A monitoring method and system for a steam generator of a nuclear power plant

Abstract

The present disclosure provides an intelligent monitoring method and system for a steam generator of a nuclear power plant, including a device thermal performance monitoring module, a device flow field digital twin module, a heat transfer tube fluid-induced vibration monitoring module, a heat transfer tube wear monitoring module, a device fatigue damage monitoring module, a device loose part monitoring module, and a data and file management module. Determine the original measuring points and obtain the data of each measuring point; perform thermal performance calculation and analysis on all the data of each obtained measuring point and then output the secondary side data; perform flow field distribution calculation on the secondary side data and then output the flow field data; use a flow field post-processing algorithm, a heat transfer tube inter-tube parameter algorithm, and a flow-to-bullet stability ratio algorithm to process the flow field data to obtain the fluid-induced vibration results of the heat transfer tubes; use a wear prediction algorithm to analyze the wear data of the heat transfer tubes to obtain a plugging method, greatly reducing the time required for the maintenance of the steam generator and improving the economic benefits of the nuclear power plant.

Description

Technical Field

[0001] The present disclosure relates to the technical field of nuclear power plant monitoring, and particularly to a monitoring method and system for a steam generator of a nuclear power plant. Background Art

[0002] The statements in this section merely provide background technical information related to the present disclosure and do not necessarily constitute prior art.

[0003] As the hub of the primary and secondary loops, the steam generator of a nuclear power plant plays an important role in the nuclear reactor system. The steam generator is very important for the safe operation of the entire nuclear power plant, and its normal operation directly affects the safety, economy, and reliability of the nuclear power plant operation. According to the failure mode analysis of the steam generator, the main faults that occur are that the outlet steam parameters (such as humidity, pressure, etc.) do not meet the standards, the heat transfer tubes are damaged, component fatigue, and loose parts fall off, etc. The existing steam generator monitoring systems only monitor single content, such as fatigue monitoring and heat transfer tube breakage monitoring. When actually used, it is necessary to switch frequently, which is rather cumbersome.

[0004] In addition, for most of the existing steam generator monitoring systems, it is necessary to add new sensors to the steam generator, which brings great difficulties to the installation of this monitoring system in old power plants. For example, when in use, reinstalling the sensors requires a certain degree of damage to the pressure-bearing boundary and needs to re-consider the sensor wiring to bring safety problems such as electromagnetic compatibility. There are certain difficulties in actual installation and use.

[0005] During the operation of the steam generator in the past, it was found that fluid-induced vibration is one of the important reasons for the wear of the heat transfer tubes of the steam generator. However, it is difficult to measure the thermal-hydraulic data such as the fouling coefficient of the steam generator and the flow field distribution inside the steam generator, and there is a lack of monitoring of the wear condition of the heat transfer tubes of the steam generator, resulting in a large amount of time being spent on non-destructive testing of the heat transfer tubes during each major overhaul of the nuclear power plant, seriously affecting the economic benefits of the nuclear power plant. Summary of the Invention

[0006] In order to solve the above problems, the present disclosure proposes a monitoring method and system for a steam generator of a nuclear power plant, and proposes an integrated intelligent monitoring method for the steam generator, including thermal performance monitoring, local flow field monitoring, evaluation of heat transfer tube vibration and wear, and monitoring and diagnosis of fatigue and loose parts, to perform full-life cycle management on the steam generator and improve the safety and reliability of the steam generator operation.

[0007] According to some embodiments, the present disclosure adopts the following technical solutions:

[0008] A monitoring method for a steam generator of a nuclear power plant includes:

[0009] Determine the original measuring points and obtain the data of each measuring point;

[0010] Perform thermal performance calculation and analysis on all the data obtained from each measurement point, and then output the secondary side data;

[0011] Perform flow field distribution calculation on the secondary side data, and then output the flow field data;

[0012] Use the flow field data and the calculation methods of flow bullet stability ratio, vortex shedding, and turbulent excitation to obtain the flow-induced vibration results of the heat transfer tubes; use the wear prediction algorithm to analyze the wear data of the heat transfer tubes to obtain the tube plugging method;

[0013] All data can be visualized.

[0014] According to some other embodiments, the present disclosure adopts the following technical solutions:

[0015] A monitoring system for a steam generator of a nuclear power plant, comprising:

[0016] A sensor for obtaining data of each measurement point;

[0017] An equipment thermal performance monitoring module for performing thermal performance calculation and analysis on all the data obtained from each measurement point, and then outputting the secondary side data;

[0018] An equipment flow field data twin module for performing flow field distribution calculation on the secondary side data, and then outputting the flow field data;

[0019] A heat transfer tube flow-induced vibration monitoring module for using the flow field data and the calculation methods of flow bullet stability ratio, vortex shedding, and turbulent excitation to obtain the flow-induced vibration results of the heat transfer tubes;

[0020] A heat transfer tube wear monitoring module for using the wear prediction algorithm to analyze the wear data of the heat transfer tubes to obtain the tube plugging method;

[0021] All data can be visualized.

[0022] Furthermore, an equipment fatigue damage monitoring module, and the equipment fatigue damage monitoring module is connected to a fatigue monitoring system database.

[0023] Furthermore, it further includes an equipment loose part monitoring module, and the equipment loose part monitoring module is connected to a loose part monitoring system database.

[0024] Compared with the prior art, the beneficial effects of the present disclosure are:

[0025] As an integrated intelligent monitoring software for steam generators that can be used for thermal performance monitoring, local flow field monitoring, flow-induced vibration and wear evaluation of heat transfer tubes, as well as fatigue and loose component monitoring and diagnosis, it can be used for the whole life cycle management of steam generators. During the installation process of the system, no new sensors are added, making the installation more convenient. At the same time, the system can monitor data such as fouling factor and flow field distribution that cannot be monitored, and predict the wear condition of heat transfer tubes, greatly reducing the time required for steam generator maintenance and improving the economic benefits of nuclear power plants. BRIEF DESCRIPTION OF THE DRAWINGS

[0026] The specification drawings forming a part of the present disclosure are used to provide a further understanding of the present disclosure. The schematic embodiments and descriptions thereof of the present disclosure are used to explain the present disclosure and do not constitute an improper limitation of the present disclosure.

[0027] Figure 1 It is a logical schematic diagram of the data sources of each module and the relationships between modules in the intelligent monitoring system of the steam generator of the present disclosure;

[0028] Figure 2 It is a logical schematic diagram of the data sources and the calculation logic of the equipment thermal performance monitoring module in the intelligent monitoring system of the steam generator of the present disclosure;

[0029] Figure 3 It is a logical schematic diagram of the data sources and the calculation logic of the equipment flow field digital twin module in the intelligent monitoring system of the steam generator of the present disclosure;

[0030] Figure 4 It is an overview of the overall operation of the equipment in the intelligent monitoring system of the steam generator of the present disclosure;

[0031] Figure 5 It is the equipment thermal performance monitoring module in the intelligent monitoring system of the steam generator of the present disclosure;

[0032] Figure 6 It is the equipment flow field digital twin module in the intelligent monitoring system of the steam generator of the present disclosure;

[0033] Figure 7 It is the heat transfer tube flow-induced vibration monitoring module in the intelligent monitoring system of the steam generator of the present disclosure;

[0034] Figure 8 It is the heat transfer tube wear monitoring module in the intelligent monitoring system of the steam generator of the present disclosure;

[0035] Figure 9 It is the equipment fatigue damage monitoring module in the intelligent monitoring system of the steam generator of the present disclosure;

[0036] Figure 10It is the monitoring module for loose components of equipment in the intelligent monitoring system of the steam generator of the present disclosure;

[0037] Figure 11 It is the data and file management module in the intelligent monitoring system of the steam generator of the present disclosure. Specific embodiments

[0038] The present disclosure will be further described below in conjunction with the accompanying drawings and embodiments.

[0039] It should be noted that the following detailed description is illustrative and is intended to provide further description of the present disclosure. Unless otherwise specified, all technical and scientific terms used herein have the same meaning as commonly understood by those of ordinary skill in the technical field to which the present disclosure belongs.

[0040] It should be noted that the terms used herein are only for describing specific embodiments and are not intended to limit the exemplary embodiments according to the present disclosure. As used herein, unless otherwise clearly specified in the context, the singular form is also intended to include the plural form. In addition, it should be understood that when the terms "comprising" and / or "including" are used in this specification, they indicate the presence of features, steps, operations, devices, components, and / or combinations thereof.

[0041] Embodiment 1

[0042] In an embodiment of the present disclosure, a monitoring method for a steam generator of a nuclear power plant is provided, and the steps include:

[0043] S101: Determine the original measurement points and obtain the data of each measurement point;

[0044] S102: Perform thermal performance calculation and analysis on all the data of each measurement point obtained and output the secondary side data;

[0045] S103: Perform flow field distribution calculation on the secondary side data and output the flow field data;

[0046] S104: Use the flow field data and the calculation methods of flow bullet stability ratio, vortex shedding, and turbulent excitation to obtain the flow-induced vibration results of the heat transfer tubes;

[0047] S105: Analyze the wear data of the heat transfer tubes using a wear prediction algorithm to obtain the plugging method;

[0048] All data can be visualized.

[0049] In step 101, in order not to install new sensors, data is acquired at existing measurement points, and data is collected using existing equipment. The collected data includes the required thermal power, primary loop temperature, pressure, flow rate, secondary side water level, feed water temperature, outlet steam pressure, flow rate, and blowdown flow rate. All the above data comes from the existing Reactor Coolant System (RCS system), Steam Generator System (SGS system), and Steam Generator Blowdown System (BDS system), and there is no need to add new measurement points to obtain additional data.

[0050] Furthermore, as an embodiment, all the data of each measurement point obtained is subjected to thermal performance calculation and analysis in the equipment thermal performance monitoring module. Parameters such as the fouling coefficient of the heat transfer tubes and the circulation ratio are calculated using the thermal model debugging algorithm and the thermal performance monitoring algorithm. The thermal performance calculation process is as follows:

[0051] As Figure 2 shown, according to the real-time monitoring data of the power plant, parameters such as temperature, pressure, and flow rate are called to form a complete input file for the thermal performance calculation module. According to the on-site needs, the run button is clicked, and the calculation module (a mature one-dimensional steady-state thermal-hydraulic analysis software for steam generators) automatically completes the calculation and generates a complete output file. Some of the parameters in the output file, such as the circulation ratio and fouling coefficient, can be directly called and compared with the predicted values to judge the actual operating state of the steam generator. The other part of the parameters, such as the primary and secondary side pressures, flow rates, and temperatures, can be used as input for the calculation of other modules.

[0052] The secondary side data output after the thermal performance calculation and analysis, including the secondary side steam space pressure, secondary side inlet flow rate and temperature, and secondary side heat transfer distribution data, is input to the equipment flow field digital twin module.

[0053] In step S103, the secondary side data is subjected to flow field distribution calculation and then the flow field data is output. Specifically, the equipment flow field digital twin module uses algorithms such as the flow field reduction algorithm and data visualization algorithm. As Figure 3 shown, according to the measured inlet and outlet parameters and some parameters obtained from the thermal model calculation, the secondary side flow field of the steam generator tube bundle area is calculated in real time. Based on the existing sampling data, the flow mode decomposition is carried out, and a new flow rate is constructed by combining the calculation input to obtain the distribution results of the secondary side flow field and temperature field. After the calculation results are obtained, data visualization is performed according to the calculation results, the cloud map on the cross-section is displayed, and physical quantities such as the inter-tube flow velocity and secondary side density at the heat transfer tube nodes are obtained through interpolation method, and the random turbulent load PSD is calculated to realize the rapid calculation and monitoring of the flow field distribution in the steam generator.

[0054] In the flow-induced vibration monitoring module of the heat transfer tube, the flow-induced vibration of the heat transfer tube is analyzed using the flow-elastic stability ratio calculation method, the turbulent excitation calculation method, and the vortex shedding calculation method, and the analysis results are given. The steps of the flow-induced vibration analysis are as follows:

[0055] Step 1: Call the calculation result data of the flow field digital twin module.

[0056] Step 2: The calculation module uses the relevant calculation methods in the relevant calculation methods of ASME (American Society of Mechanical Engineers) and public literature to complete the calculation of the flow-elastic stability ratio, and generates output files, including the effective flow velocity, critical flow velocity, damping ratio, flow-elastic stability ratio, etc. of the straight section and bent section of the heat transfer tube.

[0057] Step 3: The calculation module uses the relevant calculation methods in the relevant calculation methods of ASME and public literature to complete the calculation of turbulent excitation, and generates output files, including the displacement and stress results of the heat transfer tube under turbulent excitation.

[0058] Step 4: The calculation module uses the relevant calculation methods in the relevant calculation methods of ASME and public literature to complete the calculation of vortex shedding, and generates output files, including the displacement and stress results of the heat transfer tube under vortex shedding excitation.

[0059] In the wear monitoring module of the heat transfer tube, the wear prediction algorithm is used to predict and analyze the wear condition of the subsequent heat transfer tube, and a pipe plugging suggestion method is given. The wear prediction algorithm is carried out in the following steps:

[0060] Step 1: According to the detection data of each major overhaul, enter the data of the wear depth, wear length, and wear morphology of each heat transfer tube with wear into the wear database to form a data table.

[0061] Step 2: According to the different wear depths, wear lengths, and wear morphologies, use geometric methods to give the relationship between the wear depth and wear volume at each type of wear point, and convert the wear depth into wear volume loss.

[0062] Step 3: Assume that the wear volume growth rate of a wear point per unit time is constant, and calculate the volume loss rate according to the already occurred wear volume loss and time.

[0063] Step 4: The volume loss at the end of the next cycle = existing volume loss + volume loss rate * time + uncertainty of volume loss measurement. The uncertainty of volume measurement depends on the calibration test of the eddy current detection of the heat transfer tube.

[0064] Step 5: Calculate the wear depth at the end of the next cycle according to the wear depth and wear volume.

[0065] Step 6: Give pipe plugging suggestions according to the pipe plugging criteria.

[0066] All data is visualized.

[0067] As Figure 4 shown, the overview of the overall operation of the equipment is the overview of the monitoring data of the steam generator, which can summarize and display the real-time data in the remaining modules, including but not limited to the real-time change curves of the outlet steam pressure, outlet steam flow, coolant flow, main feed water flow, etc., and the real-time status of alarm items such as fatigue, loose parts, and secondary side radioactive leakage. When abnormal data is detected, an alarm reminder is sent to the operator.

[0068] As Figures 4 - 11 shown, in the intelligent monitoring system of the steam generator, buttons can be selected to enter the corresponding modules. The steam generator to be monitored can be selected for monitoring.

[0069] Specifically, in the intelligent monitoring system of the steam generator of a nuclear power plant, buttons in the upper area (00) can be used to enter each module; buttons in the area (01) can be used to switch between groups / sites / units to select the corresponding steam generator;

[0070] In the overview of the overall operation of the equipment, the results of flow-induced vibration calculation can be displayed by button (11); the results of fouling factor calculation can be displayed by button (12); the results of loose part mass estimation can be displayed in area (13); whether the data of the steam generator is abnormal can be observed in area (14), and the data curves of the outlet steam pressure, outlet steam flow, coolant inlet flow, main feed water flow, etc. of the steam generator can be observed in area (15).

[0071] In the thermal performance monitoring section of the equipment, buttons in area (21) can be used for debugging or diagnostic functions; data such as the outlet pressure, flow rate, feed water temperature, water level height, blowdown flow rate, inlet temperature, operating pressure, pump flow rate, fouling factor, and circulation ratio of the steam generator are displayed in area (22), and real-time curves are shown; alarm information is displayed at area (23); the outlet steam pressure, coolant inlet flow rate, outlet steam flow rate, and main feed water flow rate are displayed at area (24).

[0072] In the equipment flow field digital twin module, flow field calculation can be performed by button (31); corresponding physical quantities such as flow velocity, temperature, void fraction, and density can be selected in the selection box (32), and the physical quantity contour maps corresponding to two mutually perpendicular longitudinal sections can be displayed in area (33). After selecting time in the selection box (34), position in the selection box (35), and physical quantities in the selection boxes (36) and (37), arbitrary corresponding physical quantity contour maps can be generated at area (38).

[0073] In the flow-induced vibration monitoring module of the heat transfer tube, the input flow field can be selected through the selection box (41). The current flow field or the flow field calculated at any other time can be selected. The content to be calculated can be selected through the selection box (42), such as the fluid-elastic stability ratio in the elbow section, the fluid-elastic stability ratio in the straight pipe section, vortex shedding, turbulent excitation. Click the button (43) to start the calculation, and the contour map of the corresponding physical quantity will be generated in the area (44).

[0074] In the wear monitoring module of the heat transfer tube, the time (next major overhaul or end of service life) can be selected through the selection box (51); the contour map of the wear condition of the heat transfer tube is displayed in the area (52); the number of heat transfer tubes with different wear amounts is displayed in the area (53); the brand serial number of the heat transfer tube to be viewed is entered at the text box (54), and the wear condition of the heat transfer tube is displayed in the area (55); click the button (56) to export the report related to the wear condition of the heat transfer tube; when there is a value for the secondary loop radiation dose, an alarm is given in the area (57).

[0075] In the equipment fatigue damage monitoring module, the three-dimensional view of the steam generator water chamber head is displayed in the area (61), and the locations of the fatigue monitoring points are marked in the view. The fatigue damage factor values of the monitoring points are displayed in the area (62), including information such as serial number, monitoring point, description, CUF, EAF, calculation time, status, etc., and the fatigue factors are monitored and alarmed. After selecting the corresponding part and time at the selection box (63), the historical fatigue damage factor curve can be displayed in the area (64).

[0076] In the loose parts monitoring module of the equipment, the view of the steam generator is displayed in the area (71), and the positions of the loose part sensors are marked. When a loose part alarm event occurs, the positions of the sensor measuring points triggered by the alarm are displayed in red; the analysis data is imported at the selection box (72), and the calculation will be automatically performed after the import; the original waveform, positioning analysis, and quality estimation are selected in the area (73), and the corresponding analysis results can be obtained; the corresponding waveform diagram or other result diagrams are displayed in the area (74), and the analysis result table is displayed in the area (75).

[0077] In the data and file management module, the various parameters of the steam generator in the design stage can be viewed through the button (81), the various parameters to be tracked of the steam generator in the manufacturing stage can be viewed through the button (82), and the various parameters to be tracked of the steam generator during operation can be viewed through the button (83); the corresponding parameter values and tables are displayed in the area (84); the files related to the steam generator in each stage are in the area (85). In the design stage, they are design atlases, design specifications, and maintenance manuals. In the manufacturing stage, they are as-built drawings, completion reports, and maintenance manuals. In the operation stage, they are operation procedures and in-service inspection reports. Click the corresponding button to call the relevant files for viewing.

[0078] Embodiment 2

[0079] In one embodiment of the present disclosure, a monitoring system for a steam generator of a nuclear power plant is provided, as Figures 4 - 11 shown, including:

[0080] A sensor for acquiring data of each measuring point;

[0081] An equipment thermal performance monitoring module for performing thermal performance calculation and analysis on all the data of each measuring point obtained and then outputting secondary side data;

[0082] An equipment flow field data twin module for performing flow field distribution calculation on the secondary side data and then outputting flow field data;

[0083] A heat transfer tube fluid-induced vibration monitoring module for obtaining the heat transfer tube fluid-induced vibration results by using the flow field data and calculation methods of fluid-solid stability ratio, vortex shedding, and turbulent excitation;

[0084] A heat transfer tube wear monitoring module for analyzing the wear data of the heat transfer tube by using a wear prediction algorithm to obtain a tube plugging method;

[0085] An equipment fatigue damage monitoring module, and the equipment fatigue damage monitoring module is connected to a fatigue monitoring system database.

[0086] An equipment loose parts monitoring module, and the equipment loose parts monitoring module is connected to a loose parts monitoring system database.

[0087] In the intelligent monitoring system of the steam generator, there are a total of eight modules above. You can select a button to enter the corresponding module. You can select the steam generator you want to monitor for monitoring.

[0088] In the intelligent monitoring system of the steam generator of the nuclear power plant, you can enter each module through the buttons in the upper area (00); you can switch the group / site / unit through the buttons in the area (01) and select the corresponding steam generator;

[0089] In the overview of the overall operation of the equipment, you can display the fluid-induced vibration calculation results through the button (11); you can display the fouling coefficient calculation results through the button (12); you can display the loose parts mass estimation results in the area (13); you can observe whether the data of the steam generator is abnormal in the area (14), and you can observe the data curves of the outlet steam pressure, outlet steam flow, coolant inlet flow, main feed water flow, etc. of the steam generator in the area (15).

[0090] In the equipment thermal performance monitoring section, debugging or diagnostic functions can be performed through the buttons in area (21); in area (22), data such as the outlet pressure, flow rate, feed water temperature, water level height, blowdown flow rate, inlet temperature, operating pressure, pump flow rate, fouling factor, and circulation ratio of the steam generator are displayed, and real-time curves are shown; alarm information is displayed at area (23); the outlet steam pressure, coolant inlet flow rate, outlet steam flow rate, and main feed water flow rate are displayed at area (24).

[0091] In the equipment flow field digital twin module, flow field calculations can be performed through button (31); corresponding physical quantities such as flow velocity, temperature, void fraction, and density can be selected in selection box (32), and the physical quantity contour maps corresponding to two mutually perpendicular longitudinal cross-sections can be displayed in area (33). After selecting time in selection box (34), position in selection box (35), and physical quantities in selection boxes (36) and (37), arbitrary corresponding physical quantity contour maps can be generated at area (38).

[0092] In the heat transfer tube fluid-induced vibration monitoring module, the input flow field can be selected through selection box (41), and the current flow field or the flow field calculated at any other time can be selected. The content to be calculated, such as the fluid-elastic stability ratio in the elbow section, the fluid-elastic stability ratio in the straight pipe section, vortex shedding, and turbulent excitation, can be selected through selection box (42). Click button (43) to start the calculation, and the contour map of the corresponding physical quantity is generated in area (44).

[0093] In the described heat transfer tube wear monitoring module, data such as the required wear amount of the heat transfer tube and the offset of the wear position are input by obtaining data during each major overhaul. In the equipment fatigue damage monitoring module, the fatigue cumulative factors of each component are imported from the fatigue monitoring system already installed in the nuclear power plant. In the equipment loose component monitoring module, the loose part signals at each position are imported from the loose part monitoring system already installed in the nuclear power plant.

[0094] In the heat transfer tube wear monitoring module, time (next major overhaul or end of service life) can be selected through selection box (51); the contour map of the heat transfer tube wear condition is displayed in area (52); the number of heat transfer tubes with different wear amounts is displayed in area (53); the row number and column number of the heat transfer tube that you want to view are input at text box (54), and the wear condition of the heat transfer tube is displayed at area (55); click button (56) to export the report related to the heat transfer tube wear condition; when there is a value for the secondary circuit radiation dose, an alarm is given in area (57).

[0095] In the device fatigue damage monitoring module, a 3D view of the steam generator water chamber head is displayed at area (61), and the fatigue monitoring point locations are marked in the view. At area (62), the fatigue damage factor values of the monitoring points are displayed, including information such as serial number, monitoring point, description, CUF, EAF, calculation time, status, etc., and the fatigue factors are monitored and alarmed. After selecting the corresponding location and time at the selection box (63), the historical fatigue damage factor curve can be displayed at area (64).

[0096] In the device loose component monitoring module, a view of the steam generator is displayed at area (71), and the positions of the loose component sensors are marked. When a loose component alarm event occurs, the sensor measurement points where the alarm is triggered are displayed in red; data for analysis is imported at the selection box (72), and calculations will be automatically performed after import; the original waveform, positioning analysis, and quality estimation are selected at area (73) to obtain the corresponding analysis results; the corresponding waveform diagram or other result diagrams are displayed at area (74), and the analysis result table is displayed at area (75).

[0097] In the data and file management module, the data and file management module is the data storage module of this monitoring system, recording the relevant data of the steam generator in the design, manufacturing, and operation stages. Design atlases, design specifications, maintenance manuals in the design stage, as-built drawings, completion reports, maintenance manuals in the manufacturing stage, operation procedures, in-service inspection reports in the operation stage, etc. can be called, providing a more convenient path for operators to access relevant content. The various parameters of the steam generator in the design stage can be viewed through button (81), the various parameters that need to be tracked of the steam generator in the manufacturing stage can be viewed through button (82), and the various parameters that need to be tracked of the steam generator during operation can be viewed through button (83); the corresponding parameter values and tables are displayed at area (84); the files related to the steam generator in each stage are at area (85), which are design atlases, design specifications, maintenance manuals in the design stage, as-built drawings, completion reports, maintenance manuals in the manufacturing stage, operation procedures, in-service inspection reports in the operation stage, and the relevant files can be called for viewing by clicking the corresponding button.

[0098] These computer program instructions can also be loaded onto a computer or other programmable data processing device, so that a series of operation steps are executed on the computer or other programmable device to generate a computer-implemented process, and thus the instructions executed on the computer or other programmable device provide steps for implementing the functions specified in Figure 1 one process or multiple processes and / or boxes Figure 1 one box or multiple boxes.

[0099] Although the specific embodiments of the present disclosure have been described above in conjunction with the accompanying drawings, they are not intended to limit the scope of protection of the present disclosure. Those skilled in the art should understand that various modifications or variations that can be made without creative efforts on the basis of the technical solutions of the present disclosure are still within the scope of protection of the present disclosure.

Claims

1. A monitoring method for a steam generator of a nuclear power plant, characterized in that, Including: Determine the original measuring points and obtain the data of each measuring point; After performing thermal performance calculation and analysis on all the data of each obtained measuring point, output the secondary side data; Directly call a part of the output parameters, and the part of the parameters includes the circulation ratio and the fouling factor; After performing flow field distribution calculation on the secondary side data, output the flow field data; Using the flow field data and the calculation methods of flow bullet stability ratio, vortex shedding, and turbulent excitation, obtain the flow-induced vibration results of the heat transfer tubes; Analyze the wear data of the heat transfer tubes using the wear prediction algorithm to obtain the tube plugging method; Using the wear prediction algorithm, conduct predictive analysis on the wear condition of the heat transfer tubes. The wear prediction algorithm adopts the following steps: Step 1: According to the detection data of each major overhaul, enter the data of the wear depth, wear length, and wear morphology of each heat transfer tube with wear in the wear database to form a data table; Step 2: According to the differences in wear depth, wear length, and wear morphology, use geometric methods to give the relationship between the wear depth and wear volume at each type of wear point, and convert the wear depth into wear volume loss; Step 3: Assume that the wear volume growth rate of a wear point per unit time is constant, and calculate the volume loss rate based on the already occurred wear volume loss and time; Volume loss at the end of the next cycle = existing volume loss + volume loss rate * time + uncertainty in volume measurement; The uncertainty in volume measurement depends on the calibration test of eddy current detection of the heat transfer tubes; Step 5: Calculate the wear depth at the end of the next cycle according to the wear depth and wear volume; All data can be visualized.

2. The monitoring method of a steam generator of a nuclear power plant according to claim 1, wherein, The data of each measuring point includes thermal power, primary loop temperature, pressure, outlet steam flow rate, secondary side water level, feed water temperature, outlet steam pressure, coolant inlet flow rate, and blowdown flow rate.

3. The monitoring method of a steam generator of a nuclear power plant according to claim 1, wherein, The secondary side data output after performing thermal performance calculation and analysis includes secondary side steam space pressure, secondary side inlet flow rate and temperature, and secondary side heat transfer distribution data.

4. The monitoring method of a steam generator of a nuclear power plant according to claim 1, characterized in that The flow field data is the flow velocity between the heat transfer tubes, the mixed density of the heat transfer tubes, the equivalent void fraction between the heat transfer tubes, and the equivalent temperature between the heat transfer tubes.

5. The monitoring method of a steam generator of a nuclear power plant according to claim 1, characterized in that, Using flow field reduction and data visualization to calculate the flow field distribution in the steam generator, obtaining the flow field distribution results and relevant flow field data.

6. The monitoring method of a steam generator of a nuclear power plant according to claim 1, wherein, Visualize the data display, showing the cloud map of the wear condition of the heat transfer tubes and the number of heat transfer tubes with different wear amounts.

7. The monitoring method of a steam generator of a nuclear power plant according to claim 1, characterized in that Display the steam generator view, mark the position of the loose part sensor, and when a loose part alarm event occurs, the measuring point position of the sensor triggered by the alarm is displayed in red.

8. A monitoring system for a steam generator of a nuclear power plant, characterized in that, Including: Sensors for obtaining the data of each measuring point; The equipment thermal performance monitoring module is used to perform thermal performance calculation and analysis on all the data of each obtained measuring point and then output the secondary side data; A part of the output parameters is directly called, and the part of the parameters includes the circulation ratio and the fouling factor; The equipment flow field data twin module is used to perform flow field distribution calculation on the secondary side data and then output the flow field data; The heat transfer tube flow-induced vibration monitoring module is used to obtain the flow-induced vibration results of the heat transfer tubes using the flow field data and the calculation methods of flow bullet stability ratio, vortex shedding, and turbulent excitation; The heat transfer tube wear monitoring module is used to analyze the wear data of the heat transfer tubes by using a wear prediction algorithm to obtain a tube plugging method; Using the wear prediction algorithm, predict and analyze the wear condition of the heat transfer tubes. The wear prediction algorithm adopts the following steps: Step 1: According to the detection data of each major overhaul, enter the data of the wear depth, wear length, and wear morphology of each heat transfer tube with wear into the wear database to form a data table; Step 2: According to the differences in wear depth, wear length, and wear morphology, use geometric methods to give the relationship between the wear depth and wear volume at each type of wear point, and convert the wear depth into wear volume loss; Step 3: Assume that the wear volume growth rate of a wear point per unit time is constant, and calculate the volume loss rate according to the occurred wear volume loss and time; The volume loss at the end of the next cycle = existing volume loss + volume loss rate * time + uncertainty of volume measurement; The uncertainty of volume measurement depends on the calibration test of the eddy current detection of the heat transfer tubes; Step 5: Calculate the wear depth at the end of the next cycle according to the wear depth and wear volume; All data can be visualized.

9. The monitoring system of a nuclear power plant steam generator according to claim 8, characterized in that It also includes an equipment fatigue damage monitoring module, and the equipment fatigue damage monitoring module is connected to the fatigue monitoring system database.

10. The monitoring system of a nuclear power plant steam generator according to claim 8, characterized in that It also includes an equipment loose component monitoring module, and the equipment loose component monitoring module is connected to the loose component monitoring system database.

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