Abstract

The present invention relates to an indirect live wire drilling tool for a lead wire of a gas insulated load break switch for an overhead line, and an operating method thereof, the tool drilling a hole in a covering (3) of a lead wire (1) by means of the rotary force of an end mill (46) in a drill body (10) connected to an indirect live wire insulating stick, so that moisture infiltrating the lead wire (1) can be removed. Therefore, since extra pre-tasks are unnecessary, construction costs and construction time can be minimized and a construction procedure can be simplified, and, since the exposed portion of a charging unit is small when a sleeve cover is removed due to strong winds and typhoons, the probability of failure can be low in comparison with a stripping operation.

IPC Classes  ?

• B26F 1/16 - Perforating by tool or tools of the drill type
• H01H 9/22 - Interlocking, locking, or latching mechanisms for interlocking between casing, cover, or protective shutter and mechanism for operating contacts

Abstract

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.

IPC Classes  ?

• G21C 7/12 - Means for moving control elements to desired position
• G21D 3/00 - Control of nuclear power plant
• G21D 3/16 - Varying reactivity
• G06F 30/20 - Design optimisation, verification or simulation

Abstract

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.

IPC Classes  ?

• G21F 5/10 - Heat-removal systems, e.g. using circulating fluid or cooling fins
• G21F 5/008 - Containers for fuel elements
• G21F 1/02 - Selection of uniform shielding materials

Abstract

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.

IPC Classes  ?

• G21D 3/00 - Control of nuclear power plant
• G21C 17/00 - MonitoringTesting

Abstract

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.

IPC Classes  ?

• G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
• G21C 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements

Abstract

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.

IPC Classes  ?

• G21C 19/22 - Arrangements for obtaining access to the interior of a pressure vessel whilst the reactor is operating
• G21C 19/04 - Means for controlling flow of coolant over objects being handledMeans for controlling flow of coolant through channel being serviced
• G21C 19/07 - Storage racksStorage pools
• G21C 19/10 - Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements

Abstract

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.

IPC Classes  ?

• G06F 30/20 - Design optimisation, verification or simulation
• G06F 111/10 - Numerical modelling

Abstract

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.

IPC Classes  ?

• G21D 3/06 - Safety arrangements responsive to faults within the plant

Abstract

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.

IPC Classes  ?

• G21D 3/04 - Safety arrangements
• G21D 3/00 - Control of nuclear power plant

Abstract

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.

IPC Classes  ?

• G05B 23/02 - Electric testing or monitoring

Abstract

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.

IPC Classes  ?

• G21D 3/06 - Safety arrangements responsive to faults within the plant

Abstract

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.

IPC Classes  ?

• G21C 3/328 - Relative disposition of the elements in the bundle lattice
• G21C 11/06 - Reflecting shields, i.e. for minimising loss of neutrons

Abstract

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.

IPC Classes  ?

• G01T 7/02 - Collecting-means for receiving or storing samples to be investigated

Abstract

Disclosed is a system capable of artificial neural network-based virtual measurement for predicting real-time fuel consumption property information, which is difficult to identify with only a conventional steam power generation fuel management system. The system comprises: a fuel management device for generating predetermined interval fuel consumption property information by using an analysis result to be input therein; a driving management device for generating driving information about the predetermined interval by using driving operation information to be input therein; and a real-time fuel consumption property prediction device which generates an artificial neural network-based virtual measurement model by referring to trends in the fuel consumption property information and the driving information, and which generates a prediction result of real-time fuel consumption property information by using the virtual measurement model.

IPC Classes  ?

• G06Q 50/06 - Energy or water supply
• G06Q 10/04 - Forecasting or optimisation specially adapted for administrative or management purposes, e.g. linear programming or "cutting stock problem"
• G06Q 10/06 - Resources, workflows, human or project managementEnterprise or organisation planningEnterprise or organisation modelling
• G06N 3/08 - Learning methods

Abstract

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.

IPC Classes  ?

• G01H 1/00 - Measuring vibrations in solids by using direct conduction to the detector
• G01M 7/02 - Vibration-testing
• G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations

Abstract

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.

IPC Classes  ?

• H02J 3/00 - Circuit arrangements for ac mains or ac distribution networks
• H02J 9/06 - Circuit arrangements for emergency or stand-by power supply, e.g. for emergency lighting in which the distribution system is disconnected from the normal source and connected to a standby source with automatic change-over
• H02J 3/38 - Arrangements for parallelly feeding a single network by two or more generators, converters or transformers
• G06Q 50/06 - Energy or water supply

Abstract

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.

IPC Classes  ?

• G21F 9/30 - Processing
• F27D 3/08 - Screw feedersScrew dischargers

Abstract

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

IPC Classes  ?

• H04L 9/40 - Network security protocols
• G01R 15/18 - Adaptations providing voltage or current isolation, e.g. for high-voltage or high-current networks using inductive devices, e.g. transformers
• G01R 31/40 - Testing power supplies
• G01R 19/165 - Indicating that current or voltage is either above or below a predetermined value or within or outside a predetermined range of values
• G01R 21/00 - Arrangements for measuring electric power or power factor
• G01R 35/00 - Testing or calibrating of apparatus covered by the other groups of this subclass

Abstract

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.

IPC Classes  ?

• G01T 1/163 - Whole-body counters
• G01T 1/167 - Measuring radioactive content of objects, e.g. contamination
• G01T 7/00 - Details of radiation-measuring instruments
• G06N 3/04 - Architecture, e.g. interconnection topology
• G06N 3/08 - Learning methods

Abstract

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

IPC Classes  ?

• G06Q 50/06 - Energy or water supply
• G06Q 10/06 - Resources, workflows, human or project managementEnterprise or organisation planningEnterprise or organisation modelling
• G06Q 10/04 - Forecasting or optimisation specially adapted for administrative or management purposes, e.g. linear programming or "cutting stock problem"
• G06N 20/00 - Machine learning
• G06F 17/18 - Complex mathematical operations for evaluating statistical data
• G06Q 50/10 - Services
• G01D 21/02 - Measuring two or more variables by means not covered by a single other subclass

Abstract

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

IPC Classes  ?

• H02S 50/00 - Monitoring or testing of PV systems, e.g. load balancing or fault identification
• G06V 10/10 - Image acquisition
• G06N 3/02 - Neural networks
• G08B 21/18 - Status alarms
• G06T 7/90 - Determination of colour characteristics
• G01W 1/10 - Devices for predicting weather conditions

Abstract

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.

IPC Classes  ?

• G01W 1/10 - Devices for predicting weather conditions

Abstract

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.

IPC Classes  ?

• G01N 1/10 - Devices for withdrawing samples in the liquid or fluent state
• G21F 9/30 - Processing
• G01N 1/00 - SamplingPreparing specimens for investigation

Abstract

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.

IPC Classes  ?

• G21F 9/30 - Processing
• C03B 5/00 - Melting in furnacesFurnaces so far as specially adapted for glass manufacture
• C03B 5/235 - Heating the glass
• C03B 5/24 - Automatically regulating the melting process

Abstract

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.

IPC Classes  ?

• G21F 9/30 - Processing
• H05B 6/06 - Control, e.g. of temperature, of power
• C03B 5/00 - Melting in furnacesFurnaces so far as specially adapted for glass manufacture

Abstract

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.

IPC Classes  ?

• G21F 9/30 - Processing
• C03B 3/00 - Charging the melting furnaces
• C03B 5/187 - Stirring devicesHomogenisation with moving elements

Abstract

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.

IPC Classes  ?

• G21D 3/04 - Safety arrangements
• G21C 17/00 - MonitoringTesting
• G06F 30/20 - Design optimisation, verification or simulation
• G06F 119/02 - Reliability analysis or reliability optimisationFailure analysis, e.g. worst case scenario performance, failure mode and effects analysis [FMEA]

Abstract

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.

IPC Classes  ?

• G06N 5/022 - Knowledge engineeringKnowledge acquisition

Abstract

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).

IPC Classes  ?

• H04N 5/33 - Transforming infrared radiation
• G01J 5/00 - Radiation pyrometry, e.g. infrared or optical thermometry
• G01J 5/02 - Constructional details
• G06F 18/23 - Clustering techniques
• G06N 3/08 - Learning methods
• G06T 7/11 - Region-based segmentation

Abstract

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.

IPC Classes  ?

• G21C 17/112 - Measuring temperature
• G21C 17/108 - Measuring reactor flux
• G01K 7/02 - Measuring temperature based on the use of electric or magnetic elements directly sensitive to heat using thermoelectric elements, e.g. thermocouples
• G01K 17/10 - Measuring quantity of heat conveyed by flowing media, e.g. in heating systems based upon measurement of temperature difference between an inlet and an outlet point, combined with measurement of rate of flow of the medium
• G01T 3/00 - Measuring neutron radiation

Abstract

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.

IPC Classes  ?

• G21C 17/003 - Remote inspection of vessels, e.g. pressure vessels
• G01M 3/32 - Investigating fluid tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for containers, e.g. radiators

Abstract

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.

IPC Classes  ?

• G21F 9/02 - Treating gases
• G21F 9/30 - Processing
• G21F 9/32 - Processing by incineration
• G21F 9/00 - Treating radioactively contaminated materialDecontamination arrangements therefor
• B01D 46/66 - Regeneration of the filtering material or filter elements inside the filter
• B01D 53/75 - Multi-step processes
• B01D 53/26 - Drying gases or vapours
• B01D 53/30 - Controlling by gas-analysis apparatus

Abstract

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

IPC Classes  ?

• G01R 31/08 - Locating faults in cables, transmission lines, or networks

Abstract

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

IPC Classes  ?

• G06F 30/27 - Design optimisation, verification or simulation using machine learning, e.g. artificial intelligence, neural networks, support vector machines [SVM] or training a model
• G06F 30/17 - Mechanical parametric or variational design
• F22B 35/18 - Applications of computers to steam-boiler control
• G06F 111/04 - Constraint-based CAD
• G06F 119/08 - Thermal analysis or thermal optimisation
• G06F 111/10 - Numerical modelling

Abstract

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.

IPC Classes  ?

• G01N 29/04 - Analysing solids
• G01N 29/44 - Processing the detected response signal
• G01P 15/18 - Measuring accelerationMeasuring decelerationMeasuring shock, i.e. sudden change of acceleration in two or more dimensions

Abstract

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.

IPC Classes  ?

• G01H 1/00 - Measuring vibrations in solids by using direct conduction to the detector

Abstract

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.

IPC Classes  ?

• G21F 9/30 - Processing
• C03B 5/00 - Melting in furnacesFurnaces so far as specially adapted for glass manufacture

Abstract

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.

IPC Classes  ?

• G21F 9/16 - Processing by fixation in stable solid media
• B01D 29/11 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups Filtering elements therefor with bag, cage, hose, tube, sleeve or like filtering elements
• B01D 29/92 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups Filtering elements therefor having feed or discharge devices for discharging filtrate
• B23B 47/26 - Liftable or lowerable drill heads or headstocksBalancing arrangements therefor

Abstract

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.

IPC Classes  ?

• G21F 9/30 - Processing
• C03B 5/00 - Melting in furnacesFurnaces so far as specially adapted for glass manufacture

Abstract

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.

IPC Classes  ?

• G21F 9/16 - Processing by fixation in stable solid media
• G01B 11/06 - Measuring arrangements characterised by the use of optical techniques for measuring length, width, or thickness for measuring thickness

Abstract

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.

IPC Classes  ?

• G21F 9/30 - Processing
• C03B 3/02 - Charging the melting furnaces combined with preheating, premelting or pretreating the glass-making ingredients, pellets or cullet
• C03B 5/00 - Melting in furnacesFurnaces so far as specially adapted for glass manufacture

Abstract

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.

IPC Classes  ?

• G01W 1/06 - Instruments for indicating weather conditions by measuring two or more variables, e.g. humidity, pressure, temperature, cloud cover or wind speed giving a combined indication of weather conditions
• G06F 30/20 - Design optimisation, verification or simulation

Abstract

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

IPC Classes  ?

• G06V 10/25 - Determination of region of interest [ROI] or a volume of interest [VOI]
• G06T 5/00 - Image enhancement or restoration
• G06T 5/20 - Image enhancement or restoration using local operators
• G06V 10/44 - Local feature extraction by analysis of parts of the pattern, e.g. by detecting edges, contours, loops, corners, strokes or intersectionsConnectivity analysis, e.g. of connected components
• G06V 10/764 - Arrangements for image or video recognition or understanding using pattern recognition or machine learning using classification, e.g. of video objects
• G06V 20/56 - Context or environment of the image exterior to a vehicle by using sensors mounted on the vehicle
• H04N 23/698 - Control of cameras or camera modules for achieving an enlarged field of view, e.g. panoramic image capture

Abstract

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

IPC Classes  ?

• G01N 21/88 - Investigating the presence of flaws, defects or contamination
• G06T 7/00 - Image analysis

Abstract

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

IPC Classes  ?

• G08B 29/18 - Prevention or correction of operating errors
• G08B 31/00 - Predictive alarm systems characterised by extrapolation or other computation using updated historic data
• G06N 20/00 - Machine learning
• G08B 21/18 - Status alarms
• G08B 29/20 - Calibration, including self-calibrating arrangements

Abstract

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

IPC Classes  ?

• G06F 40/211 - Syntactic parsing, e.g. based on context-free grammar [CFG] or unification grammars
• G06F 40/129 - Handling non-Latin characters, e.g. kana-to-kanji conversion
• G06F 40/268 - Morphological analysis

Abstract

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.

IPC Classes  ?

• G05B 13/04 - Adaptive control systems, i.e. systems automatically adjusting themselves to have a performance which is optimum according to some preassigned criterion electric involving the use of models or simulators
• G05B 23/02 - Electric testing or monitoring

Abstract

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.

IPC Classes  ?

• G05B 19/418 - Total factory control, i.e. centrally controlling a plurality of machines, e.g. direct or distributed numerical control [DNC], flexible manufacturing systems [FMS], integrated manufacturing systems [IMS] or computer integrated manufacturing [CIM]
• G05B 13/04 - Adaptive control systems, i.e. systems automatically adjusting themselves to have a performance which is optimum according to some preassigned criterion electric involving the use of models or simulators
• G05B 23/02 - Electric testing or monitoring

Abstract

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.

IPC Classes  ?

• G21C 9/012 - Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
• G21C 13/10 - Means for preventing contamination in event of leakage
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

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

IPC Classes  ?

• G06Q 50/06 - Energy or water supply
• G06Q 20/38 - Payment protocolsDetails thereof

Abstract

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

IPC Classes  ?

• G05B 23/02 - Electric testing or monitoring
• G06Q 50/06 - Energy or water supply
• G06Q 50/10 - Services
• G06Q 10/06 - Resources, workflows, human or project managementEnterprise or organisation planningEnterprise or organisation modelling

Abstract

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.

IPC Classes  ?

• G21F 9/06 - Processing
• G21F 9/00 - Treating radioactively contaminated materialDecontamination arrangements therefor

Abstract

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.

IPC Classes  ?

• C02F 1/32 - Treatment of water, waste water, or sewage by irradiation with ultraviolet light

Abstract

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.

IPC Classes  ?

• G21F 9/06 - Processing

Abstract

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

IPC Classes  ?

• C12N 1/12 - Unicellular algaeCulture media therefor
• C12M 1/00 - Apparatus for enzymology or microbiology

Abstract

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

IPC Classes  ?

• G05B 19/418 - Total factory control, i.e. centrally controlling a plurality of machines, e.g. direct or distributed numerical control [DNC], flexible manufacturing systems [FMS], integrated manufacturing systems [IMS] or computer integrated manufacturing [CIM]
• G21D 3/00 - Control of nuclear power plant
• F16K 31/04 - Operating meansReleasing devices electricOperating meansReleasing devices magnetic using a motor
• H01F 7/18 - Circuit arrangements for obtaining desired operating characteristics, e.g. for slow operation, for sequential energisation of windings, for high-speed energisation of windings
• H02P 1/04 - Means for controlling progress of starting sequence in dependence upon time or upon current, speed, or other motor parameter

Abstract

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

IPC Classes  ?

• G21F 5/012 - Fuel element racks in the containers
• G21F 5/12 - Closures for containersSealing arrangements
• G21F 5/14 - Devices for handling containers or shipping-casks, e.g. transporting devices

Abstract

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

IPC Classes  ?

• B23C 1/14 - Milling machines not designed for particular work or special operations with rotary work-carrying table
• G21F 5/008 - Containers for fuel elements

Abstract

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

IPC Classes  ?

• G06F 9/455 - EmulationInterpretationSoftware simulation, e.g. virtualisation or emulation of application or operating system execution engines
• G21D 3/00 - Control of nuclear power plant
• H04L 45/76 - Routing in software-defined topologies, e.g. routing between virtual machines
• H04L 49/60 - Software-defined switches
• H04L 45/74 - Address processing for routing
• H04L 41/122 - Discovery or management of network topologies of virtualised topologies e.g. software-defined networks [SDN] or network function virtualisation [NFV]
• H04L 12/46 - Interconnection of networks

Abstract

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

IPC Classes  ?

• G06F 30/20 - Design optimisation, verification or simulation
• G06Q 50/26 - Government or public services

Abstract

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

IPC Classes  ?

• G06N 3/08 - Learning methods

Abstract

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

IPC Classes  ?

• G21D 3/00 - Control of nuclear power plant
• G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core

Abstract

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

IPC Classes  ?

• B01F 27/90 - Mixers with rotary stirring devices in fixed receptaclesKneaders with stirrers rotating about a substantially vertical axis with paddles or arms
• C10L 1/32 - Liquid carbonaceous fuels consisting of coal-oil suspensions or aqueous emulsions
• B01F 27/70 - Mixers with rotary stirring devices in fixed receptaclesKneaders with stirrers rotating about a horizontal or inclined axis with paddles, blades or arms
• B01F 35/32 - Driving arrangements
• B01F 35/71 - Feed mechanisms
• B01F 25/50 - Circulation mixers, e.g. wherein at least part of the mixture is discharged from and reintroduced into a receptacle
• B01F 23/23 - Mixing gases with liquids by introducing gases into liquid media, e.g. for producing aerated liquids
• B01F 35/21 - Measuring
• B01F 35/214 - Measuring characterised by the means for measuring

Abstract

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.

IPC Classes  ?

• G01R 31/08 - Locating faults in cables, transmission lines, or networks
• H05B 3/56 - Heating cables

Abstract

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

IPC Classes  ?

• G21F 9/30 - Processing
• C03B 5/00 - Melting in furnacesFurnaces so far as specially adapted for glass manufacture

Abstract

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

IPC Classes  ?

• G01F 23/296 - Acoustic waves
• G01D 11/30 - Supports specially adapted for an instrumentSupports specially adapted for a set of instruments
• G21C 19/07 - Storage racksStorage pools

Abstract

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

IPC Classes  ?

• G01F 23/296 - Acoustic waves

Abstract

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

IPC Classes  ?

• C30B 29/22 - Complex oxides
• C30B 19/10 - Controlling or regulating

Abstract

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

IPC Classes  ?

• G21F 9/00 - Treating radioactively contaminated materialDecontamination arrangements therefor
• G21F 9/06 - Processing

Abstract

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.

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• G21D 3/06 - Safety arrangements responsive to faults within the plant

Abstract

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.

IPC Classes  ?

• G21C 9/004 - Pressure suppression
• G21C 9/02 - Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse
• G21D 3/06 - Safety arrangements responsive to faults within the plant

Abstract

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

IPC Classes  ?

• G21F 9/00 - Treating radioactively contaminated materialDecontamination arrangements therefor
• G21F 9/06 - Processing

Abstract

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

IPC Classes  ?

• G06N 20/00 - Machine learning

Abstract

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

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• G21C 15/243 - Promoting flow of the coolant for liquids

Abstract

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

IPC Classes  ?

• G06N 5/02 - Knowledge representationSymbolic representation

Abstract

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

IPC Classes  ?

• G21C 17/104 - Measuring reactivity

Abstract

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

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core

Abstract

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

IPC Classes  ?

• G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
• G21C 19/19 - Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
• G21C 19/34 - Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing

Abstract

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

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements

Abstract

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

IPC Classes  ?

• G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• G21D 3/06 - Safety arrangements responsive to faults within the plant

Abstract

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.

IPC Classes  ?

• G21D 3/04 - Safety arrangements
• G05B 23/02 - Electric testing or monitoring
• G06N 3/02 - Neural networks

Abstract

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.

IPC Classes  ?

• G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
• G21C 11/06 - Reflecting shields, i.e. for minimising loss of neutrons

Abstract

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.

IPC Classes  ?

• G21C 3/32 - Bundles of parallel pin-, rod-, or tube-shaped fuel elements
• G21C 11/06 - Reflecting shields, i.e. for minimising loss of neutrons

Abstract

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

IPC Classes  ?

• G21F 9/06 - Processing

Abstract

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

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• G21C 15/243 - Promoting flow of the coolant for liquids

Abstract

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.

IPC Classes  ?

• G21C 15/06 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements from fissile or breeder material in fuel elements
• G21C 1/32 - Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core

Abstract

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.

IPC Classes  ?

• G21D 3/04 - Safety arrangements
• G21D 3/00 - Control of nuclear power plant
• G06F 30/20 - Design optimisation, verification or simulation

Abstract

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

IPC Classes  ?

• G21D 1/00 - Details of nuclear power plant
• B28D 1/22 - Working stone or stone-like materials, e.g. brick, concrete, not provided for elsewhereMachines, devices, tools therefor by cutting, e.g. incising
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

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

IPC Classes  ?

• G21F 9/00 - Treating radioactively contaminated materialDecontamination arrangements therefor

Abstract

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

IPC Classes  ?

• G21D 1/00 - Details of nuclear power plant
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• B28D 1/22 - Working stone or stone-like materials, e.g. brick, concrete, not provided for elsewhereMachines, devices, tools therefor by cutting, e.g. incising

Abstract

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

IPC Classes  ?

• G21F 9/00 - Treating radioactively contaminated materialDecontamination arrangements therefor

Abstract

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

IPC Classes  ?

• G21D 1/00 - Details of nuclear power plant
• G21F 1/02 - Selection of uniform shielding materials

Abstract

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

IPC Classes  ?

• G21D 1/00 - Details of nuclear power plant
• G21C 9/04 - Means for suppressing fires
• A62C 35/10 - Containers destroyed or opened by flames or heat

Abstract

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

IPC Classes  ?

• G21F 9/30 - Processing
• C03C 8/02 - Frit compositions, i.e. in a powdered or comminuted form

Abstract

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

IPC Classes  ?

• G21F 9/30 - Processing
• G21F 5/005 - Containers for solid radioactive wastes, e.g. for ultimate disposal
• G21F 5/10 - Heat-removal systems, e.g. using circulating fluid or cooling fins

Abstract

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

IPC Classes  ?

• G01T 1/16 - Measuring radiation intensity
• G01T 1/29 - Measurement performed on radiation beams, e.g. position or section of the beamMeasurement of spatial distribution of radiation

Abstract

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

IPC Classes  ?

• G21D 3/00 - Control of nuclear power plant
• G21D 3/04 - Safety arrangements
• G06Q 10/04 - Forecasting or optimisation specially adapted for administrative or management purposes, e.g. linear programming or "cutting stock problem"

Abstract

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

IPC Classes  ?

• C04B 18/06 - Combustion residues, e.g. purification products of smoke, fumes or exhaust gases
• C04B 20/00 - Use of materials as fillers for mortars, concrete or artificial stone according to more than one of groups and characterised by shape or grain distributionTreatment of materials according to more than one of the groups specially adapted to enhance their filling properties in mortars, concrete or artificial stoneExpanding or defibrillating materials
• C04B 40/02 - Selection of the hardening environment
• C04B 28/02 - Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
• B28B 11/24 - Apparatus or processes for treating or working the shaped articles for curing, setting or hardening

Abstract

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

IPC Classes  ?

• A01K 61/73 - Artificial fishing banks or reefs assembled from components
• A01K 61/78 - Arrangements for sinking or mooring thereof
• E02B 3/04 - Structures or apparatus for, or methods of, protecting banks, coasts, or harbours

Abstract

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

IPC Classes  ?

• G21D 3/04 - Safety arrangements