Online protection parameter rapid evaluation method based on control rod position information

Abstract

The invention relates to the technical field of nuclear engineering and reactor safety control. The online protection parameter rapid evaluation method based on the rod position information of the control rod comprises the following steps: simulating reactor core states under a plurality of sets of preset rod positions based on real-time burnup data of a reactor core; obtaining a first intermediate parameter corresponding to the reactor core state under each set of preset rod position, and collecting real-time electric signal data and real-time rod position data; according to the first intermediate parameter, correcting the first intermediate parameter by the actually measured rod position data of the reactor to obtain a second intermediate parameter; on the basis of the second intermediate parameter and the real-time electric signal data, calculating an online protection parameter of the reactor core; and based on the online protection parameters of the reactor core and according to a preset protection parameter threshold, evaluating the safety margin of the reactor core through a rapid evaluation module. The problems that the overall calculation uncertainty of an online protection system of an existing online protection method is high, and the improvement effect of an online protection technology on the operation range of a reactor cannot be fully played are solved.

Description

Technical Field

[0001] The invention relates to the field of nuclear engineering technology and reactor safety control technology, and in particular to an online protection parameter rapid evaluation method based on control rod position information. Background Art

[0002] When traditional second-generation and second-generation pressurized water reactor nuclear power plants are in operation, they rely on the set operating diagrams and over-temperature and over-power protection channels to protect the operating units. The reactor protection logic designed based on the operating diagram is relatively conservative, which affects the flexibility of reactor operation, limits the operating range of the reactor, and thus affects the economic efficiency of nuclear power plant operation.

[0003] The existing Russian VVER1000 and French EPR models both implement online protection of the core operation, but the online protection technologies of the above two models are based on large uncertainties. The reason for the large uncertainty of the above online protection technology is that the accuracy of the intermediate parameters used to calculate its protection parameters is affected by the change of the reactor core state. The core state changes significantly during the reactor transient process, and the intermediate parameters and the core state do not match, which leads to large uncertainty in the calculation of the protection parameters. The effect of increasing the core operation range brought by the original online protection technology is affected by the large uncertainty, resulting in a relatively reduced core operation range, and the online protection technology cannot fully play its role in improving the reactor operation range. Summary of the invention

[0004] The purpose of the present invention is to provide a method for rapid evaluation of online protection parameters based on control rod position information, aiming to solve the problem that the overall calculation uncertainty of the online protection system of the existing online protection method is high and the role of online protection technology in improving the operating range of the reactor cannot be fully utilized.

[0005] The present invention is achieved through the following technical solutions:

[0006] A method for quickly evaluating online protection parameters based on control rod position information comprises the following steps:

[0007] Based on the real-time fuel consumption data of the core, the simulation module is used to simulate the core status under several sets of preset rod positions;

[0008] Acquire the first intermediate parameter corresponding to the core state under each set of preset rod positions during the simulation process, collect the real-time electrical signal data of the core measurement system and the real-time rod position data of the reactor control system, and feed back the first intermediate parameter, the real-time electrical signal data and the real-time rod position data to the rapid evaluation module;

[0009] According to the first intermediate parameter, the first intermediate parameter is corrected by the rapid evaluation module with the actual measured rod position data of the reactor to obtain the second intermediate parameter;

[0010] Based on the second intermediate parameter and the real-time electrical signal data, the online protection parameters of the core are calculated through the fast evaluation module;

[0011] Based on the online protection parameters of the core and according to the preset protection parameter thresholds, the safety margin of the core is evaluated through the rapid evaluation module.

[0012] Optionally, the specific process of simulating the core states under several sets of preset rod positions through the simulation module based on the real-time burnup data of the core is:

[0013] The real-time fuel consumption data of the core is obtained and a simulation cycle is preset; based on the simulation cycle, several core simulation models are periodically established, each cycle corresponds to a core simulation model, and each core simulation model simulates the core state under a set of preset rod positions.

[0014] Optionally, according to the actual layout and performance parameters of the detectors of the core measurement system, corresponding detector parameters are set in the simulation model; the simulation model is run to simulate the neutron flux distribution and radiation intensity of the core under different preset rod positions, the theoretical electrical signal data corresponding to the detectors are calculated, and the power distribution data of the core is extracted from the simulation results.

[0015] Optionally, the first intermediate parameters include: component-level networking three-dimensional power distribution parameters and fuel rod-level refined three-dimensional power distribution parameters.

[0016] Optionally, the specific process of collecting the real-time electrical signal data of the core measurement system and the real-time rod position data of the reactor control system is:

[0017] The core measurement system collects real-time data on electrical signals generated by neutron flux or related radiation in the core through the detector array arranged around the core; and obtains real-time rod position data of all control rods in the reactor through the reactor control system.

[0018] Optionally, the specific process of obtaining the second intermediate parameter by correcting the first intermediate parameter with the reactor measured rod position data through the rapid evaluation module according to the first intermediate parameter is:

[0019] The rapid evaluation module receives the first intermediate parameters under each set of preset rod positions transmitted by the simulation module, and corrects the first intermediate parameters with the reactor measured rod position data through interpolation or fitting method according to the real-time collected control rod position data to obtain the second intermediate parameters.

[0020] Optionally, the specific process of calculating the online protection parameter of the core through the fast evaluation module based on the second intermediate parameter and the real-time electrical signal data is:

[0021] The rapid evaluation module calculates the online protection parameters of the current core according to the corrected second intermediate parameter and the electrical signal data collected in real time by the core measurement system through a pre-set protection parameter calculation model.

[0022] Optionally, the specific construction process of the protection parameter calculation model is:

[0023] According to the physical characteristics of the core and the operating principle of the reactor, key parameters reflecting the safety of the core are selected;

[0024] Based on the historical operation data and experimental data of the core, the correlation between key parameters and core online protection parameters is analyzed, and a mathematical relationship model between key parameters and online protection parameters is established through statistical methods or machine learning algorithms;

[0025] Verify and optimize the established mathematical relationship model to ensure that it can accurately reflect the actual operating status of the core and has good predictive capabilities;

[0026] The verified and optimized mathematical relationship model is used as a protection parameter calculation model and integrated into the rapid evaluation module for real-time calculation of the online protection parameters of the core.

[0027] Optionally, the specific process of evaluating the safety margin of the core by the fast evaluation module based on the online protection parameters of the core and according to the preset protection parameter threshold is:

[0028] The rapid evaluation module compares the calculated online protection parameters with the preset protection parameter thresholds to evaluate the safety margin of the current core operation; if the online protection parameters exceed the protection parameter thresholds, an early warning is issued or a protection action is triggered; based on the safety margin, the reactor operation strategy is optimized.

[0029] Optionally, based on the optimized reactor operation strategy, the position of the control rods is adjusted through the reactor control system so that the reactor operates within a safety margin range; the evaluation results and the adjustment measures taken are fed back to the simulation module to optimize the parameter configuration of the simulation module.

[0030] The technical solution of the present invention has at least the following advantages and beneficial effects:

[0031] Improve the flexibility and economy of reactor operation: Through the online protection parameter rapid evaluation method based on control rod position information, the protection parameters can be adjusted more accurately according to the actual operating status of the reactor, avoiding the conservatism brought about by the traditional reactor protection logic based on operation diagram design, which helps to expand the operating range of the reactor and improve the operating flexibility of the reactor, thereby optimizing the operating efficiency and economy of the nuclear power plant.

[0032] Reducing the uncertainty of online protection technology: By collecting the electrical signal data of the core measurement system and the rod position data of the reactor control system in real time, and combining it with the core state simulated by the simulation module, the intermediate parameters are corrected to obtain a more accurate second intermediate parameter. This effectively reduces the problem of mismatch between the intermediate parameters and the core state caused by changes in the core state during the reactor transient process, reduces the uncertainty of online protection technology, and enables the core operation range to be expanded more accurately.

[0033] Enhanced reactor safety: The online protection parameters calculated based on the corrected intermediate parameters and real-time electrical signal data can more accurately reflect the actual safety status of the reactor; the evaluation of the core safety margin by the rapid evaluation module can timely discover and respond to potential safety risks, ensure that the reactor operates under conditions with sufficient safety margin, and improve the overall safety of the reactor.

[0034] Improve the automation and intelligence level of nuclear power plants: The implementation of this invention relies on advanced simulation technology and real-time data acquisition technology, which realizes real-time monitoring and rapid evaluation of the reactor status, which not only improves the automation level of nuclear power plants, but also provides strong support for the intelligent operation of nuclear power plants, and helps to promote the development of nuclear power plants in a more efficient, safe and intelligent direction. BRIEF DESCRIPTION OF THE DRAWINGS

[0035] Figure 1 Schematic diagram of a flow chart of an online protection parameter rapid evaluation method based on control rod position information according to Embodiment 1 of the present invention;

[0036] Figure 2 It is a structural schematic diagram of the online protection system in the online protection parameter rapid evaluation method based on control rod position information of Example 1 of the present invention. DETAILED DESCRIPTION

[0037] The following is a specific implementation method in conjunction with the drawings.

[0038] Example 1

[0039] Reference Figure 1 , Figure 2 , a method for quickly evaluating online protection parameters based on control rod position information, comprising the steps of:

[0040] Step 1: Based on the real-time fuel consumption data of the core, the core status under several sets of preset rod positions is simulated through the simulation module.

[0041] In this embodiment, based on the real-time burnup data of the core, the specific process of simulating the core state under several sets of preset rod positions through the simulation module is as follows:

[0042] The real-time fuel consumption data of the core is obtained and a simulation cycle is preset; based on the simulation cycle, several core simulation models are periodically established, each cycle corresponds to a core simulation model, and each core simulation model simulates the core state under a set of preset rod positions.

[0043] In this embodiment, the rod position data in each set of preset rod positions is the rod position data corresponding to the designated control rod.

[0044] In this embodiment, the latest core burnup data is obtained from the fuel management system of the reactor. The core burnup data includes key information such as the burnup depth, residual reactivity, and fission product accumulation of the fuel assembly. The update frequency of the burnup data is determined according to the operating status and monitoring requirements of the reactor. During the stable operation of the reactor, a lower update frequency can be set; during key operations such as reactor startup, shutdown, or power adjustment, the data update frequency is increased to ensure the accuracy of the data.

[0045] In this embodiment, the setting of the simulation cycle should comprehensively consider the availability of computing resources, the stability of the reactor operation state, and the requirements for real-time performance. The simulation cycle can be adjusted according to the operation of the reactor and the accuracy of the simulation results. For example, in the early stage of reactor operation, due to the rapid change of fuel consumption, the simulation cycle can be appropriately shortened; after the reactor operation is stable, the simulation cycle can be extended to reduce the amount of calculation.

[0046] In this embodiment, the core simulation model is constructed based on the physical characteristics and operating principles of the reactor, including the core structure, fuel assembly characteristics, neutron transport process, etc. The core simulation model can accurately simulate the behavior of the reactor under different rod positions. The rod positions are preset according to the operating requirements and safety requirements of the reactor. The rod positions of the control rods include normal operating rod positions, maximum insertion rod positions, minimum withdrawal rod positions, etc. By simulating the core state under multiple rod positions, the performance of the reactor under different operating conditions can be evaluated. In each simulation cycle, a corresponding core simulation model is established based on the real-time burnup data of the core and the preset rod positions. By running the simulation model, the core state under each set of preset rod positions can be simulated. For each core simulation model, by simulating physical processes such as neutron transport and heat conduction, key parameters such as power distribution and temperature distribution in the core can be calculated. These parameters are important bases for evaluating reactor performance and safety.

[0047] Step 2: Obtain the first intermediate parameter corresponding to the core state under each set of preset rod positions during the simulation process, collect the real-time electrical signal data of the core measurement system and the real-time rod position data of the reactor control system, and feed back the first intermediate parameter, real-time electrical signal data and real-time rod position data to the rapid evaluation module.

[0048] In this embodiment, the core measurement system, the simulation module and the rapid evaluation module constitute an online protection system. Figure 2 As shown, the core measurement system is connected to the simulation module and the rapid evaluation module respectively, and the simulation module is connected to the rapid evaluation module. The rapid evaluation module feeds back the core operation safety margin to the reactor control system.

[0049] In this embodiment, the specific process of obtaining the first intermediate parameter corresponding to the core state under each set of preset rod positions during the simulation is as follows:

[0050] The simulation module is used to simulate the response signals of each detector of the core measurement system, simulate the core state under several sets of preset rod positions, and obtain the theoretical electrical signal data corresponding to each detector; based on the theoretical electrical signal data, the simulation module is used to calculate and obtain the first intermediate parameters corresponding to each core state. Among them, the first intermediate parameters include: the three-dimensional power distribution parameters of the network at the component level and the fine three-dimensional power distribution parameters at the fuel rod level.

[0051] In this embodiment, according to the actual layout and performance parameters of the detectors of the core measurement system, the corresponding detector parameters are set in the simulation model; the simulation model is run to simulate the neutron flux distribution and radiation intensity of the core at different preset rod positions, and the theoretical electrical signal data corresponding to the detector is calculated. The power distribution data of the core is extracted from the simulation results, including the networked three-dimensional power distribution at the component level and the fine three-dimensional power distribution at the fuel rod level; based on the extracted power distribution data, professional calculation methods and tools (such as MATLAB, Python, etc.) are used to calculate the first intermediate parameters under each set of preset rod positions. The first intermediate parameters include the average power, maximum power, power deviation, power peak factor, etc. of the core.

[0052] In this embodiment, the specific process of collecting the real-time electrical signal data of the core measurement system and the real-time rod position data of the reactor control system is as follows:

[0053] The core measurement system collects real-time data on electrical signals generated by neutron flux or related radiation in the core through the detector array arranged around the core; and obtains real-time rod position data of all control rods in the reactor through the reactor control system.

[0054] In this embodiment, a stable data transmission channel is established between the simulation module, the core measurement system and the reactor control system; the first intermediate parameter calculated by the simulation module, the real-time electrical signal data collected by the core measurement system and the real-time rod position data collected by the reactor control system are transmitted to the rapid evaluation module in real time; a data storage module is established in the rapid evaluation module to store the received first intermediate parameter, real-time electrical signal data and real-time rod position data.

[0055] Step 3: Based on the first intermediate parameter, the intermediate parameter of the real-time rod position data is corrected through the rapid evaluation module to obtain the second intermediate parameter.

[0056] In this embodiment, according to the first intermediate parameter, the intermediate parameter of the real-time rod position data is corrected by the rapid evaluation module to obtain the second intermediate parameter in the following specific process:

[0057] The rapid evaluation module receives the first intermediate parameters under each set of preset rod positions transmitted by the simulation module, and corrects the first intermediate parameters with the reactor measured rod position data through interpolation or fitting method according to the real-time collected control rod position data to obtain the second intermediate parameters.

[0058] In this embodiment, the rapid evaluation module matches the received control rod position data with the preset rod position in the simulation module to find the preset rod position closest to the current measured rod position; if the current measured rod position does not completely match the preset rod position, the rapid evaluation module will use the interpolation method to calculate the intermediate parameter under the current measured rod position according to the first intermediate parameter under the preset rod position. The interpolation method can select linear interpolation, quadratic interpolation or a higher-order interpolation method according to the actual situation to ensure the accuracy of the calculation. After completing the rod position data matching and interpolation, the rapid evaluation module compares the calculated intermediate parameter under the current measured rod position with the first intermediate parameter under the preset rod position transmitted by the simulation module, and corrects the intermediate parameter according to the comparison result. The purpose of the correction is to make the intermediate parameter closer to the actual operating state of the current core, thereby improving the calculation accuracy of the online protection parameter. After correction, the rapid evaluation module will output the second intermediate parameter based on the current measured rod position information. The second intermediate parameter will be used for subsequent online protection parameter calculation and safety margin evaluation. 。

[0059] Step 4: Based on the second intermediate parameter and the real-time electrical signal data, the online protection parameters of the core are calculated through the fast evaluation module.

[0060] In this embodiment, based on the second intermediate parameter and the real-time electrical signal data, the specific process of calculating the online protection parameter of the core through the rapid evaluation module is as follows:

[0061] The rapid evaluation module calculates the online protection parameters of the current core according to the second intermediate parameter and the electrical signal data collected in real time by the core measurement system through a preset protection parameter calculation model.

[0062] In this embodiment, the rapid evaluation module first receives the first intermediate parameter under each set of preset rod positions transmitted from the simulation module; at the same time, the rapid evaluation module also receives the electrical signal data collected in real time by the core measurement system. The rapid evaluation module has a built-in protection parameter calculation model, which is constructed based on the physical characteristics of the core and the operating principle of the reactor; the protection parameter calculation model selects key parameters reflecting the safety of the core, such as power peak factor, power distribution unevenness, etc., and establishes a mathematical relationship between these key parameters and online protection parameters. The rapid evaluation module inputs the second intermediate parameter and real-time electrical signal data into the protection parameter calculation model, and the protection parameter calculation model finally calculates the online protection parameters of the current core through a series of calculation steps based on the input data. After the calculation is completed, the rapid evaluation module outputs the online protection parameters to the reactor protection system or other related systems; at the same time, it is compared with the preset protection parameter threshold to provide a basis for subsequent safety margin evaluation.

[0063] Step 5: Based on the online protection parameters of the core and according to the preset protection parameter thresholds, the safety margin of the core is evaluated through the rapid evaluation module.

[0064] In this embodiment, based on the online protection parameters of the core and according to the preset protection parameter threshold, the specific process of evaluating the safety margin of the core by the fast evaluation module is as follows:

[0065] The rapid evaluation module compares the calculated online protection parameters with the preset protection parameter thresholds to evaluate the safety margin of the current core operation; if the online protection parameters exceed the protection parameter thresholds, an early warning is issued or a protection action is triggered, including emergency shutdown, control rod insertion, etc., to ensure that the reactor operates in a safe state; based on the safety margin, the reactor operation strategy is optimized, including adjusting the reactor power, changing the control rod position, optimizing the core fuel management, etc.

[0066] In this embodiment, the protection parameter threshold is determined based on the reactor's design safety standards and historical operating experience to ensure that the reactor operates within a safe range. The safety margin refers to the difference between the current operating state of the reactor and the conditions required to trigger the protection action, which reflects the safety level of the reactor's operation.

[0067] In this embodiment, during the operation of the reactor, the rapid evaluation module continuously monitors the online protection parameters and safety margin of the core, and immediately issues an early warning or triggers a protection action once an abnormality or potential risk is detected; regularly conducts safety assessments on the operating status of the reactor, and adjusts the reactor's operating strategy and maintenance plan based on the assessment results.

[0068] In this embodiment, based on the optimized reactor operation strategy, the position of the control rods is adjusted through the reactor control system so that the reactor operates within a safety margin range; the evaluation results and the adjustment measures taken are fed back to the simulation module to optimize the parameter configuration of the simulation module.

[0069] Example 2

[0070] Based on Example 1, in this embodiment, the specific construction process of the protection parameter calculation model is as follows:

[0071] According to the physical characteristics of the core and the operating principle of the reactor, key parameters reflecting the safety of the core are selected; based on the historical operating data and experimental data of the core, the correlation between the key parameters and the online protection parameters of the core is analyzed, and a mathematical relationship model between the key parameters and the online protection parameters is established through a machine learning algorithm; the established mathematical relationship model is verified and optimized to ensure that it can accurately reflect the actual operating status of the core and has good predictive ability; the verified and optimized mathematical relationship model is used as a protection parameter calculation model and integrated into the rapid evaluation module for real-time calculation of the online protection parameters of the core.

[0072] In this embodiment, the specific process of building a protection parameter calculation model based on a machine learning algorithm is as follows:

[0073] From the reactor's operating records, experimental data, and simulation results, key parameters related to core safety (such as power peak factor, power distribution unevenness, average core temperature, etc.) and corresponding online protection parameters (such as maximum allowable power, minimum safety margin, etc.) are collected. The collected data is cleaned to remove outliers and missing values ​​to ensure data accuracy and consistency. At the same time, the data is standardized or normalized to improve the training efficiency and accuracy of the machine learning model.

[0074] According to the physical characteristics of the core and the operating principle of the reactor, it is necessary to deeply analyze which key parameters have the greatest impact on the online protection parameters. This can be obtained with the help of expert knowledge, literature research or experimental verification. Based on the analysis results, the most representative key parameters are selected as features for building a machine learning model. These features should be able to fully reflect the safety status of the core.

[0075] According to the complexity of the problem and the characteristics of the data, select a suitable machine learning algorithm. Machine learning algorithms such as linear regression, support vector machine, random forest, neural network, etc. can be used. In this embodiment, a support vector machine is used to construct an initial protection parameter calculation model. The preprocessed data is divided into a training set and a test set, and the initialized support vector machine is trained using the training set data to obtain the initial protection parameter calculation model. During the training process, overfitting can be prevented by methods such as cross-validation. The trained model is verified using the test set data to evaluate its prediction accuracy and generalization ability. The performance of the model can be quantified by calculating indicators such as mean square error (MSE), root mean square error (RMSE), and accuracy. According to the verification results, the initial protection parameter calculation model is tuned to obtain a protection parameter calculation model. The tuning methods include adjusting algorithm parameters, adding features, using more complex model structures, etc. The optimized model can more accurately predict online protection parameters.

[0076] The protected parameter calculation model is integrated into the rapid evaluation module. The integrated rapid evaluation module is deployed into the reactor control system for actual operation test. During the test, the difference between the model's prediction results and the actual operation status is closely monitored, and the model is adjusted and optimized in a timely manner.

[0077] During the operation of the reactor, the rapid evaluation module continuously monitors the online protection parameters and safety margins of the core. Once an abnormality or potential risk is found, it immediately issues an early warning or triggers a protective action. It regularly conducts safety assessments on the operating status of the reactor and adjusts the reactor's operating strategy and maintenance plan based on the assessment results. At the same time, the machine learning model is continuously optimized and improved based on newly collected data and feedback.

Claims

1. A method for rapid evaluation of online protection parameters based on control rod position information, characterized in that: Includes steps: Based on the real-time fuel consumption data of the core, the simulation module is used to simulate the core status under several sets of preset rod positions; Acquire the first intermediate parameter corresponding to the core state under each set of preset rod positions during the simulation process, collect the real-time electrical signal data of the core measurement system and the real-time rod position data of the reactor control system, and feed back the first intermediate parameter, the real-time electrical signal data and the real-time rod position data to the rapid evaluation module; According to the first intermediate parameter, the first intermediate parameter is corrected by the rapid evaluation module with the actual measured rod position data of the reactor to obtain the second intermediate parameter; Based on the second intermediate parameter and the real-time electrical signal data, the online protection parameters of the core are calculated through the fast evaluation module; Based on the online protection parameters of the core and according to the preset protection parameter thresholds, the safety margin of the core is evaluated through the rapid evaluation module.

2. The online protection parameter rapid evaluation method based on control rod position information according to claim 1, characterized in that: The specific process of simulating the core state under several sets of preset rod positions through the simulation module based on the real-time core burnup data is as follows: The real-time fuel consumption data of the core is obtained and a simulation cycle is preset; based on the simulation cycle, several core simulation models are periodically established, each cycle corresponds to a core simulation model, and each core simulation model simulates the core state under a set of preset rod positions.

3. The online protection parameter rapid evaluation method based on control rod position information according to claim 2 is characterized in that: According to the actual layout and performance parameters of the detectors in the core measurement system, the corresponding detector parameters are set in the simulation model. The simulation model is run to simulate the neutron flux distribution and radiation intensity of the core under different preset rod positions, the theoretical electrical signal data corresponding to the detectors are calculated, and the power distribution data of the core is extracted from the simulation results.

4. The online protection parameter rapid evaluation method based on control rod position information according to claim 1 is characterized in that: The first intermediate parameters include: component-level networking three-dimensional power distribution parameters and fuel rod-level fine three-dimensional power distribution parameters.

5. The online protection parameter rapid evaluation method based on control rod position information according to claim 1, characterized in that: The specific process of collecting the real-time electrical signal data of the core measurement system and the real-time rod position data of the reactor control system is as follows: The core measurement system collects real-time data on electrical signals generated by neutron flux or related radiation in the core through the detector array arranged around the core; and obtains real-time rod position data of all control rods in the reactor through the reactor control system.

6. The online protection parameter rapid evaluation method based on control rod position information according to claim 1, characterized in that: The specific process of obtaining the second intermediate parameter by correcting the first intermediate parameter with the reactor measured rod position data through the rapid evaluation module according to the first intermediate parameter is as follows: The rapid evaluation module receives the first intermediate parameters under each set of preset rod positions transmitted by the simulation module, and corrects the first intermediate parameters with the reactor measured rod position data through interpolation or fitting method according to the real-time collected control rod position data to obtain the second intermediate parameters.

7. The online protection parameter rapid evaluation method based on control rod position information according to claim 1 is characterized in that: The specific process of calculating the online protection parameters of the core through the rapid evaluation module based on the second intermediate parameter and the real-time electrical signal data is as follows: The rapid evaluation module calculates the online protection parameters of the current core according to the corrected second intermediate parameter and the electrical signal data collected in real time by the core measurement system through a pre-set protection parameter calculation model.

8. The online protection parameter rapid evaluation method based on control rod position information according to claim 7 is characterized in that: The specific construction process of the protection parameter calculation model is as follows: According to the physical characteristics of the core and the operating principle of the reactor, the key parameters reflecting the safety of the core are selected; based on the historical operating data and experimental data of the core, the correlation between the key parameters and the online protection parameters of the core is analyzed, and a mathematical relationship model between the key parameters and the online protection parameters is established through statistical methods or machine learning algorithms; the established mathematical relationship model is verified and optimized to ensure that it can accurately reflect the actual operating status of the core and has good predictive ability; the verified and optimized mathematical relationship model is used as a protection parameter calculation model and integrated into the rapid evaluation module for real-time calculation of the online protection parameters of the core.

9. The online protection parameter rapid evaluation method based on control rod position information according to claim 1, characterized in that: The specific process of evaluating the safety margin of the core by the rapid evaluation module based on the online protection parameters of the core and according to the preset protection parameter threshold is as follows: The rapid evaluation module compares the calculated online protection parameters with the preset protection parameter thresholds to evaluate the safety margin of the current core operation; if the online protection parameters exceed the protection parameter thresholds, an early warning is issued or a protection action is triggered; Optimize reactor operation strategy based on safety margin.

10. The online protection parameter rapid evaluation method based on control rod position information according to claim 9, characterized in that: Based on the optimized reactor operation strategy, the position of the control rods is adjusted through the reactor control system to make the reactor operate within the safety margin range; the evaluation results and the adjustment measures taken are fed back to the simulation module to optimize the parameter configuration of the simulation module.

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