Reactor core state parameter determination method and apparatus, device, and storage medium

Abstract

The present application relates to a reactor core state parameter determination method and apparatus, a device, and a storage medium. The method comprises: acquiring actually measured reactor core power distribution of a target nuclear reactor; on the basis of the actually measured reactor core power distribution, adjusting the water gap width of each fuel assembly in a three-dimensional reactor core correction physical model of the target nuclear reactor to acquire a reactor core correction physical model of the target nuclear reactor, wherein the difference between reactor core power distribution calculated by the reactor core correction physical model and the actually measured reactor core power distribution is smaller than a preset value; and calculating the reactor core power distribution of the target nuclear reactor by means of the reactor core correction physical model. Use of the method can accurately calculate the reactor core power distribution of a nuclear reactor.

Description

Method, device, equipment and storage medium for determining core state parameters

[0001] Related applications:

[0002] This application claims priority to Chinese patent application number 2024100359412, filed on January 10, 2024, entitled “Core state parameter determination method, device, equipment and storage medium,” the entire text of which is hereby incorporated by reference. Technical Field

[0003] The present application relates to the field of reactor core monitoring, and in particular to a method, device, equipment and storage medium for determining core state parameters. Background Art

[0004] With the widespread application of nuclear energy technology and the construction of nuclear power plants, the operational safety of nuclear reactors has become particularly important. By calculating core state parameters, we can quickly understand the operating status of nuclear reactors. For example, core power distribution is one of the core parameters of core state parameters.

[0005] The relevant technology mainly monitors and statistically calculates the core state parameters of the nuclear reactor through the core correction physical model.

[0006] However, in related technologies, the core correction physical model cannot accurately calculate the core state parameters of the nuclear reactor, which affects the judgment of the operating state of the nuclear reactor. Summary of the Invention

[0007] Based on this, it is necessary to provide a method, device, equipment and storage medium for determining core state parameters to address the above technical problems, which can accurately determine the core state parameters of the nuclear reactor and improve the accuracy of judging the operating status of the nuclear reactor.

[0008] In a first aspect, an embodiment of the present application provides a method for determining a core state parameter. The method comprises:

[0009] Obtaining the measured core power distribution of the target nuclear reactor;

[0010] adjusting the water gap width of each fuel assembly in the three-dimensional core correction physical model of the target nuclear reactor based on the measured core power distribution to obtain the core correction physical model of the target nuclear reactor; wherein the deviation between the calculated core power distribution of the core correction physical model and the measured core power distribution is less than a preset value;

[0011] The core state parameters of the target nuclear reactor are determined through the core correction physical model.

[0012] In one embodiment, obtaining a measured core power distribution of a target nuclear reactor includes:

[0013] Obtaining the measured core power data of each nuclear reactor collected regularly by the nuclear power plant to which the target nuclear reactor belongs;

[0014] The measured core power distribution of the target nuclear reactor is determined based on the measured core power data of each nuclear reactor.

[0015] In one embodiment, adjusting the water gap width of each fuel assembly in the three-dimensional core modified physical model of the target nuclear reactor based on the measured core power distribution includes:

[0016] According to the measured core power distribution, the water gap width of each fuel assembly in the three-dimensional core modified physical model is adjusted by executing a water gap width adjustment step;

[0017] If the deviation between the calculated core power distribution of the adjusted three-dimensional core corrected physical model and the measured core power distribution is greater than or equal to a preset value, the water gap width adjustment step is re-executed until the deviation between the calculated core power distribution of the adjusted three-dimensional core corrected physical model and the measured core power distribution is less than a preset value, and the adjustment is stopped.

[0018] In one embodiment, the step of adjusting the water gap width includes:

[0019] Obtain the latest calculated core power distribution of the 3D core modified physical model;

[0020] Based on the latest calculated and measured core power distribution, the water gap width adjustment method for each fuel assembly in the 3D core correction physical model is determined;

[0021] According to the serial numbering sequence of each fuel assembly, the water gap width of the corresponding fuel assembly is adjusted in turn according to the water gap width adjustment method of each fuel assembly.

[0022] In one embodiment, determining a method for adjusting the water gap width of each fuel assembly in a three-dimensional core modified physical model based on the latest calculated core power distribution and the measured core power distribution includes:

[0023] For any fuel assembly in the three-dimensional core corrected physical model, obtaining the latest calculated assembly power of the fuel assembly in the latest calculated core power distribution, and obtaining the measured assembly power of the fuel assembly in the measured core power distribution;

[0024] Determine the water gap width adjustment method for the fuel assembly based on the latest calculated assembly power and the actual measured assembly power.

[0025] In one embodiment, determining a method for adjusting the water gap width of a fuel assembly based on the latest calculated assembly power and the actual measured assembly power includes:

[0026] If the latest calculated assembly power is greater than the actually measured assembly power, and the deviation ratio between the latest calculated assembly power and the actually measured assembly power is greater than or equal to a preset ratio, then the water gap width adjustment method is determined to be to reduce the water gap width around the fuel assembly by a preset amount.

[0027] If the latest calculated component power is less than the actually measured component power, and the deviation ratio between the latest calculated component power and the actually measured component power is less than a preset ratio, the water gap width adjustment method is determined to be to increase the water gap width around the fuel assembly by a preset amplitude.

[0028] In one embodiment, adjusting the water gap width of the corresponding fuel assembly according to the water gap width adjustment method of each fuel assembly in turn includes:

[0029] For any fuel assembly, if the water gap width adjustment method of the fuel assembly is to increase the water gap width of all four sides by a preset amount, the water gap width is adjusted by increasing the current water gap width of the fuel assembly by the preset amount.

[0030] If the water gap width adjustment method of the fuel assembly is to reduce the water gap widths of all four sides by a preset amplitude, the water gap width is adjusted by reducing the current water gap width of the fuel assembly by the value of the preset amplitude.

[0031] In one embodiment, before adjusting the water gap width of each fuel assembly in the three-dimensional core modified physical model of the target nuclear reactor based on the measured core power distribution, the method further includes:

[0032] obtaining current unit rated parameters of the target nuclear reactor, a core loading plan of the target nuclear reactor, and historical operating conditions of the target nuclear reactor;

[0033] A three-dimensional core correction physical model of the target nuclear reactor is constructed according to the current unit rated parameters of the target nuclear reactor, the core loading plan of the target nuclear reactor and the historical operating conditions of the target nuclear reactor.

[0034] In a second aspect, an embodiment of the present application further provides a device for determining a core state parameter, the device comprising:

[0035] an acquisition module, for acquiring the measured core power distribution of the target nuclear reactor;

[0036] a physical model determination module, configured to adjust the water gap width of each fuel assembly in a three-dimensional core correction physical model of the target nuclear reactor based on the measured core power distribution, thereby obtaining a core correction physical model of the target nuclear reactor; wherein the deviation between the calculated core power distribution of the core correction physical model and the measured core power distribution is less than a preset value;

[0037] The power state parameter determination module is used to calculate the core state parameters of the target nuclear reactor through the core correction physical model.

[0038] In a third aspect, an embodiment of the present application 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 method provided in any embodiment of the first aspect when executing the computer program.

[0039] In a fourth aspect, an embodiment of the present application provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the steps of the method provided in any embodiment of the first aspect above.

[0040] In a fifth aspect, an embodiment of the present application further provides a computer program product, comprising a computer program, which, when executed by a processor, implements the steps of the method provided in any embodiment of the first aspect above. BRIEF DESCRIPTION OF THE DRAWINGS

[0041] In order to more clearly illustrate the embodiments of the present application or the technical solutions in the prior art, the following briefly introduces the drawings required for use in the embodiments or the description of the prior art. Obviously, the drawings described below are only some embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on these drawings without any creative work.

[0042] FIG1 is a diagram showing an application environment of a method for determining a core state parameter according to an embodiment;

[0043] FIG2 is a schematic flow chart of a method for determining core state parameters in one embodiment;

[0044] FIG3 is a schematic diagram of a water gap in a rectangular fuel assembly according to one embodiment;

[0045] FIG4 is a schematic flow chart of a method for determining core state parameters in another embodiment;

[0046] FIG5 is a schematic flow chart of a method for determining core state parameters in another embodiment;

[0047] FIG6 is a schematic flow chart of a method for determining core state parameters in another embodiment;

[0048] FIG7 is a schematic diagram of a core arrangement diagram according to an embodiment;

[0049] FIG8 is a schematic flow chart of a method for determining core state parameters in another embodiment;

[0050] FIG9 is a schematic flow chart of a method for determining core state parameters in another embodiment;

[0051] FIG10 is a schematic flow chart of a method for determining core state parameters in another embodiment;

[0052] FIG11 is a schematic flow chart of a method for determining core state parameters in another embodiment;

[0053] FIG12 is a structural block diagram of a core state parameter determination device in one embodiment. DETAILED DESCRIPTION

[0054] 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.

[0055] In one embodiment, a method for determining core state parameters is provided, which is illustrated by taking the method applied to the computer device in Figure 1 as an example. The computer device includes a processor, a memory, a communication interface, a display screen, and an input device connected via a system bus. 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 an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of the operating system and the computer program in the non-volatile storage medium. The communication interface of the computer device is used to communicate with an external terminal in a wired or wireless manner, and the wireless manner can be implemented through WIFI, a mobile cellular network, NFC (near field communication) or other technologies. When the computer program is executed by the processor, a method for determining core state parameters is implemented.

[0056] The computer device may include, but is not limited to, a personal computer, laptop computer, smartphone, tablet computer, server, IoT device, and portable wearable device. The server may be implemented as a standalone server or a server cluster consisting of multiple servers. A data storage system may be deployed on the server to store data that the server needs to process. The data storage system may be integrated on the server or located in the cloud or on another network server. IoT devices may include smart TVs, smart car devices, and the like; portable wearable devices may include smart watches, smart bracelets, head-mounted devices, and the like.

[0057] In the related art, during the core design process of a nuclear reactor, due to approximations in theoretical calculations and many uncertain factors in actual operation, there are certain differences between the theoretical calculation results and the measured results of the core state parameters of the core correction physical model. Therefore, it is impossible to fully and accurately grasp and judge the current and future operating states of the core based on the existing core model. Based on this, an embodiment of the present application provides a core state parameter determination method that can accurately calculate the core state parameters of a nuclear reactor, thereby accurately judging the operating state of the nuclear reactor.

[0058] The following describes a method for determining a core state parameter provided by an embodiment of the present application, taking a computer device as an example. As shown in FIG2 , in one embodiment, the method for determining a core state parameter provided by an embodiment of the present application includes the following steps:

[0059] S201, obtaining the measured core power distribution of the target nuclear reactor.

[0060] A nuclear reactor, also known as an atomic reactor or reactor, is a device capable of maintaining a controlled, self-sustaining chain nuclear fission reaction to achieve nuclear energy utilization. By rationally arranging nuclear fuel, a nuclear reactor enables a self-sustaining chain nuclear fission process without the need for additional neutron sources. Nuclear reactors include pressurized water reactors, boiling water reactors, heavy water reactors, and fast reactors.

[0061] The target nuclear reactor can be any pressurized water reactor that requires fuel assembly core power distribution analysis. It should be noted that the target nuclear reactor in the embodiment of the present application includes at least one nuclear reactor or multiple nuclear reactors.

[0062] The core power distribution refers to the power distribution at different locations within a nuclear reactor, including the power distribution of individual components (such as fuel assemblies). The measured core power distribution is the power distribution at different locations within the reactor, obtained through actual measurement and monitoring. For example, this data can be obtained through periodic testing.

[0063] The core power distribution is one of the core state parameters of a nuclear reactor. Therefore, the embodiment of the present application uses the core power distribution as a benchmark to train a core correction physical model of a nuclear reactor.

[0064] In one embodiment, the computer device may obtain the measured core power distribution of the target nuclear reactor by directly reading it from a database, or by automatically generating the measured core power distribution data based on historical experience data.

[0065] In another embodiment, the measured core power distribution of the target nuclear reactor can be obtained using different types of detectors and sensors. The detectors can include neutron monitoring detectors, nuclear reactivity detectors, and the like, while the sensors can include acoustic sensors, pressure sensors, and the like. Detectors are positioned at various locations inside and outside the nuclear reactor to cover different areas within the core. These detectors are selected based on the needs. The data obtained from the detectors and sensors is processed and analyzed to obtain the measured core power distribution of the target nuclear reactor.

[0066] S202, adjusting the water gap width of each fuel assembly in the three-dimensional core correction physical model of the target nuclear reactor according to the measured core power distribution, and obtaining the core correction physical model of the target nuclear reactor; the deviation between the calculated core power distribution of the core correction physical model and the measured core power distribution is less than a preset value.

[0067] A 3D modified core model is a mathematical model used to describe and analyze the three-dimensional structure and physical processes within a nuclear reactor. In practical applications, the 3D modified core model can simulate the structure and design of nuclear fuel assemblies to scale according to actual conditions. For example, the 3D modified core model can simulate the geometry and position of fuel assemblies, their arrangement, and the gaps between them. This is not a limitation.

[0068] The core correction physical model is a physical model that can invert the core power distribution with high precision by fusing the measured signals. The measured power distribution data can be obtained through regular tests. The key influencing parameters of the core correction physical model (component water gap) can be used to invert the core power distribution with high precision using the cyclic step method to obtain a core physical model that is identical to the measured state.

[0069] The core correction physics model is inverted based on the 3D core correction physics model. By comparing it with measured data, the fuel assembly water gap width is adjusted to align with the measured data. This improves the accuracy and reliability of the core physics model, making it more useful for predicting and analyzing core power distribution and other state parameters.

[0070] A fuel assembly refers to a complete group of fuel elements assembled together, consisting of several fuel elements, upper tube sockets, lower tube sockets, control rods, guide tubes and positioning grids.

[0071] It is understandable that the number, arrangement, and structure of elements within a fuel assembly vary depending on the reactor type. Different reactors use different fuel elements, and their shapes include rods, tubes, plates, spheres, hexagons, and squares. Fuel elements also include metallic, ceramic, and dispersed fuels.

[0072] Fuel assemblies are typically arranged in a specific pattern. This arrangement can vary between reactors. These arrangements can range from a single arrangement to complex arrangements with multiple rows and columns, or even involve complex three-dimensional arrangements.

[0073] Since adjusting the water gap width of the assembly changes the moderation conditions and assembly cross-section of each assembly, and thus changes the power level, the method of adjusting the water gap width of the fuel assembly is adopted to obtain the core corrected physical model of the target nuclear reactor.

[0074] Taking a rectangular fuel assembly as an example, a schematic diagram of the water gap of a rectangular fuel assembly is shown in Figure 3. Since there is a certain gap between assemblies during layout, in a pressurized water reactor, the intervening space is filled with water, and the intervening space is defined as the assembly water gap.

[0075] In one embodiment, a modified physical model of the core of a target nuclear reactor can be obtained by incorporating the water gap width as an adjustable parameter into the physical model. Simulation calculations are performed using nuclear reactor simulation software, and the water gap width of each fuel assembly is adjusted to obtain the modified physical model of the core of the target nuclear reactor.

[0076] In another embodiment, by analyzing the historical operating data of the nuclear reactor, including sensor measurement data, control parameter settings, etc., the historical operating data is analyzed using big data analysis technology. Data mining, machine learning and other methods can be used to find the correlations and patterns in the data. Based on the results of the data analysis, a water gap width adjustment model is established. According to the water gap width adjustment model, the water gap width of each fuel assembly is adjusted to obtain a core corrected physical model of the target nuclear reactor.

[0077] Deviation is the difference between the calculated and measured values ​​of the core correction physics model. During the core design process, due to approximations in theoretical calculations and numerous uncertainties in actual operation, there may be discrepancies between the theoretical and measured power distributions of the core correction physics model. The preset value is a reference value set based on specific circumstances and requirements to determine whether the deviation between the calculated and measured core power distributions of the core correction physics model is within an acceptable range. The preset value can be set to 0.1%, with no specific limit.

[0078] S203, calculating the core state parameters of the target nuclear reactor using the core correction physical model.

[0079] The core state parameters of the target nuclear reactor are calculated based on the obtained core modified physical model. The core state parameters include, but are not limited to, the subsequent core power distribution of the target nuclear reactor and the changing trends of various other state parameters.

[0080] Optionally, the method for determining the core state parameters may be to input the collected measured data or historical operating data into the core correction physical model. It is necessary to collect some measured data or historical operating data, divide them into a training set and a test set, use the training set to train the initial core correction physical model, and obtain a trained core state parameter prediction model. Then use the test set to evaluate the performance of the core state parameter prediction model. If the performance is achieved, it is determined that the core state parameter prediction model has been trained successfully, and the core state parameters in the embodiment of the present application are obtained.

[0081] Optionally, the core state parameters can be determined by a preset core state parameter prediction algorithm in the core correction physical model. Specifically, the collected measured data or historical operating data is used as the input of the core state parameter prediction algorithm, and the core state parameter prediction algorithm is run to obtain the core state parameters of the target nuclear reactor.

[0082] The embodiments of the present application provide a method, device, equipment and storage medium for determining core state parameters. The method obtains the measured core power distribution of the target nuclear reactor, and adjusts the water gap width of each fuel assembly in the three-dimensional core correction physical model of the target nuclear reactor according to the measured core power distribution. The core correction physical model of the target nuclear reactor is obtained, and the deviation between the calculated core power distribution of the core correction physical model and the measured core power distribution is less than a preset value. The core power distribution of the target nuclear reactor is calculated using the core correction physical model. In this method, the water gap width of each fuel assembly in the three-dimensional core correction physical model of the nuclear reactor is adjusted based on the measured core power distribution. In this adjustment process, the physical model can be closer to the actual situation, thereby obtaining a more accurate target nuclear reactor core correction physical model. Moreover, the deviation between the calculated power distribution of the obtained core correction physical model and the measured core power distribution is kept within a preset small range, ensuring the reliability and accuracy of the model, and making the core state parameters determined by the core correction physical model more credible. Therefore, the core correction physical model of the target nuclear reactor can accurately obtain the core state parameters of the nuclear reactor.

[0083] Another method for determining core state parameters provided by an embodiment of the present application is described below. As shown in FIG4 , in one embodiment, the measured core power distribution of the target nuclear reactor is obtained. The method may further include the following steps:

[0084] S401, obtaining the measured core power data of each nuclear reactor collected regularly by the nuclear power plant to which the target nuclear reactor belongs.

[0085] A nuclear power plant typically consists of multiple units, each of which is an independent nuclear reactor unit that may have different operating parameters, configurations, and performance data.

[0086] The measured data of the core power of a nuclear reactor include, but are not limited to, temperature data of different parts, such as fuel temperature, coolant temperature, etc., as well as pressure data of different parts of the nuclear reactor, and flow data of coolant or other fluids.

[0087] In one embodiment, the method for obtaining the actual core power measured data of each nuclear reactor regularly collected by the nuclear power plant to which the target nuclear reactor belongs can be to obtain, integrate and analyze sensor measurement values ​​and operation records, thereby obtaining the actual core power measured data of each nuclear reactor in the nuclear power plant to which the target nuclear reactor belongs.

[0088] In another embodiment, the method for obtaining the measured core power data of each nuclear reactor regularly collected in the nuclear power plant to which the target nuclear reactor belongs can be determined by a preset power distribution algorithm, and the collected data of each nuclear reactor in the nuclear power plant to which the target nuclear reactor belongs is used as input, and the algorithm is run to obtain the measured core power data of each nuclear reactor in the nuclear power plant to which the target nuclear reactor belongs.

[0089] For example, the power distribution of the core assembly of the target nuclear reactor can be expressed as:

[0090] (p_real(i), i = 1, 2, ... N). Where N is the number of components in the core. For example, N is a positive integer, which can be 157.

[0091] S402 : Determine the measured core power distribution of the target nuclear reactor based on the measured core power data of each nuclear reactor.

[0092] Based on the above-obtained measured core power data of each nuclear reactor, the measured core power distribution of the target nuclear reactor is determined.

[0093] In one embodiment, the core power distribution data of the target nuclear reactor is retrieved from a mapping table between each nuclear reactor and its measured core power distribution data. Specifically, the corresponding core power distribution data identifier is searched in the mapping table. Based on this identifier, the measured core power distribution data of the target nuclear reactor is retrieved from a database to determine the measured core power distribution of the target nuclear reactor.

[0094] In another embodiment, measured data from various nuclear reactors is input into a preset core power distribution algorithm to calculate the core power of the nuclear reactor at different locations. The preset core power distribution algorithm is used to analyze and calculate the measured core power data to determine the measured core power distribution of the target nuclear reactor.

[0095] In an embodiment of the present application, the measured core power distribution of the target nuclear reactor is determined based on the measured core power data of each nuclear reactor regularly collected at the nuclear power plant to which the target nuclear reactor belongs. In this method, by obtaining the measured core power data of each nuclear reactor regularly collected at the nuclear power plant, an accurate record of the actual operating conditions of different nuclear reactors can be obtained. Because the measured data reflects the core power distribution of nuclear reactors under different operating conditions, analyzing and processing the measured data to determine the measured core power distribution of the target nuclear reactor provides a more realistic understanding of the nuclear reactor's operating conditions.

[0096] Another method for determining core state parameters provided by an embodiment of the present application is described below. As shown in FIG5 , in one embodiment, the water gap width of each fuel assembly in the three-dimensional core modified physical model of the target nuclear reactor is adjusted based on the measured core power distribution. The method may further include the following steps:

[0097] S501 , adjusting the water gap width of each fuel assembly in the three-dimensional core modified physical model by executing a water gap width adjustment step according to the measured core power distribution.

[0098] In one embodiment, the change in water gap width that requires adjustment is calculated based on measured core power distribution data. A preset water gap width adjustment algorithm is used to calculate the change in water gap width for each fuel assembly. The water gap width adjustment algorithm is then run to automatically calculate and adjust the water gap width for each fuel assembly. The initial water gap width is added to or subtracted from the change to obtain the adjusted water gap width. The adjusted water gap width value is then updated to the corresponding fuel assembly position in the three-dimensional core modified physical model.

[0099] In another embodiment, the required water gap width change is calculated based on measured core power distribution data. Based on preset adjustment rules, the water gap width is adjusted for each fuel assembly. After the adjustment is complete, the adjusted water gap width value is updated to the corresponding fuel assembly position in the 3D core modified physical model.

[0100] S502: If the deviation between the calculated core power distribution of the adjusted three-dimensional core corrected physical model and the measured core power distribution is greater than or equal to the preset value, the water gap width adjustment step is re-executed until the deviation between the calculated core power distribution of the adjusted three-dimensional core corrected physical model and the measured core power distribution is less than the preset value, and the adjustment is stopped.

[0101] Optionally, the deviation can be expressed as the difference between the calculated core power distribution and the measured core power distribution, or as the mean square error between the calculated core power distribution and the measured core power distribution, which is not limited to this.

[0102] The calculated core power distribution of the adjusted three-dimensional core correction physical model is compared with the measured core power distribution. If the deviation between the two is greater than or equal to a preset value, the water gap width between the fuel assemblies is adjusted to bring the calculated core power distribution closer to the measured data. If the adjusted three-dimensional core correction physical model still does not meet the preset deviation requirement after re-performing the water gap width adjustment step, the water gap width adjustment step is continued. This process will continue to loop until the loop ends, that is, the deviation between the calculated core power distribution of the adjusted three-dimensional core correction physical model and the measured core power distribution is less than the preset value.

[0103] The calculated core power distribution can be expressed as (p_ref(i), i = 1, 2, ..., 157), and the measured core power distribution can be expressed as (p_real(i), i = 1, 2, ..., 157). As shown in formula (1), formula (1) represents the condition for the end of the cycle, that is, the mean square error between the calculated core power distribution and the measured core power distribution is less than a preset value.

[0104] Where N is the number of components in the core, i is the component number, p_ref(i) is the calculated power level of the i-th component, p_real(i) is the measured power level of the i-th component, and ε is a preset value that can be set to 0.1% without limitation.

[0105] If the deviation between the calculated core power distribution and the measured core power distribution is less than a preset value, the loop is exited.

[0106] In an embodiment of the present application, a water gap width adjustment step is performed based on the measured core power distribution to adjust the water gap width of each fuel assembly in the three-dimensional core modified physical model. If the deviation between the calculated core power distribution of the adjusted three-dimensional core modified physical model and the measured core power distribution is greater than or equal to a preset value, the water gap width adjustment step is re-executed until the deviation between the calculated core power distribution of the adjusted three-dimensional core modified physical model and the measured core power distribution is less than the preset value, at which point the adjustment is stopped. In this method, based on the current measured core power distribution, a cyclical stepping method is used to adjust the component water gap parameters in the physical model multiple times, thereby correcting the component cross-section and changing its power level. Finally, the calculated power distribution level is corrected to be consistent with the measured power distribution level through water gap adjustment, thereby achieving a physical model that inverts the actual power state. Adjusting the water gap width based on the measured core power distribution can gradually optimize the physical model to more accurately reflect the actual core conditions, thereby improving the prediction accuracy of the core power distribution. Through continuous iterative adjustment of the water gap width, the physical model can gradually approach the actual situation, reducing the deviation between the model calculation and reality. In addition, this method does not require human participation in processing, can avoid human participation errors, and can also improve the accuracy of the core power distribution.

[0107] Another method for determining core state parameters provided by an embodiment of the present application is described below. As shown in FIG6 , in one embodiment, the water gap width adjustment step includes the following steps:

[0108] S601, obtaining the latest calculated core power distribution of the three-dimensional core correction physical model.

[0109] In practical applications, to obtain the latest calculated core power distribution based on the 3D core modified physics model, nuclear reactor design simulation software can be used. Nuclear reactor design simulation software is specifically designed for the design, analysis, and simulation of nuclear reactors and includes a range of specific programs, such as a 3D core physics design program.

[0110] In one embodiment, the latest calculated core power distribution of the three-dimensional core modified physical model is obtained by using nuclear reactor simulation software to construct the three-dimensional core modified physical model and perform simulation calculations during the simulation process. The latest calculated core power distribution of the three-dimensional core modified physical model is obtained based on the set design parameters, physical characteristics, and operating conditions.

[0111] In another embodiment, the latest calculated core power distribution of the three-dimensional core-corrected physics model is obtained through historical data analysis and a preset prediction model. During nuclear reactor operation, a large amount of historical data is accumulated. A prediction model, such as a machine learning model or a neural network model, is built based on this historical data. The prediction model uses the historical data as input and runs to obtain the latest calculated core power distribution of the three-dimensional core-corrected physics model.

[0112] S602: Determine a water gap width adjustment method for each fuel assembly in the three-dimensional core correction physical model based on the latest calculated core power distribution and the measured core power distribution.

[0113] In one embodiment, the water gap width adjustment locations are determined based on the difference between the latest calculated and measured core power distributions. Each location requiring adjustment is defined as a design variable, representing the water gap width adjustment amount for the fuel assembly surrounding that location. Constraints, such as upper and lower limits on the adjustment amount, can also be set to ensure reasonable adjustments.

[0114] In another embodiment, based on the difference between the latest calculated core power distribution and the measured core power distribution, the locations where the water gap width needs to be adjusted are analyzed. A threshold is set, and if the difference exceeds the threshold, the location is marked as a location where the water gap width needs to be adjusted.

[0115] S603 , adjusting the water gap widths of the corresponding fuel assemblies in sequence according to the numbering sequence of the fuel assemblies and the water gap width adjustment method of each fuel assembly.

[0116] Considering the large number of fuel assemblies in a nuclear reactor, a numbering method is adopted to avoid duplication or confusion. The numbering method can be from small to large or from large to small, or from left to right, from right to left, from top to bottom, and from bottom to top. These numbering methods can be combined arbitrarily without limitation.

[0117] When adjusting the water gap width of the fuel assembly, the adjustment can be carried out in sequence according to the number of each fuel assembly. This orderly method can effectively manage the various fuel assemblies in the nuclear reactor, maintain their correct position and status, and reduce the possibility of misoperation and confusion.

[0118] As shown in Figure 7, a schematic diagram of a reactor is provided, in which the core of the nuclear reactor is loaded with 157 groups of fuel assemblies. All assemblies are numbered from 1 to 157 (or the total number of any fuel assemblies) in order from the upper left corner to the lower right corner of the core. First, the initial water gap width of all assemblies is set to 2mm, which is not limited. Starting from number 1, the water gap width of the fuel assemblies is adjusted one by one. The first fixed step adjustment is completed in sequence according to the component serial number, and the calculated water gap width adjustment amount is added to the initial water gap width of each fuel assembly in the order of numbering to obtain the adjusted water gap width. The water gap width of each fuel assembly is adjusted in sequence according to the order of numbering until the water gap width adjustment of all fuel assemblies is completed.

[0119] In an embodiment of the present application, the latest calculated core power distribution of the three-dimensional core correction physical model is obtained. Based on the latest calculated core power distribution and the measured core power distribution, the water gap width adjustment method for each fuel assembly in the three-dimensional core correction physical model is determined. Then, according to the numbering order of each fuel assembly, the water gap width of the corresponding fuel assembly is adjusted in sequence according to the water gap width adjustment method of each fuel assembly. In this method, by analyzing the difference between the latest calculated core power distribution and the measured core power distribution, the specific water gap width adjustment method for each fuel assembly can be inferred, thereby making the calculated core power distribution obtained by the three-dimensional core correction physical model closer to the measured core power distribution. Furthermore, adjusting the gaps one by one can effectively eliminate, to a certain extent, the mutual interference with the power levels of other components.

[0120] Another method for determining core state parameters provided in an embodiment of the present application is described below. As shown in FIG8 , in one embodiment, obtaining the latest calculated core power distribution of the three-dimensional core corrected physical model includes the following steps:

[0121] S801, obtaining the latest assembly cross section of each fuel assembly in the three-dimensional core correction physical model.

[0122] A component cross section represents the probability of various interactions during a nuclear reaction. In nuclear physics and engineering, this refers to the likelihood or probability of a particular nuclear reaction (such as absorption, scattering, or fission) occurring under specific conditions. Component cross sections can be categorized into various types, including but not limited to absorption, scattering, and fission. These cross sections are dependent on various conditions, including the component's material (nuclide concentration), geometry, and external environment (temperature, pressure, water gap, and control rod position). Changes in these conditions will result in changes in the component cross section.

[0123] The state of the component is related to the core conditions. For example, if the core fuel consumption, temperature, pressure, layout (mainly affecting the water gap), etc. change, the component cross-section will change or be updated.

[0124] In one embodiment, the latest component cross-section of each fuel assembly in the three-dimensional core corrected physical model can be obtained by calculating the current component nuclide density distribution and external water gap conditions, and solving the neutron transport equation under the corresponding temperature and pressure to obtain the probability of various nuclear reactions occurring in the component under the current conditions, that is, the component cross-section.

[0125] In another embodiment, the latest component cross-section of each fuel assembly in the three-dimensional core corrected physical model can be obtained by analyzing the nuclear physics data of each fuel assembly and, in combination with the actual core model, calculating the latest component cross-section of each fuel assembly in the model.

[0126] S802: Determine the latest calculated assembly power of each fuel assembly based on the latest assembly cross-section of each fuel assembly.

[0127] Module power is the energy released from the nuclear reaction per unit time.

[0128] In one embodiment, the method for determining the latest calculated assembly power of each fuel assembly based on the latest assembly cross-section of each fuel assembly can be obtained using an empirical formula. Based on the selected empirical formula, the latest cross-section of the fuel assembly is substituted into the formula to obtain the latest calculated assembly power of each fuel assembly.

[0129] In another embodiment, the method for determining the latest calculated assembly power of each fuel assembly based on the latest assembly cross-section of each fuel assembly can be obtained through a preset assembly power algorithm. The preset assembly power algorithm is run using the latest assembly cross-section of each fuel assembly as input to determine the latest calculated assembly power of each fuel assembly.

[0130] S803 , determining the latest calculated core power distribution of the three-dimensional core corrected physical model according to the latest calculated assembly power of each fuel assembly and the position of each fuel assembly in the three-dimensional core corrected physical model.

[0131] In one embodiment, for each fuel assembly, the most recently calculated power of the assembly is combined with its position in the three-dimensional modified core physics model to generate a spatial distribution map containing the power distribution of each fuel assembly. In the spatial distribution map, each fuel assembly position corresponds to a specific power value. By combining the positions and powers of all fuel assemblies, the most recently calculated core power distribution of the three-dimensional modified core physics model can be determined.

[0132] In an embodiment of the present application, the latest cross-section of each fuel assembly in the three-dimensional core correction physical model is obtained, and based on the latest cross-section of each fuel assembly, the latest calculated assembly power of each fuel assembly is determined according to the neutron diffusion theory solution formula. The latest calculated assembly power of each fuel assembly and the position of each fuel assembly in the three-dimensional core correction physical model are used to determine the latest calculated core power distribution of the three-dimensional core correction physical model. In this method, the calculated power of each fuel assembly can be more accurately calculated using the latest cross-section data of each fuel assembly. In addition, by combining the latest calculated assembly power of each fuel assembly with the position of each fuel assembly in the three-dimensional core correction physical model, the latest calculated core power distribution of the three-dimensional core correction physical model can be accurately determined.

[0133] Another method for determining core state parameters provided by an embodiment of the present application is described below. As shown in FIG9 , in one embodiment, a method for adjusting the water gap width of each fuel assembly in a three-dimensional core modified physical model is determined based on the latest calculated core power distribution and the measured core power distribution, including the following steps:

[0134] S901, for any fuel assembly in the three-dimensional core corrected physical model, obtain the latest calculated assembly power of the fuel assembly in the latest calculated core power distribution, and obtain the measured assembly power of the fuel assembly in the measured core power distribution.

[0135] Optionally, the latest calculated assembly power of the fuel assembly in the latest calculated core power distribution can be obtained from the correspondence between the fuel assembly position and the latest calculated core power distribution. For example, according to the latest calculated core power distribution, the corresponding fuel assembly position is found, and the latest calculated assembly power of the fuel assembly at that position is obtained.

[0136] Optionally, the measured assembly power of the fuel assembly in the measured core power distribution can be obtained from the correspondence between the measured core power distribution and the fuel assembly position in the three-dimensional core model. For example, the corresponding fuel assembly position in the measured core power distribution is found, and the measured assembly power of the fuel assembly at that position is obtained.

[0137] S902: Determine a water gap width adjustment method for the fuel assembly based on the latest calculated assembly power and the actual measured assembly power.

[0138] Adjusting the width of the water gap will change the moderation conditions and component cross-section of each component, thereby changing the power level.

[0139] Moderation conditions refer to the process by which neutrons are slowed down in a nuclear reactor, allowing them to better collide with fissile material and thus accelerate the nuclear reaction rate. Moderators, such as water, heavy water, and graphite, are commonly used in nuclear reactors. These materials have high neutron scattering cross sections and can effectively slow down neutrons.

[0140] In one embodiment, the latest calculated component power is compared with the measured component power. If the latest calculated component power is greater than the measured component power, the calculated component power needs to be reduced, thereby reducing the water gap. If the latest calculated component power is compared with the measured component power, if the latest calculated component power is less than the measured component power, the calculated component power needs to be increased, thereby increasing the water gap.

[0141] In an embodiment of the present application, for any fuel assembly in the three-dimensional core correction physical model, the latest calculated assembly power of the fuel assembly in the latest calculated core power distribution is obtained, and the measured assembly power of the fuel assembly in the measured core power distribution is obtained, and the water gap width adjustment method of the fuel assembly is determined based on the latest calculated assembly power and the measured assembly power. In this method, by comparing the latest calculated assembly power and the measured assembly power, the water gap width of the fuel assembly is appropriately adjusted according to the comparison result to better reflect the actual situation. When there is a difference between the latest calculated assembly power and the measured assembly power, it means that there may be a deviation between the physical model and the actual situation. Through comparative analysis, the power status of each fuel assembly can be accurately understood, and then it can be determined whether its water gap width needs to be adjusted.

[0142] Another method for determining core state parameters provided by an embodiment of the present application is described below. In one embodiment, a method for adjusting the water gap width of a fuel assembly is determined based on the latest calculated assembly power and the actual measured assembly power, including:

[0143] As shown in formula (2), based on the latest calculated component power and the measured component power, if the latest calculated component power is greater than or equal to the measured component power and the percentage deviation is higher than the threshold, the water gap width around the component is reduced by a fixed amplitude (Δμ = 0.01 mm).

[0144] Where p_ref(i) is the calculated power level of the i-th component, p_real(i) is the measured power level of the i-th component, and δ is the threshold for adjusting the water gap width, which can be set to 0.1% and is not limited to this.

[0145] If the latest calculated assembly power is higher than the measured assembly power, the width of the water gap between the fuel assemblies is reduced to reduce the intensity of the nuclear reaction.

[0146] Of course, there is also a case where the power is less than the actual measured component power. As shown in formula (3), based on the latest calculated component power and the actual measured component power, if the latest calculated component power is less than the actual measured component power and the percentage deviation is higher than the threshold, the water gap width around the component is increased by a fixed amplitude (Δμ = 0.01 mm).

[0147] Where p_ref(i) is the calculated power level of the i-th component, p_real(i) is the measured power level of the i-th component, and δ is the threshold for adjusting the water gap width, which can be set to 0.1% and is not limited to this.

[0148] If the latest calculated assembly power is lower than the measured assembly power, the width of the water gap between the fuel assemblies is increased to increase the intensity of the nuclear reaction.

[0149] After completing the first step of all components in sequence, diffusion calculations are performed in the core segment program SMART based on the core physical model after the first component water gap correction to obtain a new full-reactor power distribution level.

[0150] Based on the newly calculated power distribution level and the measured power distribution level, the next fixed-step adjustment is carried out until the cycling conditions are met. Finally, a modified core physical model with a specific water gap distribution is obtained, which has a theoretical power level that fully corresponds to the measured core power level.

[0151] In an embodiment of the present application, if the latest calculated assembly power is greater than the actual measured assembly power, and the deviation ratio between the latest calculated assembly power and the actual measured assembly power is less than a preset ratio, the water gap width adjustment method is determined to be a preset reduction in the water gap width around the fuel assembly. If the latest calculated assembly power is less than the actual measured assembly power, and the deviation ratio between the latest calculated assembly power and the actual measured assembly power is greater than or equal to a preset ratio, the water gap width adjustment method is determined to be a preset increase in the water gap width around the fuel assembly. This method dynamically adjusts the fuel assembly water gap width to bring the latest calculated assembly power closer to the actual measured assembly power. By comparing the latest calculated assembly power with the actual measured assembly power, the accuracy of the three-dimensional core correction physics model can be verified. When the deviation ratio between the latest calculated assembly power and the actual measured assembly power exceeds a preset ratio, it indicates that the three-dimensional core correction physics model contains errors or is inaccurate. Therefore, further improvements to the three-dimensional core correction physics model are needed to improve its accuracy. Furthermore, the water gap width adjustment method is automated, reducing manual intervention and thus improving adjustment efficiency.

[0152] Another method for determining core state parameters provided by an embodiment of the present application is described below. In one embodiment, the water gap widths of corresponding fuel assemblies are adjusted sequentially according to the water gap width adjustment method of each fuel assembly, including:

[0153] For any fuel assembly, if the water gap width adjustment method of the fuel assembly is to increase the water gap width of the surrounding areas by a preset amplitude, the water gap width is adjusted by increasing the current water gap width of the fuel assembly by the preset amplitude; if the water gap width adjustment method of the fuel assembly is to decrease the water gap width of the surrounding areas by a preset amplitude, the water gap width is adjusted by decreasing the current water gap width of the fuel assembly by the preset amplitude.

[0154] In one embodiment, the current water gap width is increased or decreased accordingly around the target fuel assembly according to a preset amplitude value. The preset amplitude value may be a pre-set parameter used to control the degree of adjustment of the water gap width.

[0155] In the embodiment of the present application, for any fuel assembly, if the water gap width adjustment method for the fuel assembly is to increase the water gap width of the surrounding areas by a preset amplitude, the water gap width is adjusted by increasing the current water gap width of the fuel assembly by the preset amplitude. If the water gap width adjustment method for the fuel assembly is to decrease the water gap width of the surrounding areas by a preset amplitude, the water gap width is adjusted by decreasing the current water gap width of the fuel assembly by the preset amplitude. In this method, the appropriate adjustment method is selected according to the specific situation, and the water gap width of the fuel assembly is fine-tuned by increasing or decreasing the preset amplitude, thereby achieving precise water gap width adjustment.

[0156] Another method for determining core state parameters provided by an embodiment of the present application is described below. As shown in FIG10 , in one embodiment, before adjusting the water gap width of each fuel assembly in the three-dimensional core modified physical model of the target nuclear reactor based on the measured core power distribution, the method further includes the following steps:

[0157] S1001, obtaining the current unit rated parameters of the target nuclear reactor, the core loading plan of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor.

[0158] The current unit rated parameters of the target nuclear reactor include its design parameters, fuel characteristics, cooling system, etc. The core loading scheme refers to the layout and arrangement of the fuel assemblies. The historical operating conditions of the target nuclear reactor include its operating conditions over different time periods, such as power and temperature variations.

[0159] In one embodiment, the current unit rated parameters of the target nuclear reactor, the core loading plan of the target nuclear reactor and the historical operating conditions of the target nuclear reactor can be obtained by directly reading from a database, or by automatically generating the rated parameters, loading plan and historical operating conditions data based on historical experience data.

[0160] In another embodiment, by visiting the location of the nuclear reactor, obtaining permission and complying with safety regulations, on-site measurements are conducted to measure the actual measurement data of the nuclear reactor, and the actual measurement data of the nuclear reactor are analyzed and calculated to obtain the rated parameters of the nuclear reactor, the core loading plan and the historical operating conditions data.

[0161] S1002: Construct a three-dimensional core modified physical model of the target nuclear reactor according to the current unit rated parameters of the target nuclear reactor, the core loading plan of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor.

[0162] Alternatively, a 3D core-corrected physical model of the target nuclear reactor can be constructed using computer simulation software for modeling and analysis. In the simulation software, physical parameters such as the fuel assembly cross-section and reaction cross-section are set based on the rated parameters and core loading plan. Different historical operating conditions are also set to simulate various power and temperature variations. The simulation software is then run to construct the 3D core-corrected physical model of the target nuclear reactor.

[0163] In an embodiment of the present application, by obtaining the current unit rated parameters of the target nuclear reactor, the core loading scheme of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor, a three-dimensional core correction physical model of the target nuclear reactor is constructed based on the current unit rated parameters of the target nuclear reactor, the core loading scheme of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor. In this method, the three-dimensional core correction physical model constructed by the current unit rated parameters, core loading scheme, and historical operating conditions of the target nuclear reactor can more accurately reflect the characteristics of the actual nuclear reactor, thereby improving the accuracy of the three-dimensional core correction physical model. Moreover, by analyzing the three-dimensional core correction physical model of the target nuclear reactor, the need for actual experiments can be reduced, reducing costs and time investment, while obtaining an accurate core power distribution.

[0164] Another method for determining core state parameters provided by an embodiment of the present application is described below. In one embodiment, during the process of adjusting the water gap width of each fuel assembly in a three-dimensional core correction physical model of a target nuclear reactor, the three-dimensional core correction physical model satisfies at least one of the following conditions:

[0165] The water gap width of each fuel assembly is only related to the fuel assembly itself and has no correlation with the actual spacing between adjacent fuel assemblies; the water gap width of each fuel assembly in all directions has an equivalent impact on the assembly cross-section and assembly power of the fuel assembly itself; the assembly power of each fuel assembly is weakly correlated with the assembly power of other fuel assemblies.

[0166] The water gap width is adjusted independently for each fuel assembly, regardless of the influence of its neighboring fuel assemblies. This means that the water gap width of each fuel assembly is related only to its own characteristics and is not affected by the actual spacing between adjacent assemblies. The assembly water gap width is used as a direct correction to the cross-section of a single fuel assembly, thereby adjusting the power level of each assembly within the stack.

[0167] In one embodiment, a nuclear reactor contains a row of fuel assemblies, each with different materials and properties. This approach allows the water gap width of each assembly to be individually adjusted to achieve the desired power distribution. This independent adjustment allows for more precise control of the power distribution between different fuel assemblies, regardless of the influence of adjacent assemblies.

[0168] The water gap widths of each fuel assembly in all directions have equivalent effects on the cross-section and power of the fuel assembly itself. Therefore, the water gap widths on all sides can be set to be consistent. During the adjustment process, the water gap widths on all sides change synchronously, simplifying the four free parameters into one adjustable parameter. For hexagonal fuel assemblies, the water gap widths in all six directions change synchronously.

[0169] The assembly power of each fuel assembly is weakly correlated with the assembly power of other fuel assemblies. That is, the change in assembly cross-section caused by the water gap width of the current assembly and the resulting power change will not have a significant impact on the power levels of other surrounding assemblies.

[0170] In the embodiments of the present application, three assumptions are made: the water gap width of each fuel assembly is related only to the fuel assembly itself and has no correlation with the actual spacing between adjacent fuel assemblies. The water gap width of each fuel assembly in all directions has an equivalent effect on the assembly cross-section and assembly power of the fuel assembly itself, and the assembly power of each fuel assembly is weakly correlated with the assembly power of other fuel assemblies. In this method, the water gap width of each fuel assembly is related only to the fuel assembly itself. This assumption allows the water gap width of each fuel assembly to be adjusted and optimized independently without considering the interaction with adjacent assemblies. Treating the water gaps in the four directions of the fuel assembly as a single variable with the same amplitude of variation greatly simplifies the computational complexity. Furthermore, by setting the water gap width to be consistent, the symmetry of the fuel assembly can be maintained, resulting in balanced performance in all directions. The assembly power of each fuel assembly is weakly correlated with the assembly power of other fuel assemblies. This assumption allows the power of each fuel assembly to be adjusted and optimized independently without considering the interaction with other assemblies.

[0171] As shown in FIG11 , in one embodiment, the present application also provides a method for determining core state parameters, the method comprising:

[0172] S1101, obtaining the measured core power data of each nuclear reactor collected regularly by the nuclear power plant to which the target nuclear reactor belongs.

[0173] S1102: Determine the measured core power distribution of the target nuclear reactor based on the measured core power data of each nuclear reactor.

[0174] S1103 , obtaining the current unit rated parameters of the target nuclear reactor, the core loading plan of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor.

[0175] S1104 , constructing a three-dimensional core modified physical model of the target nuclear reactor based on the current unit rated parameters of the target nuclear reactor, the core loading plan of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor.

[0176] S1105, obtaining the latest component cross section of each fuel assembly in the three-dimensional core correction physical model.

[0177] S1106, determining the latest calculated assembly power of each fuel assembly based on the latest assembly cross-section of each fuel assembly.

[0178] S1107 , determining the latest calculated core power distribution of the three-dimensional core corrected physical model based on the latest calculated assembly power of each fuel assembly and the position of each fuel assembly in the three-dimensional core corrected physical model.

[0179] S1108, for any fuel assembly in the three-dimensional core corrected physical model, obtain the latest calculated assembly power of the fuel assembly in the latest calculated core power distribution, and obtain the measured assembly power of the fuel assembly in the measured core power distribution.

[0180] S1109: Determine a water gap width adjustment method for the fuel assembly based on the latest calculated assembly power and the actual measured assembly power.

[0181] S1110 , adjusting the water gap widths of corresponding fuel assemblies in sequence according to the numbering sequence of the fuel assemblies and the water gap width adjustment method of each fuel assembly.

[0182] S1111, if the latest calculated component power is greater than the actually measured component power, and the deviation ratio between the latest calculated component power and the actually measured component power is less than the preset ratio, then the water gap width adjustment method is determined to be to reduce the water gap width around the fuel assembly by a preset amplitude as a whole; if the latest calculated component power is less than the actually measured component power, and the deviation ratio between the latest calculated component power and the actually measured component power is greater than or equal to the preset ratio, then the water gap width adjustment method is determined to be to increase the water gap width around the fuel assembly by a preset amplitude as a whole.

[0183] S1112, for any fuel assembly, if the water gap width adjustment method of the fuel assembly is to increase the water gap width of the surrounding areas by a preset amplitude, the water gap width is adjusted by increasing the current water gap width of the fuel assembly by the preset amplitude; if the water gap width adjustment method of the fuel assembly is to decrease the water gap width of the surrounding areas by a preset amplitude, the water gap width is adjusted by decreasing the current water gap width of the fuel assembly by the preset amplitude.

[0184] S1113, calculating the core state parameters of the target nuclear reactor using the core correction physical model.

[0185] The implementation principle and process of the technical solution in this embodiment are similar to the implementation principle and process of the technical solution recorded in the above method. Therefore, its specific limitations can be found in the above limitations on the method for determining core state parameters, and will not be repeated here.

[0186] It should be understood that, although the various steps in the flowcharts involved in the various embodiments described above are displayed in sequence according to the instructions of the arrows, these steps are not necessarily executed in sequence 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 executed in other orders. Moreover, at least a portion of the steps in the flowcharts involved in the various embodiments described above can include multiple steps or multiple stages, and these steps or stages are not necessarily executed and completed at the same time, but can be executed at different times, and the execution order of these steps or stages is not necessarily to be carried out in sequence, but can be executed in turn or alternately with other steps or at least a portion of steps or stages in other steps.

[0187] Based on the same inventive concept, embodiments of the present application also provide a core state parameter determination device for implementing the aforementioned core state parameter determination 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 core state parameter determination device provided below can be found in the limitations of the core state parameter determination method described above and will not be further elaborated here.

[0188] In one embodiment, as shown in FIG12 , a core state parameter determination device is provided, which includes: an acquisition module 1201 , a physical model determination module 1202 , and a power state parameter determination module 1203 , wherein:

[0189] An acquisition module 1201 is used to obtain the measured core power distribution of the target nuclear reactor;

[0190] The physical model determination module 1202 is configured to adjust the water gap width of each fuel assembly in the three-dimensional core correction physical model of the target nuclear reactor based on the measured core power distribution, thereby obtaining the core correction physical model of the target nuclear reactor; wherein the deviation between the calculated core power distribution of the core correction physical model and the measured core power distribution is less than a preset value;

[0191] The power state parameter determination module 1203 is used to determine the core state parameters of the target nuclear reactor through the core correction physical model.

[0192] In one embodiment, the acquisition module 1201 includes:

[0193] The first acquisition unit is used to acquire the measured core power data of each nuclear reactor regularly collected by the nuclear power plant to which the target nuclear reactor belongs;

[0194] The first determining unit is used to determine the measured core power distribution of the target nuclear reactor based on the measured core power data of each nuclear reactor.

[0195] In one embodiment, the physical model determination module 1202 includes:

[0196] a first adjustment unit, configured to adjust the water gap width of each fuel assembly in the three-dimensional core modified physical model by executing a water gap width adjustment step according to the measured core power distribution;

[0197] The second adjustment unit is used to re-execute the water gap width adjustment step when the deviation between the calculated core power distribution of the adjusted three-dimensional core corrected physical model and the measured core power distribution is greater than or equal to a preset value, and stop the adjustment until the deviation between the calculated core power distribution of the adjusted three-dimensional core corrected physical model and the measured core power distribution is less than the preset value.

[0198] In one embodiment, the apparatus further comprises:

[0199] An assembly power acquisition module is used to obtain, for any fuel assembly in the three-dimensional core modified physical model, the latest calculated assembly power of the fuel assembly in the latest calculated core power distribution, and to obtain the measured assembly power of the fuel assembly in the measured core power distribution;

[0200] The adjustment mode determination module is used to determine the water gap width adjustment mode of the fuel assembly based on the latest calculated assembly power and the actual measured assembly power.

[0201] In one embodiment, the physical model determination module 1202 is further configured to:

[0202] If the latest calculated assembly power is greater than the actually measured assembly power, and the deviation ratio between the latest calculated assembly power and the actually measured assembly power is greater than or equal to a preset ratio, then the water gap width adjustment method is determined to be to reduce the water gap width around the fuel assembly by a preset amount.

[0203] If the latest calculated component power is less than the actually measured component power, and the deviation ratio between the latest calculated component power and the actually measured component power is less than a preset ratio, the water gap width adjustment method is determined to be to increase the water gap width around the fuel assembly by a preset amplitude.

[0204] In one embodiment, the adjustment mode determination module includes:

[0205] a first adjusting unit configured to adjust the water gap width of any fuel assembly by increasing the current water gap width of the fuel assembly by the value of the preset width if the water gap width adjustment method of the fuel assembly is to increase the water gap width of all four sides by a preset width;

[0206] The second adjusting unit is configured to adjust the water gap width by reducing the current water gap width of the fuel assembly by the preset value if the water gap width adjustment mode of the fuel assembly is to reduce the water gap widths of all four sides by a preset amount.

[0207] In one embodiment, the apparatus further comprises:

[0208] A first acquisition module is used to acquire the current unit rated parameters of the target nuclear reactor, the core loading plan of the target nuclear reactor and the historical operating conditions of the target nuclear reactor;

[0209] The construction module is used to construct a three-dimensional core correction physical model of the target nuclear reactor according to the current unit rated parameters of the target nuclear reactor, the core loading plan of the target nuclear reactor and the historical operating conditions of the target nuclear reactor.

[0210] Each module in the core state parameter determination apparatus described above may be implemented in whole or in part through software, hardware, or a combination thereof. Each module may be embedded in or independent of a processor in a computer device in the form of hardware, or may 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.

[0211] In one embodiment, a computer device is provided, including a memory and a processor. The memory stores a computer program, and the processor implements the steps in the above method embodiments when executing the computer program.

[0212] The computer device provided in the above embodiment has an implementation principle and technical effects similar to those of the above method embodiment, and will not be described in detail here.

[0213] In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored. When the computer program is executed by a processor, the technical solutions in the above-mentioned method embodiments are implemented.

[0214] The above embodiment provides a computer-readable storage medium, whose implementation principle and technical effects are similar to those of the above method embodiment, and will not be repeated here.

[0215] In one embodiment, a computer program product is provided, including a computer program. When the computer program is executed by a processor, the technical solutions in the above-mentioned method embodiments are implemented.

[0216] The above embodiment provides a computer program product, whose implementation principle and technical effects are similar to those of the above method embodiment, and will not be repeated here.

[0217] It should be noted that the data involved in this application (including but not limited to data used for analysis, stored data, displayed data, etc.) are all information or data fully authorized by all parties.

[0218] 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.

[0219] 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.

[0220] The above-described embodiments merely represent several implementation methods of the present application, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present invention. It should be noted that a person of ordinary skill in the art may make a number of modifications and improvements without departing from the concept of the present application, and these modifications and improvements fall within the scope of protection of the embodiments of the present application. Therefore, the scope of protection of the embodiments of the present application shall be subject to the appended claims.

Claims

1. A method for determining core state parameters, characterized in that, The method includes: Obtaining the measured core power distribution of the target nuclear reactor; Adjusting the water gap widths of the fuel assemblies in the three-dimensional core corrected physical model of the target nuclear reactor according to the measured core power distribution, to obtain the core corrected physical model of the target nuclear reactor; the deviation between the calculated core power distribution of the core corrected physical model and the measured core power distribution is less than a preset value; Determining the core state parameters of the target nuclear reactor through the core corrected physical model.

2. The method according to claim 1, wherein The obtaining the measured core power distribution of the target nuclear reactor includes: Obtaining the measured core power data of each nuclear reactor regularly collected by the nuclear power plant to which the target nuclear reactor belongs; Determining the measured core power distribution of the target nuclear reactor according to the measured core power data of each nuclear reactor.

3. The method according to claim 2, wherein The measured core power data includes fuel temperature, coolant temperature, pressure data at different parts of the nuclear reactor, and coolant flow rate data.

4. The method according to claim 1, characterized in that, The adjusting the water gap widths of the fuel assemblies in the three-dimensional core corrected physical model of the target nuclear reactor according to the measured core power distribution includes: Adjusting the water gap widths of the fuel assemblies in the three-dimensional core corrected physical model by performing the water gap width adjustment step according to the measured core power distribution; If the deviation between the calculated core power distribution of the adjusted three-dimensional core corrected physical model and the measured core power distribution is greater than or equal to the preset value, then re-perform the water gap width adjustment step until the deviation between the calculated core power distribution of the adjusted three-dimensional core corrected physical model and the measured core power distribution is less than the preset value, and stop the adjustment.

5. The method according to claim 4, characterized in that, The water gap width adjustment step includes: Obtaining the latest calculated core power distribution of the three-dimensional core corrected physical model; Determining the water gap width adjustment method for each fuel assembly in the three-dimensional core corrected physical model according to the latest calculated core power distribution and the measured core power distribution; Sequentially adjusting the water gap widths of the corresponding fuel assemblies according to the water gap width adjustment method of each fuel assembly in the order of the fuel assembly numbers.

6. The method according to claim 5, wherein The determining the water gap width adjustment method for each fuel assembly in the three-dimensional core corrected physical model according to the latest calculated core power distribution and the measured core power distribution includes: For any fuel assembly in the three-dimensional core corrected physical model, obtaining the latest calculated assembly power of the fuel assembly in the latest calculated core power distribution, and obtaining the measured assembly power of the fuel assembly in the measured core power distribution; Determining the water gap width adjustment method for the fuel assembly according to the latest calculated assembly power and the measured assembly power.

7. The method according to claim 6, wherein The determining the water gap width adjustment method for the fuel assembly according to the latest calculated assembly power and the measured assembly power includes: If the latest calculated component power is greater than the measured component power, and the deviation ratio between the latest calculated component power and the measured component power is greater than or equal to the preset ratio, it is determined that the adjustment method of the water gap width is to globally reduce the water gap width around the fuel assembly by a preset amplitude; If the latest calculated component power is less than the measured component power, and the deviation ratio between the latest calculated component power and the measured component power is less than the preset ratio, it is determined that the adjustment method of the water gap width is to globally increase the water gap width around the fuel assembly by the preset amplitude.

8. The method according to any one of claims 1 to 7, characterized in that, Before adjusting the water gap width of each fuel assembly in the three-dimensional core correction physical model of the target nuclear reactor according to the measured core power distribution, the method further includes: Obtaining the current unit rated parameters of the target nuclear reactor, the core loading scheme of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor; Constructing a three-dimensional core correction physical model of the target nuclear reactor according to the current unit rated parameters of the target nuclear reactor, the core loading scheme of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor.

9. The method according to any one of claims 1-7, characterized in that, The three-dimensional core correction physical model is a mathematical model used to describe and analyze the three-dimensional structure and physical processes inside the nuclear reactor.

10. The method according to any one of claims 1-7, characterized in that The fuel assembly is a complete set of fuel elements assembled together.

11. The method according to claim 10, wherein The fuel assembly is composed of fuel elements, upper nozzle, lower nozzle, control rods, guide tubes, and spacer grids.

12. The method according to any one of claims 1-7, characterized in that Different reactors use different fuel elements.

13. A device for determining core state parameters, characterized in that, The device includes: An acquisition module, configured to acquire the measured core power distribution of the target nuclear reactor; A physical model determination module, configured to adjust the water gap width of each fuel assembly in the three-dimensional core correction physical model of the target nuclear reactor according to the measured core power distribution, and obtain the core correction physical model of the target nuclear reactor; the deviation between the calculated core power distribution of the core correction physical model and the measured core power distribution is less than a preset value; A power state parameter determination module, configured to determine the core state parameters of the target nuclear reactor through the core correction physical model.

14. The device according to claim 13, wherein, The acquisition module includes: A first acquisition unit, configured to acquire the measured core power data of each nuclear reactor regularly collected by the nuclear power plant to which the target nuclear reactor belongs; A second acquisition unit, configured to determine the measured core power distribution of the target nuclear reactor according to the measured core power data of each nuclear reactor.

15. The device according to claim 13, characterized in that, The physical model determination module includes: A first adjustment unit, configured to adjust the water gap width of each fuel assembly in the three-dimensional core correction physical model by performing the water gap width adjustment step according to the measured core power distribution; A second adjustment unit, configured to re - execute the water gap width adjustment step when the deviation between the calculated core power distribution of the adjusted three - dimensional core corrected physical model and the measured core power distribution is greater than or equal to the preset value, until the deviation between the calculated core power distribution of the adjusted three - dimensional core corrected physical model and the measured core power distribution is less than the preset value, and then stop the adjustment.

16. The device according to claim 13, characterized in that, The device further includes: A component power acquisition module, configured to, for any fuel component in the three - dimensional core corrected physical model, acquire the latest calculated component power of the fuel component in the latest calculated core power distribution, and acquire the measured component power of the fuel component in the measured core power distribution; An adjustment method determination module, configured to determine the water gap width adjustment method for the fuel component according to the latest calculated component power and the measured component power.

17. The device according to claim 16, wherein The physical model determination module is further configured to, when the latest calculated component power is greater than the measured component power and the deviation ratio between the latest calculated component power and the measured component power is greater than or equal to a preset ratio, determine that the water gap width adjustment method is to globally reduce the water gap width around the fuel component by a preset amplitude; when the latest calculated component power is less than the measured component power and the deviation ratio between the latest calculated component power and the measured component power is less than the preset ratio, determine that the water gap width adjustment method is to globally increase the water gap width around the fuel component by the preset amplitude.

18. The device according to claim 13, wherein, The device further includes: A first acquisition module, configured to acquire the current unit rated parameters of the target nuclear reactor, the core loading scheme of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor; A construction module, configured to construct a three - dimensional core corrected physical model of the target nuclear reactor according to the current unit rated parameters of the target nuclear reactor, the core loading scheme of the target nuclear reactor, and the historical operating conditions of the target nuclear reactor.

19. A computer device, characterized in that, Comprising a memory and a processor, the memory stores a computer program, and the processor implements the steps in the method according to any one of claims 1 to 12 when executing the computer program.

20. A computer-readable storage medium having a computer program stored thereon, characterized in that, The computer program, when executed by the processor, implements the steps in the method according to any one of claims 1 to 12.

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