CN117747157A - Nuclear reactor data correction method, device, computer equipment and storage medium - Google Patents
Nuclear reactor data correction method, device, computer equipment and storage medium Download PDFInfo
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Abstract
The application relates to a data correction method, a data correction device, computer equipment and a storage medium of a nuclear reactor. The method comprises the following steps: acquiring calibration core data of a reactor of a nuclear power plant at a calibration time; the calibration time refers to the time of calibrating the detector in the reactor; acquiring real-time core data obtained by monitoring a reactor by using a detector; carrying out thermodynamic and hydraulic calculation on the reactor based on the real-time reactor core data to obtain the estimated deviation nucleate boiling ratio of the reactor; correcting the estimated deviation nucleate boiling ratio according to the core data deviation between the real-time core data and the corrected core data to obtain a corrected deviation nucleate boiling ratio; the correction of the deviation from the nucleate boiling ratio is used for protection control of the reactor. By adopting the method, the precision of the reactor protection control can be improved.
Description
Technical Field
The present invention relates to the field of data processing technologies, and in particular, to a method and apparatus for correcting data of a nuclear reactor, a computer device, and a storage medium.
Background
In the nuclear power field, in order to ensure the safety of a reactor in a nuclear power plant, the reactor in the nuclear power plant needs to be monitored in real time, whether protection control is performed on the reactor is determined according to monitoring data, for example, when the reactor is monitored to deviate from nuclear boiling, shutdown protection operation is performed.
In the conventional technology, the deviated nucleate boiling ratio of the reactor is generally determined based on the core data monitored in real time by an in-reactor Self-powered neutron detector (SPND, self-Powered Neutron Detector) and the thermodynamic and hydraulic parameters monitored in real time, so that whether to perform protection control on the reactor is determined according to the deviated nucleate boiling ratio.
However, since the SPND is usually calibrated by a periodic calibration method, and the reactor core state of the reactor is continuously changed, the deviation nucleate boiling ratio calculated by the conventional method is not accurate enough due to the deviation between the real-time reactor core state and the reactor core state at the calibration time, resulting in lower precision of the reactor protection control.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a data correction method, apparatus, computer device, computer-readable storage medium, and computer program product for a nuclear reactor that can improve the accuracy of reactor protection control.
In a first aspect, the present application provides a method of data modification for a nuclear reactor. The method comprises the following steps: acquiring calibration core data of a reactor of a nuclear power plant at a calibration time; the calibration time refers to the time of calibrating the detector in the reactor; acquiring real-time core data obtained by monitoring the reactor by using the detector; performing thermodynamic and hydraulic calculations on the reactor based on the real-time core data to obtain an estimated deviation nucleate boiling ratio of the reactor; correcting the estimated deviation nucleate boiling ratio according to the core data deviation between the real-time core data and the calibration core data to obtain a corrected deviation nucleate boiling ratio; the correction deviates from the nucleate boiling ratio for protection control of the reactor.
In a second aspect, the present application also provides a data correction device for a nuclear reactor. The device comprises: the calibration data acquisition module is used for acquiring calibration core data of a reactor of the nuclear power plant at a calibration time; the calibration time refers to the time of calibrating the detector in the reactor; the real-time data acquisition module is used for acquiring real-time reactor core data obtained by monitoring the reactor by using the detector; the thermodynamic hydraulic calculation module is used for carrying out thermodynamic hydraulic calculation on the reactor based on the real-time reactor core data to obtain an estimated deviation nucleate boiling ratio of the reactor; the correction module is used for correcting the estimated deviation nucleate boiling ratio according to the core data deviation between the real-time core data and the corrected core data to obtain a corrected deviation nucleate boiling ratio; the correction deviates from the nucleate boiling ratio for protection control of the reactor.
In some embodiments, the correction module is further to: determining a target deviation function representing a relationship between a deviation from a nucleate boiling ratio deviation and the core data deviation; the deviation from the nucleate boiling ratio deviation is a deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio; substituting the core data deviation into the target deviation function to obtain a deviation from a nucleate boiling ratio deviation; determining the modified off-nucleate boiling ratio based on the estimated off-nucleate boiling ratio deviation from the off-nucleate boiling ratio.
In some embodiments, the data correction device of a nuclear reactor further comprises a function determination module for: acquiring corresponding actual deviation nucleate boiling ratios and reactor core data of the reactor in a plurality of reactor core running states through a design program; the core operating state includes a normal operating state and an accident operating state; for each reactor core operation state, performing thermodynamic and hydraulic calculation according to reactor core data corresponding to the reactor core operation state, and determining an estimated deviation nucleate boiling ratio corresponding to the reactor core operation state; determining deviation from a nucleate boiling ratio deviation corresponding to the core operating condition according to the estimated deviation from a nucleate boiling ratio and the actual deviation from a nucleate boiling ratio corresponding to the core operating condition; determining core data deviation existing between each core operation state and the core operation state at the calibration time; and performing function fitting according to the deviation nucleate boiling ratio deviation and the core data deviation corresponding to each core operation state to obtain the target deviation function.
In some embodiments, the real-time core data includes real-time hot aisle data; the real-time data acquisition module is further configured to: determining corresponding calibration parameters of the detector at the calibration time; acquiring a current signal of the detector; performing power reconstruction based on the calibration parameters and the current signals to obtain core power distribution of the reactor; reconstructing thermal channel data based on the reactor core power distribution to obtain the real-time thermal channel data; the correction module is further configured to: determining the core data bias based on a bias between the real-time hot aisle data and the calibrated hot aisle data; and correcting the estimated off-nucleate boiling ratio according to the core data deviation to obtain a corrected off-nucleate boiling ratio.
In some embodiments, the real-time core data further includes a real-time status parameter; the boiling estimation module is further configured to: and performing thermodynamic and hydraulic calculation on the reactor according to the reactor core power distribution and the real-time state parameter to obtain the estimated deviation nucleate boiling ratio of the reactor.
In some embodiments, the real-time status parameters include coolant inlet temperature, coolant flow, and pressurizer pressure; the thermodynamic hydraulic power calculation module is also used for: determining a critical heat flux density of the reactor based on the coolant inlet temperature, coolant flow and pressurizer pressure; determining the local heat flux density of the reactor core according to the ratio between the power distribution of the reactor core and the heating circumference; the estimated departure from the nucleate boiling ratio is determined based on a ratio between the core local heat flux density and the critical heat flux density.
In some embodiments, after obtaining the corrected off-nucleate boiling ratio, the data correction device of the nuclear reactor further comprises a control protection module for: comparing the corrected off-nucleate boiling ratio with a preset threshold corresponding to the reactor; and performing shutdown protection on the reactor in the condition that the modified deviation nucleate boiling ratio is smaller than the preset threshold value.
In a third aspect, the present application also provides a computer device. The computer device includes a memory storing a computer program and a processor that when executing the computer program performs the steps of the data correction method for a nuclear reactor described above.
In a fourth aspect, the present application also provides a computer-readable storage medium. The computer readable storage medium has stored thereon a computer program which, when executed by a processor, performs the steps in the data correction method of a nuclear reactor described above.
In a fifth aspect, the present application also provides a computer program product. The computer program product comprises a computer program which, when executed by a processor, implements the steps of the data correction method of a nuclear reactor described above.
According to the data correction method, the device, the computer equipment, the storage medium and the computer program product of the nuclear reactor, the correction core data of the reactor of the nuclear power plant at the correction time and the real-time core data obtained by monitoring the reactor by using the detector are obtained, then the thermal hydraulic calculation is carried out on the reactor based on the real-time core data to obtain the estimated deviation nucleate boiling ratio of the reactor, the real-time correction is carried out on the estimated deviation nucleate boiling ratio according to the core data deviation between the real-time core data and the correction core data, unnecessary excessive conservative assumption is reduced, the calculation of the deviation nucleate boiling ratio is more accurate, and the correction deviation nucleate boiling ratio is used for carrying out protection control on the reactor, so that the accuracy of the protection control of the reactor is improved.
Drawings
FIG. 1 is an application environment diagram of a data modification method for a nuclear reactor in one embodiment;
FIG. 2 is a flow diagram of a method of data modification of a nuclear reactor in one embodiment;
FIG. 3 is a flow chart of fitting an objective deviation function in one embodiment;
FIG. 4 is a block diagram of a data modification device of a nuclear reactor in one embodiment;
FIG. 5 is an internal block diagram of a computer device in one embodiment;
fig. 6 is an internal structural view of a computer device in another embodiment.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application will be further described in detail with reference to the accompanying drawings and examples. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the present application.
The data correction method of the nuclear reactor provided by the embodiment of the application can be applied to an application environment shown in fig. 1. The application environment includes a terminal 102 and a server 104, wherein the terminal 102 communicates with the server 104 over a network. The data storage system may store data that the server 104 needs to process. The data storage system may be integrated on the server 104 or may be located on a cloud or other network server.
Specifically, taking the example that the method is applied to the server 104, the server 104 acquires the calibration core data of the reactor of the nuclear power plant at the calibration time; the calibration time refers to the time of calibrating the detector in the reactor; the server 104 acquires real-time core data obtained by monitoring the reactor by using the detector; the server 104 performs a thermodynamic calculation on the reactor based on the real-time core data to obtain an estimated deviation nucleate boiling ratio of the reactor; the server 104 corrects the estimated off-nucleate boiling ratio according to the core data deviation between the real-time core data and the calibration core data to obtain a corrected off-nucleate boiling ratio; the correction of the deviation from the nucleate boiling ratio is used for protection control of the reactor. For example, the server 104 generates a shutdown protection command for the reactor and sends the shutdown protection command to the terminal 102. The terminal 102 performs shutdown protection on the reactor in accordance with the shutdown protection command.
The terminal 102 may be, but is not limited to, various personal computers, notebook computers, smart phones, tablet computers, and internet of things devices. The server 104 may be implemented as a stand-alone server or as a server cluster of multiple servers.
Those skilled in the art will appreciate that the application environment shown in fig. 1 is only a partial scenario related to the present application scenario, and does not constitute a limitation on the application environment of the present application scenario.
In some embodiments, as shown in fig. 2, a method for modifying data of a nuclear reactor is provided, which may be executed by a terminal or a server, and may also be executed by the terminal and the server together, where the method is applied to the server 104 in fig. 1, and is illustrated as an example, and includes the following steps:
step 202, obtaining calibration core data of a reactor of a nuclear power plant at a calibration time; the calibration time refers to the time when the detector in the reactor is calibrated.
A reactor, also called a nuclear reactor or a nuclear power reactor, is a device capable of maintaining a controllable self-sustaining chain-type nuclear fission reaction to achieve nuclear power utilization, for example, in a nuclear power plant, the reactor is used for power generation. In a nuclear power plant, to ensure the safety of the core active region of the reactor, for example, to prevent safety accidents due to melting of fuel cell assembly pellets and failure of cladding due to nucleate boiling (DNB) occurring, the reactor is typically monitored in real time by detectors in the reactor. The detector may be a Self-powered neutron detector (SPND, self-Powered Neutron Detector). Since the signal transmitted by the detector is a current signal, the detector needs to be calibrated periodically by a field person, for example, the detector can be calibrated at month 1. The calibration is to calibrate the data obtained by the detector. The calibration time refers to the time when the detector in the reactor is calibrated.
Specifically, there may be a plurality of calibration times, the server stores core data corresponding to each of the reactor at each of the calibration times, and the server may determine the core data corresponding to the latest calibration time as the calibration core data.
And step 204, acquiring real-time reactor core data obtained by monitoring the reactor by using the detector.
The reactor core data refers to relevant data of a reactor core active area in a reactor, and the relevant data comprise hot channel data and state parameters. The fuel assembly of the reactor comprises a plurality of fuel rods, a hot channel refers to a channel where the fuel rod with the highest power is located, and hot channel data refers to data related to the hot channel, wherein the data comprises at least one of a hot channel enthalpy rise factor, a hot channel position or a hot channel axial power offset; the state parameter may also be referred to as a thermodynamic and hydraulic parameter, including at least one of coolant inlet temperature, coolant flow, or pressure of the pressurizer. The real-time core data is core data obtained by monitoring the reactor by using a detector in real time.
Specifically, the detector monitors the reactor in real time and sends a monitoring signal to the server. The server may receive the monitoring signals from the detectors and determine real-time core data based on the monitoring signals.
In some embodiments, the real-time core data includes real-time status parameters, which may be directly acquired, and real-time hot aisle data, which needs to be reconstructed from the current signals of the detectors. The server can reconstruct the power of the current signal to obtain the core power distribution of the reactor. And then the server carries out hot channel data reconstruction according to the reactor core power distribution to obtain real-time hot channel data. The reactor core power distribution refers to the distribution condition of the linear power density corresponding to each fuel rod in the reactor.
And 206, performing thermal hydraulic calculation on the reactor based on the real-time reactor core data to obtain the estimated deviation nucleate boiling ratio of the reactor.
Wherein the deviation nucleate boiling ratio characterizes the boiling state or the boiling degree of the reactor, the deviation nucleate boiling ratio and the boiling degree of the reactor are in negative correlation, and the smaller the deviation nucleate boiling ratio is, the higher the boiling degree of the reactor is, and the higher the reactor core power of the reactor is. In practice, the deviation from the nucleate boiling ratio refers to the ratio between the critical heat flux density and the local heat flux density.
Specifically, the server calculates critical heat flow density according to the heat transfer principle and the real-time state parameter. And then the server can obtain the linear power density corresponding to each node in the reactor according to the reactor core power distribution, and calculate the ratio between the linear power density and the heating circumference corresponding to each node to obtain the local heat flux density of the reactor core. The server may determine a ratio between the core critical heat flux density and the local heat flux density as an estimated off-nucleate boiling ratio.
Step 208, correcting the estimated off-nucleate boiling ratio according to the core data deviation between the real-time core data and the calibration core data to obtain a corrected off-nucleate boiling ratio; the correction of the deviation from the nucleate boiling ratio is used for protection control of the reactor.
The core data deviation refers to a deviation between real-time core data and calibration core data, and specifically may include a thermal channel data deviation and a state parameter deviation.
Specifically, the server calculates a core data deviation between the real-time core data and the calibration core data, determines a target deviation function indicating a relationship between the deviated nucleate boiling ratio deviation and the core data deviation, and then substitutes the core data deviation into the target deviation function to calculate, thereby obtaining the deviated nucleate boiling ratio deviation. The server corrects the estimated off-nucleate boiling ratio based on the off-nucleate boiling ratio deviation to obtain a corrected off-nucleate boiling ratio. The target deviation function may be determined based on the actual off-nucleate boiling ratio and core data corresponding to the reactor under various core operating conditions, and the core data at the moment of calibration. The deviation from the nucleate boiling ratio deviation is a deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio. The actual off-nucleate boiling ratio is the actual off-nucleate boiling ratio that corresponds to the theoretical reactor.
According to the data correction method of the nuclear reactor, the correction core data of the reactor of the nuclear power plant at the correction time and the real-time core data obtained by monitoring the reactor by using the detector are obtained, then the thermodynamic calculation is carried out on the reactor based on the real-time core data to obtain the estimated off-nucleate boiling ratio of the reactor, the real-time correction is carried out on the estimated off-nucleate boiling ratio according to the core data deviation between the real-time core data and the correction core data, unnecessary excessive conservation assumption is reduced, the calculation of the off-nucleate boiling ratio is more accurate, and the correction off-nucleate boiling ratio is used for protecting and controlling the reactor, so that the accuracy of protecting and controlling the reactor is improved.
In some embodiments, step 408, correcting the estimated off-nucleate boiling ratio based on the core data bias between the real-time core data and the calibrated core data to obtain a corrected off-nucleate boiling ratio, comprises: determining a target deviation function representing a relationship between the deviation from the nucleate boiling ratio deviation and the core data deviation; the deviation from the nucleate boiling ratio deviation is a deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio; substituting the core data deviation into a target deviation function to obtain a deviation from a nucleate boiling ratio deviation; a modified off-nucleate boiling ratio is determined based on the estimated off-nucleate boiling ratio and the off-nucleate boiling ratio deviation.
Specifically, the server acquires a target deviation function fitted from core data in a large number of different core operating states, wherein the dependent variable in the target deviation function is a deviation from a nucleate boiling ratio, and the independent variable is a core data deviation. The server may calculate the core data bias by substituting it into the target bias function to obtain a biased nucleate boiling ratio bias, and then determine a corrected biased nucleate boiling ratio using the estimated biased nucleate boiling ratio and the biased nucleate boiling ratio bias.
In some embodiments, the server may sum the estimated off-nucleate boiling ratio with the off-nucleate boiling ratio deviation to obtain a corrected off-nucleate boiling ratio. The corrected off-nucleate boiling ratio can be expressed as follows:
；
wherein,indicating a correction of the deviation from the nucleate boiling ratio +.>Indicating an estimated deviation from the nucleate boiling ratio.Indicating deviation from nucleate boiling ratioAll belong to core data deviation +.>Is to correct for the deviation between the coolant inlet temperature and the real-time coolant inlet temperature; />Correcting deviation between the pressure of the voltage stabilizer and the pressure of the real-time voltage stabilizer; />Is to correct the deviation between the coolant flow and the real-time coolant flow; />The method is to correct the deviation between the enthalpy rise factor of the heat channel and the enthalpy rise factor of the real-time channel; / >The deviation between the position of the etching heat channel and the position of the real-time heat channel is corrected;is the deviation between the axial power offset of the calibration heat channel and the axial power offset of the real-time heat channel.
In this embodiment, the target deviation function may represent a relationship between the deviated nucleate boiling ratio and the core data deviation, so that the core data deviation may be directly substituted into the target deviation function to obtain the deviated nucleate boiling ratio deviation, and real-time correction of the data is implemented based on the deviated nucleate boiling ratio deviation, so that the corrected deviation nucleate boiling ratio is more accurate.
In some embodiments, determining an objective deviation function that represents a relationship between the deviation from the nucleate boiling ratio deviation and the core data deviation includes: acquiring the actual deviation nucleate boiling ratio and core data corresponding to the reactor in a plurality of core operating states; for each reactor core running state, performing thermodynamic and hydraulic calculation according to reactor core data corresponding to the reactor core running state, and determining an estimated deviation nucleate boiling ratio corresponding to the reactor core running state; determining deviation from the nucleate boiling ratio deviation corresponding to the core operating state according to the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio corresponding to the core operating state; determining core data deviation existing between each core operation state and the core operation state at the calibration time; and performing function fitting according to the deviation nucleate boiling ratio deviation and the core data deviation corresponding to each core operation state to obtain a target deviation function.
The design program is used for simulating the working condition of the reactor, and the plurality of core operation states are preset through the design program, and for example, the normal working condition state and the accident working condition state can be included, wherein the normal working condition state refers to the core state of the normal working condition, and the accident working condition state refers to the core state of the accident working condition. The actual off-nucleate boiling ratio is the actual off-nucleate boiling ratio of the reactor in the core operating state, and may be obtained by simulation through a design program.
Specifically, the server may obtain actual deviation nucleate boiling ratio and core data corresponding to each core operation state of the reactor from the locally stored data of a plurality of core operation states, and obtain core data at the moment of calibration, where the data of each core operation state is generated by performing reactor working condition simulation through a design program. For each core operating state, the server may perform a thermodynamic calculation based on thermodynamic and hydraulic parameters in core data corresponding to the core operating state to obtain an estimated off-nucleate boiling ratio corresponding to the core operating state, and determine a deviation between the estimated off-nucleate boiling ratio and the actual off-nucleate boiling ratio corresponding to the core operating state as an off-nucleate boiling ratio deviation corresponding to the core operating state. The server may also determine a calibration time corresponding to the core operation state, so as to determine a deviation between the core data corresponding to the core operation state and the calibration core data at the calibration time as a core data deviation between the core operation state and the core operation state at the calibration time.
In some embodiments, as shown in fig. 3, a flow chart of a target deviation function fit is illustrated, and the terminal may simulate core operation states under normal or accident conditions of the reactor by using a core design program, so as to obtain core data and theoretical deviation nucleate boiling ratios under each simulated core operation state. The terminal can also simulate the core operation state at the calibration time by using a core design program to obtain simulated calibration parameters and calibration core data, so that the terminal can obtain state parameter deviation, hot channel deviation and deviation nucleate boiling ratio deviation based on the core data and theoretical deviation nucleate boiling ratio, simulated calibration parameters and calibration core data under each simulated core operation state, and fit a target deviation function based on the state parameter deviation, the hot channel deviation and the deviation nucleate boiling ratio deviation.
In the embodiment, function fitting is performed based on the deviation nucleate boiling ratio deviation and the core data deviation corresponding to each core operation state, so that a target deviation function for calculating the deviation nucleate boiling ratio deviation in real time is obtained, in the actual correction process, only the coefficient of a correction term in the function is required to be adjusted when uncertainty is adjusted, other constant value data are not influenced, and the safety of a protection control system is improved.
In some embodiments, the real-time core data includes real-time hot aisle data; step 204, obtaining real-time core data obtained by monitoring the reactor with the detector, including: determining corresponding calibration parameters of the detector at the calibration time; acquiring a current signal of a detector; performing power reconstruction based on the calibration parameters and the current signals to obtain reactor core power distribution of the reactor; reconstructing thermal channel data based on reactor core power distribution to obtain real-time thermal channel data; correcting the estimated off-nucleate boiling ratio according to the core data deviation between the real-time core data and the calibration core data to obtain a corrected off-nucleate boiling ratio, comprising: determining core data bias based on the bias between the real-time hot aisle data and the calibrated hot aisle data; and correcting the estimated off-nucleate boiling ratio according to the core data deviation to obtain a corrected off-nucleate boiling ratio.
The calibration parameters are determined based on monitoring signals of the detector at the calibration time. The deviation between the real-time thermal channel data and the calibration thermal channel data is thermal channel data deviation, and the thermal channel data deviation and the deviation nucleate boiling ratio deviation are in positive correlation.
Specifically, the real-time hot aisle data includes a real-time hot aisle position, a real-time hot aisle enthalpy rise factor, and a real-time hot aisle axial power offset. The server can determine the channel where the fuel rod with the maximum linear power density is located as a real-time heat channel according to the reactor core power distribution, and determine the position of the real-time heat channel in the reactor to obtain the position of the real-time heat channel. The server can also calculate integral power based on the linear power density corresponding to the thermal channel to obtain a real-time thermal channel enthalpy rise factor, and the upper half integral power subtracted by the lower half integral power divided by the total integral power calculated based on the linear power density of the thermal channel is used to obtain real-time thermal channel axial power offset.
In some embodiments, the calibration parameters include a calibration current signal and a thermal channel line power density. Technicians in the nuclear power plant site can regularly perform calibration on the detector, for example, calibration is performed once a month, and a calibration current signal of the detector at the calibration time is obtained. The terminal may utilize nuclear design software to simulate the core state of the reactor to obtain the thermal channel linear power density of all fuel assemblies of the core. The terminal takes the heat channel linear power density and the calibration current signal as calibration parameters, and sends the calibration time and the corresponding calibration parameters to the server.
In some embodiments, the server may utilize the principle that current is proportional to power to reconstruct power based on the calibration parameters and the current signal to obtain the core power distribution of the reactor. For example, the calibration parameters include a hot aisle line power Pcalib (i, j) and a calibration current signal Icalib (i, j), the real-time current signal of the detector is Imes (i, j), the core power distribution can be expressed as Pmes (i, j), and the formula of power reconstruction is as follows:
Pmes(i,j)=Pcalib(i,j)×Imes(i,j)/Icalib(i,j)；
where (i, j) represents the location of the node in the reactor.
In this embodiment, since the hot aisle is changed according to the reactor core state change of the reactor, and the hot aisle data cannot be directly obtained, the reactor core power distribution is obtained by performing power reconstruction based on the calibration parameters and the current signals, and the real-time hot aisle data is reconstructed according to the reactor core power distribution, so that the reactor core data deviation is determined based on the deviation between the real-time hot aisle data and the calibration hot aisle data, and the real-time data correction is realized.
In some embodiments, the real-time core data further includes real-time status parameters; step 206, performing a thermodynamic and hydraulic calculation on the reactor based on the real-time core data to obtain an estimated deviation from a nucleate boiling ratio of the reactor, including: and performing thermal hydraulic calculation on the reactor according to the reactor core power distribution and the real-time state parameters to obtain the estimated deviation nucleate boiling ratio of the reactor.
Specifically, it is understood that the real-time core data includes real-time state parameters and real-time hot aisle data, and the real-time state parameters can be used for performing a thermodynamic calculation to obtain an estimated off-nucleate boiling ratio, and can also participate in correction of the off-nucleate boiling ratio, i.e., the core data deviation includes a state parameter deviation.
In the embodiment, the real-time calculation of the deviation nucleate boiling ratio is realized by carrying out the thermodynamic calculation on the reactor according to the reactor core power distribution and the real-time state parameter.
In some embodiments, the real-time core data includes coolant inlet temperature, coolant flow, and pressurizer pressure; carrying out thermal hydraulic calculation on the reactor according to the reactor core power distribution and the real-time state parameters to obtain the estimated deviation nucleate boiling ratio of the reactor, wherein the method comprises the following steps: determining a critical heat flux density of the reactor based on the coolant inlet temperature, the coolant flow and the pressurizer pressure; determining the local heat flux density of the reactor core according to the ratio between the reactor core power distribution and the heating circumference; an estimated off-nucleate boiling ratio is determined based on a ratio between the core critical heat flux density and the local heat flux density.
Specifically, the server calculates the enthalpy, the flow rate and the gas content of local fluid in the reactor according to the core inlet temperature, the core inlet flow rate, the pressure of the pressure stabilizer and the heat transfer principle, and then substitutes the enthalpy, the flow rate and the gas content of the local fluid into a preset fitting relation to calculate the critical heat flow density. The preset fitting relation is obtained by fitting the enthalpy value, the flow rate, the gas content and the critical heat flow density of the local fluid obtained through the test. The server obtains heating circumferences corresponding to all nodes in the reactor, determines linear power density corresponding to each node, and determines the ratio between the linear power density and the heating circumferences as the core local heat flow density corresponding to the node. The server may determine a ratio between the core critical heat flux density and the local heat flux density as an estimated off-nucleate boiling ratio.
In the embodiment, by determining the critical heat flux density and the core local heat flux density and determining the estimated deviation from the nucleate boiling ratio based on the ratio between the core local heat flux density and the critical heat flux density, the real-time estimation of the boiling state is realized.
In some embodiments, after obtaining the corrected off-nucleate boiling ratio, the method of data correction for a nuclear reactor further comprises: comparing the corrected deviation nucleate boiling ratio with a preset threshold corresponding to the reactor; and performing shutdown protection on the reactor under the condition that the corrected deviation nucleate boiling ratio is smaller than a preset threshold value.
The preset threshold is a preset value, and specifically may be any value between 1 and 10. Shutdown protection refers to controlling the operation of stopping the reactor to prevent safety accidents caused by boiling of the reactor.
Specifically, the server may compare the corrected deviated nucleate boiling ratio with a preset threshold, and determine that nucleate boiling does not occur in the reactor without performing protection control in the case where the corrected deviated nucleate boiling ratio is greater than or equal to the preset threshold; when the corrected deviation nucleate boiling ratio is smaller than a preset threshold value, it can be determined that nucleate boiling of the reactor currently occurs, and at the moment, the reactor core power of the reactor is too high, and shutdown protection is needed. The server may generate a shutdown protection command for the reactor and send the shutdown protection command to the terminal. And the terminal receives a shutdown protection instruction sent by the server, and controls the reactor to execute shutdown protection according to the shutdown protection instruction.
In this embodiment, since the correction deviation nucleate boiling ratio is more accurate than the data before correction, by comparing the correction deviation nucleate boiling ratio with the preset threshold, shutdown protection is performed under the condition that the correction deviation nucleate boiling ratio is smaller than the preset threshold, more accurate reactor protection control is realized, and the operation safety of the nuclear power plant can be improved.
It should be understood that, although the steps in the flowcharts related to the above embodiments are sequentially shown as indicated by arrows, these steps are not necessarily sequentially performed in the order indicated by the arrows. The steps are not strictly limited to the order of execution unless explicitly recited herein, and the steps may be executed in other orders. Moreover, at least some of the steps in the flowcharts described in the above embodiments may include a plurality of steps or a plurality of stages, which are not necessarily performed at the same time, but may be performed at different times, and the order of the steps or stages is not necessarily performed sequentially, but may be performed alternately or alternately with at least some of the other steps or stages.
Based on the same inventive concept, the embodiment of the application also provides a data correction device of the nuclear reactor for realizing the data correction method of the nuclear reactor. The implementation of the solution provided by the device is similar to the implementation described in the above method, so the specific limitations in the embodiments of the data correction device for one or more nuclear reactors provided below may be referred to the above limitations of the data correction method for a nuclear reactor, and will not be repeated here.
In some embodiments, as shown in fig. 4, there is provided a data correction device of a nuclear reactor, including: a calibration data acquisition module 402, a real-time data acquisition module 404, a boiling estimation module 406, and a correction module 408, wherein:
a calibration data acquisition module 402, configured to acquire calibration core data of a reactor of a nuclear power plant at a calibration time; the calibration time refers to the time when the detector in the reactor is calibrated.
The real-time data acquisition module 404 is configured to acquire real-time core data obtained by monitoring the reactor with the detector.
The boiling estimation module 406 is configured to perform a thermodynamic calculation on the reactor based on the real-time core data to obtain an estimated deviation from the nucleate boiling ratio of the reactor.
A correction module 408 for correcting the estimated off-nucleate boiling ratio according to the core data deviation between the real-time core data and the calibration core data to obtain a corrected off-nucleate boiling ratio; the correction of the deviation from the nucleate boiling ratio is used for protection control of the reactor.
In some embodiments, the correction module 408 is further configured to: determining a target deviation function representing a relationship between the deviation from the nucleate boiling ratio deviation and the core data deviation; the deviation from the nucleate boiling ratio deviation is a deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio; substituting the core data deviation into a target deviation function to obtain a deviation from a nucleate boiling ratio deviation; a modified off-nucleate boiling ratio is determined based on the estimated off-nucleate boiling ratio and the off-nucleate boiling ratio deviation.
In some embodiments, the data correction device of the nuclear reactor further comprises a function determination module for: acquiring corresponding actual deviation nucleate boiling ratios and core data of the reactor in a plurality of core operating states through a design program; for each reactor core running state, performing thermodynamic and hydraulic calculation according to reactor core data corresponding to the reactor core running state, and determining an estimated deviation nucleate boiling ratio corresponding to the reactor core running state; determining deviation from the nucleate boiling ratio deviation corresponding to the core operating state according to the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio corresponding to the core operating state; determining core data deviation existing between each core operation state and the core operation state at the calibration time; and performing function fitting according to the deviation nucleate boiling ratio deviation and the core data deviation corresponding to each core operation state to obtain a target deviation function.
In some embodiments, the real-time core data includes real-time hot aisle data; the real-time data acquisition module 404 is further configured to: determining corresponding calibration parameters of the detector at the calibration time; acquiring a current signal of a detector; performing power reconstruction based on the calibration parameters and the current signals to obtain reactor core power distribution of the reactor; reconstructing thermal channel data based on reactor core power distribution to obtain real-time thermal channel data; the correction module 408 is also configured to: determining core data bias based on the bias between the real-time hot aisle data and the calibrated hot aisle data; and correcting the estimated off-nucleate boiling ratio according to the core data deviation to obtain a corrected off-nucleate boiling ratio.
In some embodiments, the real-time core data further includes real-time status parameters; the boiling estimation module 406 is also configured to: and performing thermal hydraulic calculation on the reactor according to the reactor core power distribution and the real-time state parameters to obtain the estimated deviation nucleate boiling ratio of the reactor.
In some embodiments, the real-time core data includes coolant inlet temperature, coolant flow, and pressurizer pressure; the boiling estimation module 406 is also configured to: determining a critical heat flux density of the reactor based on the coolant inlet temperature, the coolant flow and the pressurizer pressure; determining the local heat flux density of the reactor core according to the ratio between the reactor core power distribution and the heating circumference; an estimated off-nucleate boiling ratio is determined based on a ratio between the core local heat flux density and the critical heat flux density.
In some embodiments, after obtaining the corrected off-nucleate boiling ratio, the data correction device of the nuclear reactor further comprises a control including module for controlling the protection module to: comparing the corrected deviation nucleate boiling ratio with a preset threshold corresponding to the reactor; and performing shutdown protection on the reactor under the condition that the corrected deviation nucleate boiling ratio is smaller than a preset threshold value.
The respective modules in the data correction device of the nuclear reactor described above may be implemented in whole or in part by software, hardware, or a combination thereof. The above modules may be embedded in hardware or may be independent of a processor in the computer device, or may be stored in software in a memory in the computer device, so that the processor may call and execute operations corresponding to the above modules.
In some embodiments, a computer device is provided, which may be a server, the internal structure of which may be as shown in fig. 5. The computer device includes a processor, a memory, an Input/Output interface (I/O) and a communication interface. The processor, the memory and the input/output interface are connected through a system bus, and the communication interface is connected to the system bus through the input/output interface. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer programs, and a database. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The database of the computer device is used for storing relevant data related to a data correction method of the nuclear reactor. The input/output interface of the computer device is used to exchange information between the processor and the external device. The communication interface of the computer device is used for communicating with an external terminal through a network connection. The computer program, when executed by a processor, implements a method of data correction for a nuclear reactor.
In some embodiments, a computer device is provided, which may be a terminal, and the internal structure of which may be as shown in fig. 6. The computer device includes a processor, a memory, an input/output interface, a communication interface, a display unit, and an input means. The processor, the memory and the input/output interface are connected through a system bus, and the communication interface, the display unit and the input device are connected to the system bus through the input/output interface. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The input/output interface of the computer device is used to exchange information between the processor and the external device. The communication interface of the computer device is used for carrying out wired or wireless communication with an external terminal, and the wireless mode can be realized through WIFI, a mobile cellular network, NFC (near field communication) or other technologies. The computer program, when executed by a processor, implements a method of data correction for a nuclear reactor. The display unit of the computer device is used for forming a visual picture, and can be a display screen, a projection device or a virtual reality imaging device. The display screen can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer equipment can be a touch layer covered on the display screen, can also be a key, a track ball or a touch pad arranged on the shell of the computer equipment, and can also be an external keyboard, a touch pad or a mouse and the like.
It will be appreciated by those skilled in the art that the structures shown in fig. 5 and 6 are block diagrams of only portions of structures that are relevant to the present application and are not intended to limit the computer device on which the present application may be implemented, and that a particular computer device may include more or fewer components than shown, or may combine certain components, or have a different arrangement of components.
In some embodiments, a computer device is provided that includes a memory having a computer program stored therein and a processor that when executed implements the steps of the data correction method of a nuclear reactor described above.
In some embodiments, a computer readable storage medium is provided having a computer program stored thereon, which when executed by a processor, implements the steps in the data correction method of a nuclear reactor described above.
In some embodiments, a computer program product is provided comprising a computer program which, when executed by a processor, implements the steps in the data correction method of a nuclear reactor described above.
It should be noted that, the user information (including, but not limited to, user equipment information, user personal information, etc.) and the data (including, but not limited to, data for analysis, stored data, presented data, etc.) referred to in the present application are information and data authorized by the user or sufficiently authorized by each party, and the collection, use and processing of the related data are required to comply with the related laws and regulations and standards of the related countries and regions.
Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, database, or other medium used in the various embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, high density embedded nonvolatile Memory, resistive random access Memory (ReRAM), magnetic random access Memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric Memory (Ferroelectric Random Access Memory, FRAM), phase change Memory (Phase Change Memory, PCM), graphene Memory, and the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory, and the like. By way of illustration, and not limitation, RAM can be in the form of a variety of forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), and the like. The databases referred to in the various embodiments provided herein may include at least one of relational databases and non-relational databases. The non-relational database may include, but is not limited to, a blockchain-based distributed database, and the like. The processors referred to in the embodiments provided herein may be general purpose processors, central processing units, graphics processors, digital signal processors, programmable logic units, quantum computing-based data processing logic units, etc., without being limited thereto.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The above examples only represent a few embodiments of the present application, which are described in more detail and are not to be construed as limiting the scope of the present application. It should be noted that it would be apparent to those skilled in the art that various modifications and improvements could be made without departing from the spirit of the present application, which would be within the scope of the present application. Accordingly, the scope of protection of the present application shall be subject to the appended claims.
Claims (10)
1. A method of modifying data for a nuclear reactor, the method comprising:
acquiring calibration core data of a reactor of a nuclear power plant at a calibration time; the calibration time refers to the time of calibrating the detector in the reactor;
acquiring real-time core data obtained by monitoring the reactor by using the detector;
performing thermodynamic and hydraulic calculations on the reactor based on the real-time core data to obtain an estimated deviation nucleate boiling ratio of the reactor;
Correcting the estimated deviation nucleate boiling ratio according to the core data deviation between the real-time core data and the calibration core data to obtain a corrected deviation nucleate boiling ratio; the correction deviates from the nucleate boiling ratio for protection control of the reactor.
2. The method of claim 1, wherein said correcting the estimated off-nucleate boiling ratio based on core data bias between the real-time core data and the calibrated core data to obtain a corrected off-nucleate boiling ratio comprises:
determining a target deviation function representing a relationship between a deviation from a nucleate boiling ratio deviation and the core data deviation; the deviation from the nucleate boiling ratio deviation is a deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio;
substituting the core data deviation into the target deviation function to obtain a deviation from a nucleate boiling ratio deviation;
determining the modified off-nucleate boiling ratio based on the estimated off-nucleate boiling ratio deviation from the off-nucleate boiling ratio.
3. The method of claim 2, wherein the determining a target deviation function representative of a relationship between a deviation from a nucleate boiling ratio deviation and a core data deviation comprises:
Acquiring corresponding actual deviation nucleate boiling ratios and reactor core data of the reactor in a plurality of reactor core running states through a design program; the reactor core operation state comprises a normal working condition state and an accident working condition state;
for each reactor core operation state, performing thermodynamic and hydraulic calculation according to reactor core data corresponding to the reactor core operation state, and determining an estimated deviation nucleate boiling ratio corresponding to the reactor core operation state;
determining deviation from a nucleate boiling ratio deviation corresponding to the core operating condition according to the estimated deviation from a nucleate boiling ratio and the actual deviation from a nucleate boiling ratio corresponding to the core operating condition;
determining core data deviation existing between each core operation state and the core operation state at the calibration time;
and performing function fitting according to the deviation nucleate boiling ratio deviation and the core data deviation corresponding to each core operation state to obtain the target deviation function.
4. The method of claim 1, wherein the real-time core data comprises real-time hot aisle data; the acquiring real-time core data obtained by monitoring the reactor by using the detector comprises the following steps:
determining corresponding calibration parameters of the detector at the calibration time;
Acquiring a current signal of the detector;
performing power reconstruction based on the calibration parameters and the current signals to obtain core power distribution of the reactor;
reconstructing thermal channel data based on the reactor core power distribution to obtain the real-time thermal channel data;
the correction of the estimated off-nucleate boiling ratio according to the core data deviation between the real-time core data and the calibration core data to obtain a corrected off-nucleate boiling ratio comprises:
determining the core data bias based on a bias between the real-time hot aisle data and the calibrated hot aisle data;
and correcting the estimated off-nucleate boiling ratio according to the core data deviation to obtain a corrected off-nucleate boiling ratio.
5. The method of claim 4, wherein the real-time core data further comprises a real-time status parameter; the performing a thermo-hydraulic calculation on the reactor based on the real-time core data to obtain an estimated deviation from a nucleate boiling ratio of the reactor, comprising:
and performing thermodynamic and hydraulic calculation on the reactor according to the reactor core power distribution and the real-time state parameter to obtain the estimated deviation nucleate boiling ratio of the reactor.
6. The method of claim 5, wherein the real-time status parameters include coolant inlet temperature, coolant flow, and pressurizer pressure; the thermal hydraulic calculation is carried out on the reactor according to the reactor core power distribution and the real-time state parameter to obtain the estimated deviation nucleate boiling ratio of the reactor, and the method comprises the following steps:
determining a critical heat flux density of the reactor based on the coolant inlet temperature, coolant flow and pressurizer pressure;
determining the local heat flux density of the reactor core according to the ratio between the power distribution of the reactor core and the heating circumference;
the estimated departure from the nucleate boiling ratio is determined based on a ratio between the core critical heat flux density and the local heat flux density.
7. The method of claim 1, wherein after obtaining the modified off-nucleate boiling ratio, the method further comprises:
comparing the corrected off-nucleate boiling ratio with a preset threshold corresponding to the reactor;
and performing shutdown protection on the reactor in the condition that the modified deviation nucleate boiling ratio is smaller than the preset threshold value.
8. A data correction device for a nuclear reactor, the device comprising:
The calibration data acquisition module is used for acquiring calibration core data of a reactor of the nuclear power plant at a calibration time; the calibration time refers to the time of calibrating the detector in the reactor;
the real-time data acquisition module is used for acquiring real-time reactor core data obtained by monitoring the reactor by using the detector;
the thermodynamic hydraulic calculation module is used for carrying out thermodynamic hydraulic calculation on the reactor based on the real-time reactor core data to obtain an estimated deviation nucleate boiling ratio of the reactor;
the correction module is used for correcting the estimated deviation nucleate boiling ratio according to the core data deviation between the real-time core data and the corrected core data to obtain a corrected deviation nucleate boiling ratio; the correction deviates from the nucleate boiling ratio for protection control of the reactor.
9. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any of claims 1 to 7 when the computer program is executed.
10. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 7.
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