete container in which a drum containing radioactive waste is accommodated, so as to prevent the diffusion of radioactive liquid waste, wherein the diffusion prevention pad is formed by sequentially stacking a lower support layer, a nuclide removal resin layer, a hygroscopic polymer structure layer and a cover sheet layer.

Classes IPC  ?

• G21F 3/00 - Blindage caractérisé par sa forme physique, p. ex. granulés, ou forme du matériau
• G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p. ex. dispositifs de transport
• G21F 1/04 - BétonsAutres matériaux durcis hydrauliquement

Abrégé

A concrete overpacking structure for a high integrity container (HIC) is disclosed. The concrete overpacking structure for an HIC is a concrete structure for overpacking the HIC for containing radioactive waste to be inserted and stored therein, and comprises: a structure body having a concrete container part and a concrete cover part for overpacking of the HIC; and sampling port parts formed at the structure body while a sample to be collected for evaluating the resistance characteristics of the structure body is formed.

Classes IPC  ?

• G21F 9/34 - Moyens de se débarrasser des résidus solides
• G21F 5/06 - Détails ou accessoires des récipients

Abrégé

A method for collecting and evaluating the characteristics of a large concrete container wall block sample according to another aspect of the present invention comprises: cutting at least a portion of a large concrete container to form a concrete container wall block; disposing the concrete container wall block inside a sample collection and characteristics evaluation space-providing apparatus; detaching a detachable surface dose rate measurement device and a detachable sample collection device located in the sample collection and characteristics evaluation space-providing apparatus, and moving the devices toward the concrete container wall block while maintaining a certain distance therefrom; arranging the detachable surface dose rate measurement device and the detachable sample collection device with respect to the concrete container wall block so that the devices do not interfere with each other; and arranging a plurality of the detachable surface dose rate measurement devices spaced apart from each other and a plurality of the detachable sample collection devices spaced apart from each other.

Classes IPC  ?

• G01T 7/02 - Moyens de collection pour recevoir ou conserver des échantillons à examiner
• G01T 1/02 - Dosimètres

Abrégé

The large concrete container cutting, dismantling, and disposal suitability evaluation system according to an embodiment of the present invention comprises: a vertical and horizontal cutting device for a large concrete container and a solidified material, the device being capable of vertically and horizontally cutting a concrete container and a solidified material; a cut block separation device for separating a solidified material block, a grounding concrete block, and an external container block from the cut container and the solidified material cut blocks produced by the vertical and horizontal cutting device for a container and a solidified material; and a suitable disposal device for determining self-disposal or disposal suitability for each of the solidified block, the grounding concrete block, and the external container block individually separated by the cut block separation device, the suitable disposal device enabling self-disposal or disposal when the self-disposal or disposal suitability is satisfied..

Classes IPC  ?

• G21F 9/30 - Traitements
• G21F 5/12 - Dispositifs obturateurs pour récipientsDispositions pour leur étanchéité
• G21F 5/002 - Récipients pour déchets radioactifs fluides
• G01T 1/02 - Dosimètres

Abrégé

A rail-type large concrete drum cutting and dismantling system according to one embodiment of the present invention comprises: a moving rail on which a large concrete drum, which is radioactive wastes, is loaded to be linearly moved to a predetermined position; a rotary platform which is disposed at the predetermined position, and sequentially rotates, at a predetermined angle, according to a predetermined cutting and dismantling control program, the large concrete drum moved along the moving rail; guide rail devices, which are provided at an interval in the vicinity of the rotary platform, disposes a cutting device at a predetermined height with respect to the rotary platform, and moves same by a predetermined angle at the predetermined height; a cutting and dismantling device for cutting and dismantling the large concrete drum while moving by a predetermined angle along the guide rail devices; and a control device for remotely controlling the moving rail, the rotary platform, the guide rail devices, and the cutting and dismantling device according to the cutting and dismantling control program.

Classes IPC  ?

• G21F 9/30 - Traitements
• G21F 5/12 - Dispositifs obturateurs pour récipientsDispositions pour leur étanchéité
• G21F 5/002 - Récipients pour déchets radioactifs fluides
• G21F 5/005 - Récipients pour déchets radioactifs solides, p. ex. pour le stockage final

Abrégé

The present invention relates to a method for producing a nuclear design core model accounting for load following, the method comprising the steps of: receiving load-following requirements for a corresponding cycle, wherein the load-following requirements include the amount of power reduction, the number of load-following operations, and at least one of the time or duration of operation at reduced power; determining the amount of insertion of a control rod on the basis of the load-following requirements; determining the duration of insertion of the control rod on the basis of the amount of insertion of the control rod and the maximum insertion limit thereof; determining the time of insertion of the control rod by simulating core combustion by reflecting the duration of insertion of the control rod in a nuclear design code at each of a plurality of time points of the corresponding cycle; and producing a nuclear design core model accounting for load following on the basis of the determined amount of insertion of the control rod, the determined duration of insertion of the control rod, and the determined time of insertion of the control rod.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire
• G21C 7/08 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c.-à-d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion par déplacement des éléments de commande solides, p. ex. barres de commandes
• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu

Abrégé

Provided are a remote restart system for vitrification equipment and a method of operating the same. The method of operating the remote restart system for the vitrification equipment includes: operating the vitrification equipment; and having power loss in the vitrification equipment, wherein the power loss occurs during or before operation of the vitrification equipment, the remote restart system assists in restarting the vitrification equipment when the power loss occurs in the vitrification equipment, and the remote restart system includes a low-temperature melting furnace, 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 put into the low-temperature melting furnace to handle the glass frit to a state suitable for reignition of the glass frit.

Classes IPC  ?

• G21F 9/30 - Traitements

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 31/58 - Test de lignes, de câbles ou de conducteurs

Abrégé

There are provided a nuclear power plant dismantling method and apparatus. The nuclear power plant dismantling method includes: selecting a nuclear reactor to be dismantled; and performing nuclear power plant dismantling work on the nuclear reactor through a nuclear reactor dismantling apparatus, wherein the nuclear reactor dismantling apparatus includes: a frame unit shielding the nuclear reactor to prevent contaminants in the nuclear reactor from being released to the outside; a cutting module provided on the frame unit and performing cutting work on the nuclear reactor; a link fixing module having a hollow area formed therein, entering an internal space of the nuclear reactor to link the frame unit and the nuclear reactor with each other, and having a bar shape; and a purging module entering the hollow area of the link fixing module and performing purging on the inside of the nuclear reactor in order to secure safety in the cutting work.

Classes IPC  ?

• G21D 1/00 - Détails des installations à énergie nucléaire

Abrégé

The present invention relates to a method for cutting a nuclear reactor and inserting cut materials, the method comprising the steps of: preparing cut materials by cutting a nuclear reactor through a plurality of processes; classifying the cut materials into a plurality of stack shapes; and inserting the cut materials into a packaging container according to the stack shapes, wherein the packaging container includes an external container, an internal container and a cover, and the inserting step includes the steps of: preparing the external container; accommodating the internal container in the external container; and mounting the cover on the upper portion of the internal container.

Classes IPC  ?

• G21D 1/00 - Détails des installations à énergie nucléaire
• G21F 5/005 - Récipients pour déchets radioactifs solides, p. ex. pour le stockage final
• G21F 5/06 - Détails ou accessoires des récipients

Abrégé

Provided is a method of treating radioactive waste glass fiber. The method of treating the radioactive waste glass fiber includes: preparing the radioactive waste glass fiber: loading the radioactive waste glass fiber into a canister; heat-treating the canister under set conditions through a heat treatment unit; and transferring the radioactive waste glass fiber whose volume has been reduced through the heat treatment.

Classes IPC  ?

• G21F 9/30 - Traitements

Abrégé

The present invention relates to a method for controlling a part strength control element assembly to enable turbine load-following, comprising the steps of: identifying operation driving characteristics of a part strength control element assembly according to turbine loads through simulation of power plant-simulation calculations with varying turbine load; determining a maximum insertion position within the core of the part strength control element assembly on the basis of the operation driving characteristics; deriving a target position of the part strength control element assembly according to turbine load on the basis of the maximum insertion position; and controlling the insertion position of the part strength control element assembly according to the target position.

Classes IPC  ?

• G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
• G21D 3/00 - Commande des installations à énergie nucléaire
• G21D 3/16 - Régulation de différents paramètres dans l'installation par ajustement du réacteur en réponse uniquement aux changements se produisant dans la demande du moteur en variant la réactivité
• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu

Abrégé

The present invention relates to a dry storage module for the spent nuclear fuel of a vertical light water reactor, and to a dry storage module with an improved air outlet and cylinder body mounting method, and a system comprising same, the module comprising: a case for forming a hexahedral accommodation space; a plurality of storage parts, which are arranged in two rows in the accommodation space, store the spent nuclear fuel and are elongated; a hexahedral module part for accommodating the storage parts; canisters in which the spent nuclear fuel is loaded; cylinder bodies each encompassing the canister; cylinder supports for attaching/detaching the cylinder body to/from the module part; an air inlet positioned at a side of the upper portion of the case; an air outlet positioned in the lower portion of the case; and shielding grids disposed in each of the inlet and the outlet.

Classes IPC  ?

• 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
• G21F 5/008 - Récipients pour éléments combustibles
• G21F 1/02 - Sélection de matériaux de blindage uniforme

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.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire
• G21C 17/00 - SurveillanceTests

Abrégé

A small modular reactor apparatus and an operation method thereof are provided. A small modular reactor apparatus includes a body unit including a reactor core therein; and an opening and closing unit that is provided to be mounted and detachable from the body unit to open and close an interior of the body unit, wherein the opening and closing unit is provided to be mounted and detachable based on seating downward inside the body unit, and a plurality of In-core instrument (ICI) modules for state measurement of a small modular reactor are inserted and mounted in the opening and 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

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 19/22 - Dispositions pour avoir accès à l'intérieur de l'enceinte sous pression pendant le fonctionnement du réacteur
• G21C 19/04 - Moyens pour commander le flux du réfrigérant sur les objets manipulésMoyens pour commander le flux de réfrigérant à travers le canal à alimenter
• G21C 19/07 - Râteliers de stockagePiscines de stockage
• G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande

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  ?

• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu
• G06F 111/10 - Modélisation numérique

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  ?

• 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 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

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  ?

• G05B 23/02 - Test ou contrôle électrique

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  ?

• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation

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 3/328 - Disposition relative des éléments dans le réseau
• G21C 11/06 - Écrans réflecteurs, c.-à-d. pour minimiser la perte de neutrons

Abrégé

The present invention relates to a method for collecting a sample from a canister, the method comprising the steps of: installing an outer pipe having an accommodation space and having a through hole, on the bottom of the canister in a height direction; inserting an inner pipe having a collection space and having a penetration unit formed therein into the accommodation space of the outer pipe; collecting, when the sample is loaded from the top of the canister, the sample into the collection space through the through hole and the penetration unit; and separating, from the outer pipe, the inner pipe in which at least a portion of the collection space is filled with the sample.

Classes IPC  ?

• G01T 7/02 - Moyens de collection pour recevoir ou conserver des échantillons à examiner

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’énergie 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 visDéchargeurs à vis

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 - 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 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 - ÉchantillonnagePréparation 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 foursFours, 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 foursFours, 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 - AgitateursHomogénéisation 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 - SurveillanceTests
• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu
• G06F 119/02 - Analyse de fiabilité ou optimisation de fiabilitéAnalyse 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 connaissanceAcquisition 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 - 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 radioactivitéDispositions 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

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'accélérationMesure de la décélérationMesure 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 foursFours, 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 descendantAgencements 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 foursFours, 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 foursFours, 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

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'urgenceMise hors circuit de la chaleur

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 radioactivitéDispositions 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