Data correction method and apparatus for nuclear reactor, computer device and storage medium

Abstract

The present application relates to a data correction method and apparatus for a nuclear reactor, a computer device and a storage medium. The method comprises: acquiring calibration reactor core data of a reactor of a nuclear power plant at a calibration moment, the calibration moment referring to the moment when a detector in the reactor is calibrated; acquiring real-time reactor core data obtained by using the detector to monitor the reactor; performing thermal hydraulic calculation on the reactor on the basis of the real-time reactor core data to obtain an estimated departure from nucleate boiling ratio of the reactor; and on the basis of a reactor core data deviation between the real-time reactor core data and the calibration reactor core data, correcting the estimated departure from nucleate boiling ratio to obtain a corrected departure from nucleate boiling ratio, wherein the corrected departure from nucleate boiling ratio is used for protection and control of the reactor. The method can improve the accuracy of reactor protection and control.

Description

Data correction method, device, computer equipment and storage medium for nuclear reactor

[0001] Cross-references

[0002] This application refers to Chinese Patent Application No. 2023116149922, filed on November 29, 2023, entitled “Data Correction Method, Device, Computer Equipment and Storage Medium for Nuclear Reactor,” which is incorporated herein by reference in its entirety. Technical Field

[0003] The present application relates to the field of data processing technology, and in particular to a data correction method, device, computer equipment and storage medium for a nuclear reactor. Background Art

[0004] In the field of nuclear power, to ensure the safety of reactors in nuclear power plants, it is necessary to monitor the reactors in the nuclear power plants in real time and determine whether to perform protective control on the reactors based on the monitoring data. For example, if it is detected that the reactor deviates from nucleate boiling, a reactor shutdown protection operation is performed.

[0005] In traditional technology, the deviation from nucleate boiling ratio of the reactor is usually determined based on the core data monitored in real time by the in-core self-powered neutron detector (SPND) and the real-time monitored thermal-hydraulic parameters. The deviation from nucleate boiling ratio is then used to determine whether to perform protective control on the reactor.

[0006] However, since SPND is usually calibrated by periodic calibration, and the reactor core state is constantly changing, the deviation between the real-time core state and the core state at the calibration time causes the deviation from the nucleate boiling ratio calculated by the traditional method to be inaccurate, resulting in low accuracy of reactor protection control.

[0007] Summary of the Invention

[0008] Based on this, it is necessary to provide a data correction method, device, computer equipment, computer-readable storage medium and computer program product for a nuclear reactor that can improve the accuracy of reactor protection control in order to address the above technical problems.

[0009] In a first aspect, the present application provides a data correction method for a nuclear reactor. The method comprises: obtaining calibration core data of a nuclear power plant reactor at a calibration time; the calibration time refers to the time when a detector in the reactor is calibrated; obtaining real-time core data obtained by monitoring the reactor using the detector; performing thermal-hydraulic calculations on the reactor based on the real-time core data to obtain an estimated deviation from nucleate boiling ratio of the reactor; correcting the estimated deviation from nucleate boiling ratio based on the core data deviation between the real-time core data and the calibration core data to obtain a corrected deviation from nucleate boiling ratio; and using the corrected deviation from nucleate boiling ratio to perform protection control on the reactor.

[0010] In a second aspect, the present application also provides a data correction device for a nuclear reactor. The device includes: a calibration data acquisition module for acquiring calibration core data of a nuclear power plant reactor at a calibration time; the calibration time refers to the time when the detectors in the reactor are calibrated; a real-time data acquisition module for acquiring real-time core data obtained by monitoring the reactor using the detectors; a thermal-hydraulic calculation module for performing thermal-hydraulic calculations 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 for correcting the estimated deviation from the nucleate boiling ratio based on the core data deviation between the real-time core data and the calibration core data to obtain a corrected deviation from the nucleate boiling ratio; the corrected deviation from the nucleate boiling ratio is used to protect and control the reactor.

[0011] In some embodiments, the correction module is further used to: determine a target deviation function representing the relationship between the deviation from the nucleate boiling ratio and the core data deviation; the deviation from the nucleate boiling ratio is the deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio; substitute the core data deviation into the target deviation function to obtain the deviation from the nucleate boiling ratio; and determine a corrected deviation from the nucleate boiling ratio based on the estimated deviation from the nucleate boiling ratio and the deviation from the nucleate boiling ratio.

[0012] In some embodiments, the data correction device of the nuclear reactor also includes a function determination module, which is used to: obtain the actual deviation from the nucleate boiling ratio and core data corresponding to the reactor under multiple core operating states through a design program; the core operating state includes a normal operating state and an accident operating state; for each core operating state, perform thermal-hydraulic calculations based on the core data corresponding to the core operating state to determine the estimated deviation from the nucleate boiling ratio corresponding to the core operating state; determine the deviation from the nucleate boiling ratio corresponding to the core operating state based on the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio; determine the core data deviation between each core operating state and the core operating state at the calibration moment; perform function fitting based on the deviation from the nucleate boiling ratio and the core data deviation corresponding to each core operating state to obtain a target deviation function.

[0013] In some embodiments, the real-time core data includes real-time hot channel data; the real-time data acquisition module is also used to: determine the calibration parameters corresponding to the detector at the calibration time; obtain the current signal of the detector; perform power reconstruction based on the calibration parameters and the current signal to obtain the core power distribution of the reactor; reconstruct the hot channel data based on the core power distribution to obtain real-time hot channel data; the correction module is also used to: determine the core data deviation based on the deviation between the real-time hot channel data and the calibration hot channel data; correct the estimated deviation from the nucleate boiling ratio according to the core data deviation to obtain the corrected deviation from the nucleate boiling ratio.

[0014] In some embodiments, the real-time core data also includes real-time state parameters; the boiling estimation module is further used to: perform thermal-hydraulic calculations on the reactor based on the core power distribution and the real-time state parameters to obtain an estimated deviation from nucleate boiling ratio of the reactor.

[0015] In some embodiments, the real-time status parameters include coolant inlet temperature, coolant flow rate and pressurizer pressure; the thermal hydraulic calculation module is also used to: determine the critical heat flux density of the reactor based on the coolant inlet temperature, coolant flow rate and pressurizer pressure; determine the local heat flux density of the core based on the ratio between the core power distribution and the heating circumference; determine the estimated deviation from the nucleate boiling ratio based on the ratio between the local heat flux density of the core and the critical heat flux density.

[0016] In some embodiments, after obtaining the corrected deviation from nucleate boiling ratio, the data correction device of the nuclear reactor also includes a control and protection module, which is used to: compare the corrected deviation from nucleate boiling ratio with a preset threshold corresponding to the reactor; and perform shutdown protection on the reactor when the corrected deviation from nucleate boiling ratio is less than the preset threshold.

[0017] In a third aspect, the present application further provides a computer device comprising a memory and a processor, wherein the memory stores a computer program, and the processor implements the steps of the above-mentioned nuclear reactor data correction method when executing the computer program.

[0018] In a fourth aspect, the present application further provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the steps of the above-mentioned nuclear reactor data correction method.

[0019] In a fifth aspect, the present application further provides a computer program product, which includes a computer program that implements the steps of the above-mentioned nuclear reactor data correction method when executed by a processor.

[0020] The above-mentioned nuclear reactor data correction method, device, computer equipment, storage medium and computer program product obtain the calibrated core data of the nuclear power plant reactor at the calibrated time and the real-time core data obtained by monitoring the reactor with a detector, and then perform thermal-hydraulic calculations on the reactor based on the real-time core data to obtain the estimated deviation from the nucleate boiling ratio of the reactor. According to the core data deviation between the real-time core data and the calibrated core data, the estimated deviation from the nucleate boiling ratio is corrected in real time, thereby reducing unnecessary over-conservative assumptions and making the calculation of the deviation from the nucleate boiling ratio more accurate. Since the corrected deviation from the nucleate boiling ratio is used to protect and control the reactor, the accuracy of the reactor protection control is improved. BRIEF DESCRIPTION OF THE DRAWINGS

[0021] FIG1 is a diagram showing an application environment of a data correction method for a nuclear reactor according to an embodiment;

[0022] FIG2 is a schematic flow chart of a method for correcting data of a nuclear reactor according to one embodiment;

[0023] FIG3 is a schematic diagram of a process for fitting a target deviation function in one embodiment;

[0024] FIG4 is a structural block diagram of a data correction device for a nuclear reactor according to one embodiment;

[0025] FIG5 is a diagram showing the internal structure of a computer device according to one embodiment;

[0026] FIG6 is a diagram showing the internal structure of a computer device in another embodiment. DETAILED DESCRIPTION

[0027] In order to make the purpose, technical solutions and advantages of this application more clear, the following further describes this application in detail with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain this application and are not intended to limit this application.

[0028] The nuclear reactor data correction method provided in the embodiments of the present application can be applied in the application environment shown in FIG1 . The application environment includes a terminal 102 and a server 104, wherein the terminal 102 communicates with the server 104 via a network. A data storage system can store data that the server 104 needs to process. The data storage system can be integrated with the server 104 or placed in the cloud or on another network server.

[0029] Specifically, taking the application of this method to server 104 as an example, server 104 obtains calibrated core data of a nuclear power plant reactor at a calibration time. Calibration time refers to the time when the detectors in the reactor are calibrated. Server 104 obtains real-time core data obtained by monitoring the reactor using the detectors. Server 104 performs thermal-hydraulic calculations on the reactor based on the real-time core data to obtain an estimated deviation from nucleate boiling ratio of the reactor. Server 104 corrects the estimated deviation from nucleate boiling ratio based on the core data deviation between the real-time core data and the calibrated core data to obtain a corrected deviation from nucleate boiling ratio. The corrected deviation from nucleate boiling ratio is used to perform protective control on the reactor. For example, server 104 generates a reactor trip protection instruction for the reactor and sends the trip protection instruction to terminal 102. Terminal 102 executes a reactor trip protection according to the trip protection instruction.

[0030] The terminal 102 may be, but is not limited to, various personal computers, laptops, smart phones, tablet computers, and IoT devices. The server 104 may be implemented as an independent server or a server cluster consisting of multiple servers.

[0031] Those skilled in the art will understand that the application environment shown in FIG1 is merely a partial scenario related to the solution of the present application and does not constitute a limitation on the application environment of the solution of the present application.

[0032] In some embodiments, as shown in FIG2 , a method for correcting data of a nuclear reactor is provided. The method can be executed by a terminal or a server, or can be executed by both the terminal and the server. The method is described by taking the application of the method to the server 104 in FIG1 as an example, and includes the following steps:

[0033] Step 202, obtaining calibration core data of the nuclear power plant reactor at the calibration time; the calibration time refers to the time when the detectors in the reactor are calibrated.

[0034] Among them, the reactor is also called a nuclear reactor or an atomic reactor. It is a device that can maintain a controllable self-sustaining chain nuclear fission reaction to realize the utilization of nuclear energy. For example, in a nuclear power plant, the reactor is used to generate electricity. In a nuclear power plant, in order to ensure the safety of the reactor core active area, for example, to prevent safety accidents caused by the melting of the fuel grid assembly pellets and the failure of the cladding due to nucleate boiling (DNB), the reactor is usually monitored in real time through detectors in the reactor. The detector can be a self-powered neutron detector (SPND). Since the signal transmitted by the detector is a current signal, it is necessary for on-site personnel to calibrate the detector regularly. For example, the detector can be calibrated on the 1st of each month. Calibration refers to the correction and marking of the data monitored by the detector. The calibration time refers to the time when the detector in the reactor is calibrated.

[0035] Specifically, there may be multiple calibration moments, and the server stores the core data corresponding to each calibration moment. The server may determine the core data corresponding to the most recent calibration moment as the calibration core data.

[0036] Step 204: Acquire real-time core data obtained by monitoring the reactor using a detector.

[0037] Core data refers to data related to the active region of the reactor core, including hot channel data and state parameters. A reactor's fuel assembly consists of multiple fuel rods. The hot channel refers to the channel containing the highest-power fuel rods. Hot channel data refers to data related to the hot channel, including at least one of the hot channel enthalpy rise factor, hot channel position, or hot channel axial power offset. State parameters, also known as thermal-hydraulic parameters, include at least one of the coolant inlet temperature, coolant flow rate, or pressurizer pressure. Real-time core data refers to core data acquired in real time through monitoring of the reactor using detectors.

[0038] Specifically, the detector monitors the reactor in real time and sends monitoring signals to the server. The server can receive the monitoring signals sent by the detector and determine real-time core data based on the monitoring signals.

[0039] In some embodiments, real-time core data includes real-time state parameters and real-time hot channel data. The real-time state parameters can be directly acquired, while the real-time hot channel data must be reconstructed based on the detector's current signal. The server can perform power reconstruction on the current signal to obtain the reactor's core power distribution. The server then reconstructs the hot channel data based on the core power distribution to obtain real-time hot channel data. The core power distribution refers to the distribution of linear power density corresponding to each fuel rod in the reactor.

[0040] Step 206 : Perform thermal-hydraulic calculations on the reactor based on the real-time core data to obtain an estimated deviation from nucleate boiling ratio of the reactor.

[0041] The deviation from nucleate boiling ratio (DNR) characterizes the boiling state or boiling degree of a reactor. It is negatively correlated with the boiling degree of a reactor. The smaller the DNR, the higher the boiling degree and the greater the core power. In practice, the DNR refers to the ratio between the critical heat flux and the local heat flux.

[0042] Specifically, the server calculates the critical heat flux based on heat transfer principles and real-time state parameters. The server then determines the linear power density corresponding to each node in the reactor based on the core power distribution. For each node, the server calculates the ratio of the linear power density to the corresponding heating perimeter to obtain the local core heat flux. The server can use the ratio between the critical core heat flux and the local heat flux as the estimated deviation from nucleate boiling ratio.

[0043] Step 208 , correcting the estimated deviation from the nucleate boiling ratio based on the core data deviation between the real-time core data and the calibrated core data to obtain a corrected deviation from the nucleate boiling ratio; the corrected deviation from the nucleate boiling ratio is used for protecting and controlling the reactor.

[0044] The core data deviation refers to the deviation between the real-time core data and the calibrated core data, which may specifically include the hot channel data deviation and the state parameter deviation.

[0045] Specifically, the server calculates the core data deviation between the real-time core data and the calibration core data, and determines a target deviation function representing the relationship between the deviation from the nucleate boiling ratio and the core data deviation, and then substitutes the core data deviation into the target deviation function for calculation to obtain the deviation from the nucleate boiling ratio. The server corrects the estimated deviation from the nucleate boiling ratio based on the deviation from the nucleate boiling ratio to obtain a corrected deviation from the nucleate boiling ratio. The target deviation function can be determined based on the actual deviation from the nucleate boiling ratio and core data corresponding to the reactor under various core operating conditions, as well as the core data at the calibration time. The deviation from the nucleate boiling ratio is the deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio. The actual deviation from the nucleate boiling ratio is the true deviation from the nucleate boiling ratio corresponding to the reactor in theory.

[0046] In the above-mentioned data correction method for a nuclear reactor, the calibration core data of the reactor of the nuclear power plant at the calibration time and the real-time core data obtained by monitoring the reactor with a detector are obtained, and then the reactor is thermal-hydraulic calculated based on the real-time core data to obtain the estimated deviation from the nucleate boiling ratio of the reactor. According to the core data deviation between the real-time core data and the calibration core data, the estimated deviation from the nucleate boiling ratio is corrected in real time, thereby reducing unnecessary over-conservative assumptions and making the calculation of the deviation from the nucleate boiling ratio more accurate. Since the corrected deviation from the nucleate boiling ratio is used to protect and control the reactor, the accuracy of the reactor protection control is improved.

[0047] In some embodiments, step 408, based on the core data deviation between the real-time core data and the calibration core data, correcting the estimated deviation from the nucleate boiling ratio to obtain a corrected deviation from the nucleate boiling ratio, includes: determining a target deviation function representing the relationship between the deviation from the nucleate boiling ratio and the core data deviation; the deviation from the nucleate boiling ratio is the 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 the deviation from the nucleate boiling ratio; and determining a corrected deviation from the nucleate boiling ratio based on the estimated deviation from the nucleate boiling ratio and the deviation from the nucleate boiling ratio.

[0048] Specifically, the server obtains a target deviation function fitted based on core data under a large number of different core operating conditions. The dependent variable in the target deviation function is the deviation from the nucleate boiling ratio, and the independent variable is the core data deviation. The server can substitute the core data deviation into the target deviation function to calculate the deviation from the nucleate boiling ratio. The server then uses the estimated deviation from the nucleate boiling ratio and the deviation from the nucleate boiling ratio to determine the corrected deviation from the nucleate boiling ratio.

[0049] In some embodiments, the server may perform a sum operation on the estimated deviation from nucleate boiling ratio and the deviation from nucleate boiling ratio to obtain a corrected deviation from nucleate boiling ratio. The corrected deviation from nucleate boiling ratio may be expressed as follows: DNBR corr =DNBR cal +f(ΔT in ,ΔP pzr ,ΔQ,ΔF ΔH ,Δd FΔH ,ΔAO);

[0050] Among them, DNBR corr Denotes the Corrected Departure from Nucleate Boiling Ratio, DNBR cal represents the estimated deviation from nucleate boiling ratio. f(ΔT in ,ΔP pzr ,ΔQ,ΔF ΔH ,Δd FΔH ,ΔAO) represents the deviation from nucleate boiling ratio, while ΔTin ,ΔP pzr ,ΔQ,ΔF ΔH ,Δd FΔH , ΔAO are all core data deviations, ΔT in is the deviation between the calibrated coolant inlet temperature and the real-time coolant inlet temperature; ΔP pzr is the deviation between the calibrated regulator pressure and the real-time regulator pressure; ΔQ is the deviation between the calibrated coolant flow and the real-time coolant flow; ΔF ΔH is the deviation between the enthalpy rise factor of the calibrated hot channel and the enthalpy rise factor of the real-time channel; Δd FΔH It is the deviation between the calibrated hot channel position and the real-time hot channel position; ΔAO is the deviation between the calibrated hot channel axial power offset and the real-time hot channel axial power offset.

[0051] In this embodiment, since the target deviation function can express the relationship between the deviation from the nucleate boiling ratio and the core data deviation, the core data deviation can be directly substituted into the target deviation function to obtain the deviation from the nucleate boiling ratio. Based on the deviation from the nucleate boiling ratio, real-time correction of the data is achieved, making the corrected deviation from the nucleate boiling ratio more accurate.

[0052] In some embodiments, determining a target deviation function representing the relationship between the deviation from the nucleate boiling ratio and the core data deviation includes: obtaining actual deviation from the nucleate boiling ratio and core data corresponding to a reactor under multiple core operating states; performing thermal-hydraulic calculations for each core operating state based on the core data corresponding to the core operating state to determine an estimated deviation from the nucleate boiling ratio corresponding to the core operating state; determining a deviation from the nucleate boiling ratio corresponding to the core operating state based on the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio; determining the core data deviation between each core operating state and the core operating state at a calibration moment; performing function fitting based on the deviation from the nucleate boiling ratio and the core data deviation corresponding to each core operating state to obtain a target deviation function.

[0053] The design program is used to simulate reactor operating conditions. Multiple core operating states are pre-set by the design program, including, for example, normal operating conditions and accident operating conditions. The normal operating condition refers to the core state under normal operating conditions, and the accident operating condition refers to the core state under accident conditions. The actual deviation from nucleate boiling ratio refers to the actual deviation from nucleate boiling ratio of the reactor under the core operating conditions, which can be obtained through simulation by the design program.

[0054] Specifically, the server can obtain the actual deviation from the nucleate boiling ratio and core data corresponding to each core operating state of the reactor from the data of multiple core operating states stored locally, and obtain the core data at the calibration time, wherein the data of each core operating state is generated by simulating the reactor operating conditions through a design program. For each core operating state, the server can perform thermal-hydraulic calculations based on the thermal-hydraulic parameters in the core data corresponding to the core operating state to obtain an estimated deviation from the nucleate boiling ratio corresponding to the core operating state, and determine the deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio corresponding to the core operating state as the deviation from the nucleate boiling ratio corresponding to the core operating state. The server can also determine the calibration time corresponding to the core operating state, thereby determining the deviation between the core data corresponding to the core operating state and the calibration core data at the calibration time as the core data deviation between the core operating state and the core operating state at the calibration time.

[0055] In some embodiments, as shown in FIG3 , a flow chart for fitting a target deviation function is shown. The terminal can use a nuclear design program to simulate the core operating state under normal reactor operation or accident conditions to obtain core data and a theoretical deviation from nucleate boiling ratio for each simulated core operating state. The terminal can also use the nuclear design program to simulate the core operating state at a calibration time to obtain simulated calibration parameters and calibration core data. Thus, based on the simulated core data and the theoretical deviation from nucleate boiling ratio, the simulated calibration parameters, and the calibration core data for each simulated core operating state, the terminal can obtain a state parameter deviation, a hot channel deviation, and a deviation from nucleate boiling ratio, and fit a target deviation function based on the state parameter deviation, the hot channel deviation, and the deviation from nucleate boiling ratio.

[0056] In this embodiment, function fitting is performed based on the deviation from the nucleate boiling ratio and the core data deviation corresponding to each core operating state to obtain a target deviation function for real-time calculation of the deviation from the nucleate boiling ratio. Moreover, in the actual correction process, when adjusting the uncertainty, it is only necessary to adjust the coefficient of the correction term in the function, which will not affect other constant data, thereby improving the safety of the protection control system.

[0057] In some embodiments, the real-time core data includes real-time hot channel data; step 204, obtaining real-time core data obtained by monitoring the reactor using a detector, including: determining the calibration parameters corresponding to the detector at the calibration time; obtaining the current signal of the detector; performing power reconstruction based on the calibration parameters and the current signal to obtain the core power distribution of the reactor; reconstructing the hot channel data based on the core power distribution to obtain real-time hot channel data; correcting the estimated deviation from the 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 from the nucleate boiling ratio, including: determining the core data deviation based on the deviation between the real-time hot channel data and the calibration hot channel data; correcting the estimated deviation from the nucleate boiling ratio according to the core data deviation to obtain a corrected deviation from the nucleate boiling ratio.

[0058] The calibration parameters are determined based on the detector's monitoring signal at the calibration time. The deviation between the real-time hot channel data and the calibration hot channel data is the hot channel data deviation, which is positively correlated with the deviation from the nucleate boiling ratio.

[0059] Specifically, real-time hot channel data includes real-time hot channel location, real-time hot channel enthalpy rise factor, and real-time hot channel axial power offset. Based on the core power distribution, the server can identify the channel with the highest linear power density as the real-time hot channel, and determine the location of the real-time hot channel in the reactor to obtain the real-time hot channel location. The server can also perform an integrated power calculation based on the linear power density corresponding to the hot channel to obtain the real-time hot channel enthalpy rise factor. The real-time hot channel axial power offset is obtained by subtracting the lower integrated power from the upper integrated power calculated based on the hot channel's linear power density and dividing it by the total integrated power.

[0060] In some embodiments, the calibration parameters include the calibration current signal and the hot channel linear power density. Nuclear power plant technicians regularly calibrate the detectors, for example, monthly, to obtain the calibration current signal at the time of calibration. The terminal can use nuclear design software to simulate the reactor core state and obtain the hot channel linear power density of all fuel assemblies in the core. The terminal uses the hot channel linear power density and the calibration current signal as calibration parameters and sends the calibration time and corresponding calibration parameters to the server.

[0061] In some embodiments, the server can utilize the principle that current is proportional to power to perform power reconstruction based on calibration parameters and current signals to obtain the core power distribution of the reactor. For example, the calibration parameters include the hot channel line power Pcalib(i,j) and the calibration current signal Icalib(i,j), the real-time current signal of the detector is Imes(i,j), and the core power distribution can be expressed as Pmes(i,j). The power reconstruction formula is as follows: Pmes(i,j) = Pcalib(i,j) × Imes(i,j) / Icalib(i,j);

[0062] Where (i, j) represents the location of the node in the reactor.

[0063] In this embodiment, since the hot channel will change according to the core state of the reactor, and the hot channel data cannot be directly obtained, the core power distribution is obtained by power reconstruction based on the calibration parameters and current signals, and the real-time hot channel data is reconstructed according to the core power distribution. Based on the deviation between the real-time hot channel data and the calibrated hot channel data, the core data deviation is determined to achieve real-time data correction.

[0064] In some embodiments, the real-time core data also includes real-time state parameters; step 206, performing thermal-hydraulic calculations on the reactor based on the real-time core data to obtain an estimated deviation from the nucleate boiling ratio of the reactor, including: performing thermal-hydraulic calculations on the reactor according to the core power distribution and the real-time state parameters to obtain an estimated deviation from the nucleate boiling ratio of the reactor.

[0065] Specifically, it can be understood that the real-time core data includes real-time state parameters and real-time heat channel data. The real-time state parameters can be used for thermal hydraulic calculations to obtain an estimated deviation from the nucleate boiling ratio, and can also participate in the correction of the deviation from the nucleate boiling ratio, that is, the core data deviation includes the state parameter deviation.

[0066] In this embodiment, by performing thermal-hydraulic calculations on the reactor based on the core power distribution and real-time state parameters, real-time calculation of the deviation from the nucleate boiling ratio is achieved.

[0067] In some embodiments, real-time core data includes coolant inlet temperature, coolant flow rate and pressurizer pressure; thermal-hydraulic calculations are performed on the reactor based on the core power distribution and real-time state parameters to obtain an estimated deviation from nucleate boiling ratio of the reactor, including: determining the critical heat flux density of the reactor based on the coolant inlet temperature, coolant flow rate and pressurizer pressure; determining the local heat flux density of the core based on the ratio between the core power distribution and the heating circumference; and determining the estimated deviation from nucleate boiling ratio based on the ratio between the critical heat flux density of the core and the local heat flux density.

[0068] Specifically, the server calculates the enthalpy, flow rate, and gas fraction of the local fluid in the reactor based on the core inlet temperature, core inlet flow rate, pressurizer pressure, and heat transfer principles. The server then substitutes the enthalpy, flow rate, and gas fraction of the local fluid into a preset fitting relationship to calculate the critical heat flux. The preset fitting relationship is obtained by fitting the enthalpy, flow rate, gas fraction, and critical heat flux of the local fluid obtained experimentally. The server obtains the heating perimeter corresponding to each node in the reactor, determines the linear power density corresponding to each node, and determines the ratio between the linear power density and the heating perimeter as the local core heat flux corresponding to the node. The server can determine the ratio between the core critical heat flux and the local heat flux as the estimated deviation from nucleate boiling ratio.

[0069] In this embodiment, by determining the critical heat flux and the local core heat flux, the estimated deviation from the nucleate boiling ratio is determined based on the ratio between the local core heat flux and the critical heat flux, thereby achieving real-time estimation of the boiling state.

[0070] In some embodiments, after obtaining the corrected deviation from nucleate boiling ratio, the data correction method for the nuclear reactor further includes: comparing the corrected deviation from nucleate boiling ratio with a preset threshold value corresponding to the reactor; and performing reactor shutdown protection on the reactor when the corrected deviation from nucleate boiling ratio is less than the preset threshold value.

[0071] The preset threshold is a pre-set value, which can be any value between 1 and 10. The reactor shutdown protection refers to the operation of controlling the reactor to stop the reaction to prevent the reactor from boiling and causing a safety accident.

[0072] Specifically, the server can compare the corrected deviation from nucleate boiling ratio with a preset threshold. If the corrected deviation from nucleate boiling ratio is greater than or equal to the preset threshold, it is determined that nucleate boiling is not occurring in the reactor and no protective control is required. If the corrected deviation from nucleate boiling ratio is less than the preset threshold, it can be determined that nucleate boiling is currently occurring in the reactor, indicating that the reactor core power is too high and a protective shutdown is required. The server can generate a shutdown protection instruction for the reactor and send the shutdown protection instruction to the terminal. The terminal receives the shutdown protection instruction sent by the server and controls the reactor to execute a protective shutdown according to the shutdown protection instruction.

[0073] In this embodiment, since the corrected deviation from the nucleate boiling ratio is more accurate than the data before correction, by comparing the corrected deviation from the nucleate boiling ratio with a preset threshold, when the corrected deviation from the nucleate boiling ratio is less than the preset threshold, the reactor is shut down for protection, thereby achieving more accurate reactor protection control and improving the operational safety of the nuclear power plant.

[0074] It should be understood that, although the steps in the flowcharts of the above embodiments are shown in sequence as indicated by the arrows, these steps are not necessarily performed in the order indicated by the arrows. Unless otherwise specified herein, there is no strict order restriction on the execution of these steps, and these steps can be performed in other orders. Moreover, at least a portion of the steps in the flowcharts of the above embodiments may include multiple steps or multiple stages, and these steps or stages are not necessarily performed at the same time, but can be performed at different times. The execution order of these steps or stages is not necessarily to be performed in sequence, but can be performed in turn or alternately with other steps or at least a portion of steps or stages in other steps.

[0075] Based on the same inventive concept, embodiments of the present application also provide a nuclear reactor data correction device for implementing the aforementioned nuclear reactor data correction method. The solution provided by this device is similar to the solution described in the aforementioned method. Therefore, the specific limitations of one or more embodiments of the nuclear reactor data correction device provided below can be found in the aforementioned limitations of the nuclear reactor data correction method and will not be further elaborated here.

[0076] In some embodiments, as shown in FIG4 , a data correction device for a nuclear reactor is provided, comprising: a calibration data acquisition module 402 , a real-time data acquisition module 404 , a boiling estimation module 406 , and a correction module 408 , wherein:

[0077] The calibration data acquisition module 402 is used to obtain the calibration core data of the nuclear power plant reactor at the calibration time; the calibration time refers to the time when the detectors in the reactor are calibrated.

[0078] The real-time data acquisition module 404 is used to acquire real-time core data obtained by monitoring the reactor using detectors.

[0079] The boiling estimation module 406 is configured to perform thermal-hydraulic calculations on the reactor based on real-time core data to obtain an estimated deviation from nucleate boiling ratio of the reactor.

[0080] The correction module 408 is used to correct the estimated deviation from the nucleate boiling ratio based on the core data deviation between the real-time core data and the calibration core data to obtain a corrected deviation from the nucleate boiling ratio; the corrected deviation from the nucleate boiling ratio is used to protect and control the reactor.

[0081] In some embodiments, the correction module 408 is further used to: determine a target deviation function representing the relationship between the deviation from the nucleate boiling ratio and the core data deviation; the deviation from the nucleate boiling ratio is the deviation between the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio; substitute the core data deviation into the target deviation function to obtain the deviation from the nucleate boiling ratio; and determine a corrected deviation from the nucleate boiling ratio based on the estimated deviation from the nucleate boiling ratio and the deviation from the nucleate boiling ratio.

[0082] In some embodiments, the data correction device of the nuclear reactor also includes a function determination module, which is used to: obtain the actual deviation from the nucleate boiling ratio and core data corresponding to the reactor under multiple core operating states through a design program; for each core operating state, perform thermal-hydraulic calculations based on the core data corresponding to the core operating state to determine the estimated deviation from the nucleate boiling ratio corresponding to the core operating state; determine the deviation from the nucleate boiling ratio corresponding to the core operating state based on the estimated deviation from the nucleate boiling ratio and the actual deviation from the nucleate boiling ratio; determine the core data deviation between each core operating state and the core operating state at the calibration moment; perform function fitting based on the deviation from the nucleate boiling ratio and the core data deviation corresponding to each core operating state to obtain a target deviation function.

[0083] In some embodiments, the real-time core data includes real-time hot channel data; the real-time data acquisition module 404 is also used to: determine the calibration parameters corresponding to the detector at the calibration time; obtain the current signal of the detector; perform power reconstruction based on the calibration parameters and the current signal to obtain the core power distribution of the reactor; reconstruct the hot channel data based on the core power distribution to obtain real-time hot channel data; the correction module 408 is also used to: determine the core data deviation based on the deviation between the real-time hot channel data and the calibration hot channel data; correct the estimated deviation from the nucleate boiling ratio according to the core data deviation to obtain a corrected deviation from the nucleate boiling ratio.

[0084] In some embodiments, the real-time core data also includes real-time state parameters; the boiling estimation module 406 is further used to: perform thermal hydraulic calculations on the reactor based on the core power distribution and the real-time state parameters to obtain an estimated deviation from nucleate boiling ratio of the reactor.

[0085] In some embodiments, real-time core data includes coolant inlet temperature, coolant flow rate and pressurizer pressure; the boiling estimation module 406 is further used to: determine the critical heat flux density of the reactor based on the coolant inlet temperature, coolant flow rate and pressurizer pressure; determine the local heat flux density of the core based on the ratio between the core power distribution and the heating circumference; and determine the estimated deviation from the nucleate boiling ratio based on the ratio between the local heat flux density of the core and the critical heat flux density.

[0086] In some embodiments, after obtaining the corrected deviation from the nucleate boiling ratio, the data correction device of the nuclear reactor also includes a control module, and the control protection module is used to: compare the corrected deviation from the nucleate boiling ratio with a preset threshold corresponding to the reactor; and perform shutdown protection on the reactor when the corrected deviation from the nucleate boiling ratio is less than the preset threshold.

[0087] Each module in the aforementioned nuclear reactor data correction device can be implemented in whole or in part through software, hardware, or a combination thereof. Each module can be embedded in or independent of a processor in a computer device in the form of hardware, or can be stored in a memory in the computer device in the form of software, so that the processor can call and execute the corresponding operations of each module.

[0088] In some embodiments, a computer device is provided, which may be a server, and its internal structure diagram may be shown in Figure 5. The computer device includes a processor, memory, an input / output (I / O) interface, and a communication interface. The processor, memory, and I / O interface are connected via a system bus, and the communication interface is connected to the system bus via the I / O interface. The processor of the computer device is used to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and internal memory. The non-volatile storage medium stores an operating system, a computer program, and a database. The internal memory provides an environment for the operation of the operating system and computer program in the non-volatile storage medium. The database of the computer device is used to store relevant data related to a data correction method for a nuclear reactor. The I / O interface of the computer device is used to exchange information between the processor and external devices. The communication interface of the computer device is used to communicate with an external terminal via a network connection. When executed by the processor, the computer program implements a data correction method for a nuclear reactor.

[0089] In some embodiments, a computer device is provided, which may be a terminal. Its internal structure diagram may be as shown in Figure 6. The computer device includes a processor, memory, an input / output interface, a communication interface, a display unit, and an input device. The processor, memory, and input / output interface are connected via a system bus, and the communication interface, display unit, and input device are connected to the system bus via the input / output interface. The processor of the computer device is used to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and 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 program in the non-volatile storage medium. The input / output interface of the computer device is used to exchange information between the processor and external devices. The communication interface of the computer device is used to communicate with external terminals via wired or wireless communication, where the wireless communication may be achieved via Wi-Fi, a mobile cellular network, NFC (near-field communication), or other technologies. When executed by the processor, the computer program implements a data correction method for a nuclear reactor. The display unit of the computer device is used to produce a visually visible image and may 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 device can be a touch layer covering the display screen, or a button, trackball or touchpad set on the computer device casing, or an external keyboard, touchpad or mouse.

[0090] Those skilled in the art will understand that the structures shown in Figures 5 and 6 are merely block diagrams of partial structures related to the solution of the present application, and do not constitute a limitation on the computer device to which the solution of the present application is applied. The specific computer device may include more or fewer components than shown in the figures, or combine certain components, or have a different component arrangement.

[0091] In some embodiments, a computer device is provided, including a memory and a processor, wherein a computer program is stored in the memory, and the processor implements the steps in the above-mentioned nuclear reactor data correction method when executing the computer program.

[0092] In some embodiments, a computer-readable storage medium is provided, on which a computer program is stored. When the computer program is executed by a processor, the steps in the above-mentioned nuclear reactor data correction method are implemented.

[0093] In some embodiments, a computer program product is provided, comprising a computer program, which implements the steps in the above-mentioned nuclear reactor data correction method when executed by a processor.

[0094] It should be noted that the user information (including but not limited to user device information, user personal information, etc.) and data (including but not limited to data used for analysis, stored data, displayed data, etc.) involved in this application are all information and data authorized by the user or fully authorized by all parties, and the collection, use and processing of relevant data must comply with the relevant laws, regulations and standards of relevant countries and regions.

[0095] Those skilled in the art will appreciate that all or part of the processes in the above-mentioned embodiment methods can be implemented by instructing the relevant hardware through a computer program, and the computer program can be stored in a non-volatile computer-readable storage medium. When the computer program is executed, it can include the processes of the embodiments of the above-mentioned methods. Among them, any reference to memory, database or other media used in the embodiments provided in this application may include at least one of non-volatile and volatile memory. Non-volatile memory may include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory may include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can be in various forms, such as static random access memory (SRAM) or dynamic random access memory (DRAM). The database involved in the various embodiments provided herein may include at least one of a relational database and a non-relational database. Non-relational databases may include, but are not limited to, distributed databases based on blockchains. The processor involved in the various embodiments provided herein may be, but are not limited to, a general-purpose processor, a central processing unit, a graphics processing unit, a digital signal processor, a programmable logic unit, a data processing logic unit based on quantum computing, and the like.

[0096] The technical features of the above embodiments can be combined arbitrarily. To make the description concise, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0097] The above-described embodiments merely represent several implementation methods of the present application. While the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the present application. It should be noted that a person of ordinary skill in the art may make various modifications and improvements without departing from the spirit of the present application, and these modifications and improvements fall within the scope of protection of the present application. Therefore, the scope of protection of the present application shall be determined by the appended claims.

Claims

1. A method for correcting data of a nuclear reactor, wherein: The method comprises: Acquire calibration core data of a reactor of a nuclear power plant at a calibration time; the calibration time refers to the time when a detector in the reactor is calibrated; Acquiring real-time core data obtained by monitoring the reactor using the detector; Performing thermal hydraulic calculations on the reactor based on the real-time core data to obtain an estimated deviation from nucleate boiling ratio of the reactor; According to the core data deviation between the real-time core data and the calibrated core data, the estimated deviation from the nucleate boiling ratio is corrected to obtain a corrected deviation from the nucleate boiling ratio; the corrected deviation from the nucleate boiling ratio is used to protect and control the reactor.

2. The method according to claim 1, wherein: The method of correcting the estimated deviation from the nucleate boiling ratio according to the core data deviation between the real-time core data and the calibrated core data to obtain a corrected deviation from the nucleate boiling ratio comprises: Determining a target deviation function representing a relationship between a deviation from nucleate boiling ratio and the core data deviation; the deviation from nucleate boiling ratio being a deviation between an estimated deviation from nucleate boiling ratio and an actual deviation from nucleate boiling ratio; Substituting the core data deviation into the target deviation function to obtain a deviation from the nucleate boiling ratio; The corrected departure from nucleate boiling ratio is determined based on the estimated departure from nucleate boiling ratio and the departure from nucleate boiling ratio deviation.

3. The method according to claim 2, wherein: The determining of a target deviation function representing the relationship between the deviation from the nucleate boiling ratio and the core data deviation comprises: Obtaining, by designing a program, the actual deviation from nucleate boiling ratio and core data corresponding to the reactor under multiple core operating states; the core operating states include normal operating states and accident operating states; For each of the core operating states, thermal hydraulic calculations are performed according to core data corresponding to the core operating state to determine an estimated deviation from nucleate boiling ratio corresponding to the core operating state; Determining a deviation of the deviation from nucleate boiling ratio corresponding to the core operating state according to the estimated deviation from nucleate boiling ratio and the actual deviation from nucleate boiling ratio corresponding to the core operating state; Determine the core data deviation between each of the core operating states and the core operating state at the calibration time; Function fitting is performed according to the deviation from nucleate boiling ratio corresponding to each core operating state and the core data deviation to obtain the target deviation function.

4. The method according to claim 1, wherein: The real-time core data includes real-time hot channel data; the real-time core data obtained by monitoring the reactor using the detector includes: Determine the calibration parameters corresponding to the detector at the calibration time; Acquiring a current signal from the detector; Performing power reconstruction based on the calibration parameters and the current signal to obtain the core power distribution of the reactor; Reconstructing the hot channel data based on the core power distribution to obtain the real-time hot channel data; The method of correcting the estimated deviation from the nucleate boiling ratio according to the core data deviation between the real-time core data and the calibrated core data to obtain a corrected deviation from the nucleate boiling ratio comprises: Determining the core data deviation based on the deviation between the real-time hot channel data and the calibrated hot channel data; The estimated deviation from nucleate boiling ratio is corrected according to the core data deviation to obtain a corrected deviation from nucleate boiling ratio.

5. The method according to claim 4, wherein: The real-time core data also includes real-time state parameters; performing thermal hydraulic calculations on the reactor based on the real-time core data to obtain an estimated deviation from nucleate boiling ratio of the reactor includes: Thermal hydraulic calculations are performed on the reactor according to the core power distribution and the real-time state parameters to obtain an estimated deviation from nucleate boiling ratio of the reactor.

6. The method according to claim 5, wherein: The real-time state parameters include coolant inlet temperature, coolant flow rate and pressurizer pressure; the thermal-hydraulic calculation of the reactor is performed according to the core power distribution and the real-time state parameters to obtain an estimated deviation from nucleate boiling ratio of the reactor, including: Determining a critical heat flux of the reactor according to the coolant inlet temperature, the coolant flow rate and the pressurizer pressure; Determining the local heat flux density of the core according to the ratio between the core power distribution and the heating perimeter; The estimated deviation from nucleate boiling ratio is determined based on a ratio between the core critical heat flux and the local heat flux.

7. The method according to claim 1, wherein: After obtaining the corrected deviation from nucleate boiling ratio, the method further comprises: comparing the corrected deviation from nucleate boiling ratio with a preset threshold value corresponding to the reactor; When the corrected deviation from nucleate boiling ratio is less than the preset threshold, a shutdown protection is performed on the reactor.

8. A data correction device for a nuclear reactor, wherein: The device comprises: A calibration data acquisition module, used to acquire calibration core data of a reactor in a nuclear power plant at a calibration time; the calibration time refers to the time when the detector in the reactor is calibrated; A real-time data acquisition module, used to acquire real-time core data obtained by monitoring the reactor using the detector; A thermal hydraulic calculation module, used for performing thermal hydraulic calculation on the reactor based on the real-time core data to obtain an estimated deviation from nucleate boiling ratio of the reactor; A correction module is used to correct the estimated deviation from the nucleate boiling ratio according to the core data deviation between the real-time core data and the calibrated core data to obtain a corrected deviation from the nucleate boiling ratio; the corrected deviation from the nucleate boiling ratio is used to protect and control the reactor.

9. A computer device comprising a memory and a processor, wherein the memory stores a computer program, wherein: When the processor executes the computer program, the steps of the method according to any one of claims 1 to 7 are implemented.

10. A computer-readable storage medium having a computer program stored thereon, wherein: When the computer program is executed by a processor, the steps of the method according to any one of claims 1 to 7 are implemented.

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