Full core fuel rod pci performance analysis method and middleware

Abstract

The application discloses a full-core fuel rod PCI performance analysis method and middleware, relates to the technical field of performance analysis under the irradiation condition of a reactor fuel rod, and meets the demand of batch analysis of the PCI performance of full-core fuel rods of a small reactor while improving analysis efficiency. The method comprises the following steps: obtaining core characteristic parameters of a core to be analyzed, and obtaining fuel rod characteristic parameters of each fuel rod to be analyzed; obtaining a fuel rod data file, reading steady-state neutron data and transient neutron data of each fuel rod to be analyzed in the fuel rod data file; fusing all the read data to generate an analysis input file; inputting multiple input files into a fuel rod performance analysis program, performing fuel rod performance analysis in parallel, and obtaining multiple fuel rod PCI performance analysis results output by the fuel rod performance analysis program; and collating the multiple fuel rod PCI performance analysis results to obtain fuel rod related information and output the fuel rod related information.

Description

Technical Field

[0001] This application relates to the field of performance analysis technology for reactor fuel rods under irradiation conditions, and in particular to a whole-core fuel rod PCI performance analysis method and middleware. Background Technology

[0002] In the nuclear energy field, small modular reactors (SMRs) possess broad application potential in energy supply, seawater desalination, and district heating due to their advantages of high flexibility, convenient deployment, and good safety. The safe and stable operation of SMRs relies heavily on the performance of the fuel rods, and the integrity of the fuel rod cladding, as a crucial barrier to prevent radioactive material leakage, is paramount. Under irradiation conditions, the fuel rods undergo pellet-cladding interaction (PCI), a complex physical and chemical process influenced by a combination of factors. During transient conditions such as reactor startup, shutdown, and power regulation, changes in fuel rod power alter the temperature of the pellets and cladding, generating thermal and mechanical stresses. Simultaneously, the swelling of the fuel pellets and the release of fission gases during irradiation exacerbate this interaction. Intense PCI can lead to cracks and damage in the cladding; once the cladding fails, radioactive material leakage will seriously threaten the safe operation of the reactor, as well as environmental and public health. Therefore, accurately analyzing the PCI performance of fuel rods under irradiation conditions and preventing cladding failure caused by PCI behavior is of great significance for ensuring the cladding integrity and reactor safety throughout the entire lifespan of small reactors.

[0003] However, the applicant recognized that traditional fuel rod PCI performance analysis programs often require fixed file format data as input and need to be used in conjunction with a systematic program. The input interface data format is highly fixed, and when the key structural parameters of the reactor change, it cannot adapt to the new data format and calculation requirements and cannot be used normally. Moreover, for fuel rods with different neutron parameters, traditional programs need to build calculation modules one by one and manually match steady-state and transient input modules. This process is time-consuming and prone to errors due to the large number of matching operations, which can easily affect the analysis efficiency and the accuracy of the analysis results, making it difficult to meet the needs of batch analysis of the full core fuel rod PCI performance of small reactors. Summary of the Invention

[0004] In view of this, this application provides a method and middleware for PCI performance analysis of all fuel rods in a reactor core. The main purpose is to solve the problems of traditional fuel rod PCI performance analysis programs that require fixed file format data as input and need to be used in conjunction with a systematic program. The input interface data format is highly fixed, and when the key structural parameters of the reactor change, it cannot adapt to the new data format and calculation requirements and cannot be used normally. Moreover, for fuel rods with different neutron parameters, traditional programs need to build calculation modules one by one and manually match steady-state and transient input modules. This process is time-consuming and prone to errors due to the large number of matching operations, which can easily affect the analysis efficiency and accuracy of the analysis results, making it difficult to meet the needs of batch analysis of the PCI performance of all fuel rods in a small reactor core.

[0005] According to a first aspect of this application, a method for analyzing the PCI performance of fuel rods in a reactor core is provided, the method comprising: The reactor core to be analyzed and multiple fuel rods to be analyzed are determined, the core characteristic parameters of the reactor core to be analyzed are obtained, and the fuel rod characteristic parameters of each fuel rod to be analyzed are obtained. Obtain the fuel rod data file, and read the steady-state neutronics data and transient neutronics data of each fuel rod to be analyzed from the fuel rod data file; Based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed, multiple analysis input files for the multiple fuel rods to be analyzed are generated. The multiple analysis input files are input into the fuel rod performance analysis program to perform parallel analysis of the PCI performance of the entire core fuel rods and obtain the PCI performance analysis results of multiple fuel rods output by the fuel rod performance analysis program. The PCI performance analysis results of the multiple fuel rods are compiled to obtain relevant fuel rod information and output it.

[0006] According to a second aspect of this application, middleware is provided, which is configured with an automatic reading module and performs parallel performance analysis of the PCI of all fuel rods in the reactor core by calling a fuel rod performance analysis program, including: The acquisition module is used to determine the reactor core to be analyzed and multiple fuel rods to be analyzed, acquire the core characteristic parameters of the reactor core to be analyzed, and acquire the fuel rod characteristic parameters of each of the fuel rods to be analyzed. The acquisition module is also used to acquire a fuel rod data file and read steady-state neutronics data and transient neutronics data of each fuel rod to be analyzed from the fuel rod data file. The generation module is used to generate multiple analysis input files for the multiple fuel rods to be analyzed based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed. The analysis module is used to input the multiple analysis input files into the fuel rod performance analysis program, perform parallel analysis of the PCI performance of the entire core fuel rods, and obtain the multiple fuel rod PCI performance analysis results output by the fuel rod performance analysis program. The processing module is used to process the PCI performance analysis results of the multiple fuel rods, obtain relevant fuel rod information, and output it.

[0007] According to a third aspect of this application, a computer device is provided, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to implement the steps of the method described in any of the first aspects above.

[0008] According to a fourth aspect of this application, a computer-readable storage medium is provided, on which a computer program is stored, wherein the computer program, when executed by a processor, implements the steps of the method described in any one of the first aspects above.

[0009] Using the above technical solution, this application provides a whole-core fuel rod PCI performance analysis method and middleware. This application determines the core to be analyzed and multiple fuel rods to be analyzed, obtains the core characteristic parameters of the core to be analyzed, and obtains the fuel rod characteristic parameters of each fuel rod to be analyzed, obtains fuel rod data files, reads the steady-state neutronics data and transient neutronics data of each fuel rod to be analyzed from the fuel rod data files, and generates multiple analysis input files for multiple fuel rods to be analyzed based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed. These multiple analysis input files are then processed. The data is input into the fuel rod performance analysis program, which performs parallel analysis of the PCI performance of all fuel rods in the reactor core. The program then outputs multiple fuel rod PCI performance analysis results, organizes these results, and outputs the relevant fuel rod information. It can automatically read relevant data from fuel rod data files and perform batch performance analysis on multiple fuel rods simultaneously. There are no restrictions on the format of the fuel rod data files, and the entire analysis process requires no manual intervention, avoiding errors caused by manual operation. This improves analysis efficiency while meeting the needs of batch analysis of the PCI performance of all fuel rods in a small reactor core.

[0010] The above description is only an overview of the technical solution of this application. In order to better understand the technical means of this application and to implement it in accordance with the contents of the specification, and to make the above and other objects, features and advantages of this application more obvious and understandable, the following are specific embodiments of this application. Attached Figure Description

[0011] Various other advantages and benefits will become apparent to those skilled in the art upon reading the following detailed description of preferred embodiments. The accompanying drawings are for illustrative purposes only and are not intended to limit the scope of this application. Furthermore, the same reference numerals denote the same parts throughout the drawings. In the drawings: Figure 1 This paper illustrates a flowchart of a full-core fuel rod PCI performance analysis method provided in an embodiment of this application. Figure 2A This paper illustrates a schematic diagram of another full-core fuel rod PCI performance analysis method provided in an embodiment of this application. Figure 2B This paper illustrates a schematic diagram of another full-core fuel rod PCI performance analysis method provided in an embodiment of this application. Figure 3 This illustration shows a structural schematic diagram of a full-core fuel rod PCI performance analysis middleware provided in an embodiment of this application; Figure 4 A schematic diagram of the device structure of a computer device provided in an embodiment of this application is shown. Detailed Implementation

[0012] Exemplary embodiments of the present application will now be described in more detail with reference to the accompanying drawings. While exemplary embodiments of the present application are shown in the drawings, it should be understood that the present application may be implemented in various forms and should not be limited to the embodiments set forth herein. Rather, these embodiments are provided so that this application will be thorough and complete, and will fully convey the scope of the present application to those skilled in the art.

[0013] This application provides a method for analyzing the PCI performance of all fuel rods in a reactor core, such as... Figure 1 As shown, the method includes: 101. Determine the reactor core to be analyzed and multiple fuel rods to be analyzed, obtain the core characteristic parameters of the reactor core to be analyzed, and obtain the fuel rod characteristic parameters of each fuel rod to be analyzed.

[0014] The technical solution of this application embodiment can be applied to a PCI performance analysis system. The PCI performance analysis system integrates a front-end interactive interface and a back-end computing engine to construct a fully automated analysis system from data input to result output. The front-end of the PCI performance analysis system can adopt a web-based operating interface, allowing staff to access a unified portal through a browser and complete operations such as uploading fuel rod data files and configuring core operating parameters in a visual panel. The PCI performance analysis system supports mainstream engineering data formats. After intelligent parsing and automatic recognition of user-uploaded CSV / Excel / HDF5 files, the PCI performance analysis system extracts key parameters such as steady-state neutron flux distribution and transient power change curves. Simultaneously, it correlates with the core thermal parameter database to achieve dynamic binding of fuel rod geometric characteristics, material properties, and core operating conditions. The back-end computing engine deploys a fuel rod performance analysis program. When staff submit an analysis task, the PCI performance analysis system uses a task scheduler to allocate all core fuel rods to different computing nodes, simultaneously performing calculations on multiple fuel rods. The fuel rod performance analysis program, based on the core-fuel rod coupling parameters in the input file, runs a thermal-hydraulic model, a neutron dynamics model, and a PCI failure prediction algorithm to calculate key indicators such as cladding stress and oxide layer thickness. During the analysis, the PCI performance analysis system records intermediate calculation results in real time through an in-memory database. After processing the final results by the fusion module, it generates fuel rod-related information including a 3D thermogram, a risk matrix, and a structured report. Staff can view fuel rod-related information and trace the historical parameter evolution trajectory through interactive charts on the front-end interface, providing quantitative support for reactor safe operation decisions.

[0015] In this embodiment, the reactor core to be analyzed is the core area in a nuclear reactor where fuel rod PCI performance analysis needs to be carried out. It consists of numerous fuel rods and supporting structures, and its operating state directly affects the performance of the fuel rods. The fuel rods to be analyzed are the specific objects in the core whose PCI performance needs to be evaluated. Each fuel rod has a different position and operating conditions within the core. Core characteristic parameters are key information describing the overall operation and structural characteristics of the core. For example, the core power distribution reflects the magnitude and trend of power at different locations in the core and has a significant impact on the heating and thermal stress distribution of the fuel rods; the coolant flow rate determines the coolant's ability to remove heat, thus affecting the temperature of the fuel rods; core geometric dimensions such as height and diameter affect the distribution of neutrons within the core and the arrangement of the fuel rods. Fuel rod characteristic parameters focus on the fuel rods themselves. For example, the cladding material has different physical and chemical properties, which affect PCI performance; the fuel pellet size (diameter, height) affects the internal heat conduction and stress distribution of the fuel rods; and the fuel rod enrichment (the content of fissile nuclides in the fuel) affects the reactivity and power output of the fuel rods. In practice, the reactor core and fuel rods to be analyzed can be determined by consulting the design documents and operation records of the nuclear reactor, and the corresponding core characteristic parameters and fuel rod characteristic parameters can be extracted from them.

[0016] For example, in a small nuclear reactor project, the staff identified the reactor core to be analyzed and the 50 fuel rods within it by studying the design drawings and operation logs. They also obtained core characteristic parameters such as power distribution and coolant flow rate, as well as fuel rod characteristic parameters such as cladding material and fuel pellet size, providing an accurate data foundation for subsequent analysis.

[0017] 102. Obtain the fuel rod data file and read the steady-state and transient neutronics data of each fuel rod to be analyzed from the fuel rod data file.

[0018] In this embodiment, the fuel rod data file serves as a carrier for storing fuel rod-related data. Its text format is diverse, including Excel, Word, and other text formats. Steady-state neutronics data reflects the neutronics characteristics of the fuel rod under stable operating conditions, such as neutron flux distribution. This describes the spatial distribution of neutrons within the fuel rod and plays a crucial role in power generation and heat distribution. Reactivity reflects the fuel rod's ability to multiply or absorb neutrons, affecting the overall reactivity of the reactor core. Transient neutronics data records neutronics changes in the fuel rod during transient processes (such as startup, shutdown, and power regulation), such as transient neutron flux changes. This reflects the dynamic changes in the number of neutrons in the fuel rod under transient conditions and is essential for evaluating the PCI performance of the fuel rod during transient processes.

[0019] After obtaining the fuel rod data file, the PCI performance analysis system can extract the steady-state and transient neutronics data of each fuel rod to be analyzed from the fuel rod data file using a specific reading program or tool, based on the file format and data structure.

[0020] For example, in a Word-format fuel rod data file, a Python script read steady-state neutron flux distribution data and transient neutron flux variation data of 50 fuel rods to be analyzed. This data provides neutronological basis for subsequent performance analysis and helps to accurately evaluate the PCI performance of fuel rods under different operating conditions.

[0021] 103. Based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed, generate multiple analysis input files for multiple fuel rods to be analyzed.

[0022] In this embodiment of the application, the analysis input file is a file used to input into the fuel rod performance analysis program. It contains various parameters and data required for PCI performance analysis. When generating this file, the core characteristic parameters (such as core power distribution, coolant flow rate, geometry, etc.), the fuel rod characteristic parameters of each fuel rod to be analyzed (such as cladding material, fuel pellet size, enrichment, etc.), steady-state neutronics data (such as steady-state neutron flux distribution, reactivity, etc.), and transient neutronics data (such as transient neutron flux changes, etc.) need to be organized and integrated according to the format required by the performance analysis program.

[0023] For example, some performance analysis programs may require data to be arranged according to specific data structures (such as tables, matrices, etc.) and with necessary labels and annotations to ensure the program can correctly read and understand the data. The PCI performance analysis system will then generate an input file based on the previously acquired core characteristic parameters, the characteristic parameters of the 50 fuel rods to be analyzed, and neutronics data, according to the format required by the performance analysis program. This input file contains comprehensive information needed for the analysis, providing standardized input for subsequent performance analysis, avoiding errors caused by inconsistent data formats or missing information, and improving the accuracy and reliability of the analysis.

[0024] 104. Input multiple analysis input files into the fuel rod performance analysis program, perform parallel analysis of the PCI performance of the entire core fuel rods, and obtain the PCI performance analysis results of multiple fuel rods output by the fuel rod performance analysis program.

[0025] In this embodiment, the fuel rod performance analysis program is a software tool used to evaluate the PCI performance of fuel rods. It can simulate the PCI process of fuel rods under different operating conditions based on input parameters and data, and calculate the corresponding performance indicators. When the fuel rod performance analysis program is invoked, the PCI performance analysis system uses it to perform parallel analysis on multiple fuel rods to be analyzed, thereby fully utilizing the multi-core processing power of the computer and improving analysis efficiency.

[0026] During parallel analysis, the PCI performance analysis system inputs the generated analysis files into the fuel rod performance analysis program. The program then calculates and analyzes the input data to obtain PCI performance analysis results for each fuel rod, such as cladding stress, strain, and oxidation status. For example, by starting the fuel rod performance analysis program and inputting the files into it, 50 fuel rods can be analyzed in parallel. This parallel analysis significantly reduces analysis time, allowing tasks that would normally take hours or even days to complete in a shorter time. Furthermore, the analysis of each fuel rod is relatively independent and does not interfere with each other, ensuring the accuracy of the results and providing rich data for subsequent data processing.

[0027] 105. Organize the PCI performance analysis results of multiple fuel rods, obtain relevant fuel rod information, and output it.

[0028] In this embodiment, the PCI performance analysis system organizes the PCI performance analysis results of multiple fuel rods. Organizing involves summarizing, classifying, and categorizing the scattered results output by the fuel rod performance analysis program. Specifically, firstly, the PCI performance analysis system cleans the data from the multiple fuel rod PCI performance analysis results to remove potential errors or abnormal data, ensuring the accuracy and reliability of the data. Then, the results are classified according to information such as the fuel rod's number and location, grouping the analysis results of the same fuel rod together. Next, statistical analysis is performed on the classified results, such as calculating average, maximum, and minimum values, to obtain and output relevant fuel rod information, enabling staff to comprehensively understand the PCI performance of the fuel rods. The fuel rod information can be output in a specific format (such as reports or tables) for easy viewing and use by staff, providing important data for reactor design, operation, and maintenance, avoiding errors and omissions that may occur during manual data processing, and improving work efficiency and the accuracy of results.

[0029] The method provided in this application embodiment determines the reactor core to be analyzed and multiple fuel rods to be analyzed, obtains the core characteristic parameters of the reactor core to be analyzed, obtains the fuel rod characteristic parameters of each fuel rod to be analyzed, obtains a fuel rod data file, reads the steady-state neutronics data and transient neutronics data of each fuel rod to be analyzed from the fuel rod data file, and generates multiple analysis input files for multiple fuel rods to be analyzed based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed, and inputs the multiple analysis input files into the fuel rod performance analysis program. The system performs parallel analysis of the PCI performance of all fuel rods in the reactor core, and obtains the PCI performance analysis results of multiple fuel rods output by the fuel rod performance analysis program. The system organizes the PCI performance analysis results of multiple fuel rods, obtains relevant fuel rod information, and outputs it. It can automatically read relevant data from the fuel rod data file and perform batch performance analysis of multiple fuel rods simultaneously. It does not restrict the format of the fuel rod data file, and the entire analysis process does not require manual intervention, avoiding errors caused by manual operation. While improving analysis efficiency, it meets the needs of batch analysis of the PCI performance of all fuel rods in the small reactor core.

[0030] Furthermore, as a refinement and extension of the specific implementation methods of the above embodiments, and in order to fully illustrate the specific implementation process of this embodiment, this application provides another method for full-core fuel rod PCI performance analysis, such as... Figure 2A As shown, the method includes: 201. Determine the reactor core to be analyzed and multiple fuel rods to be analyzed, obtain the core characteristic parameters of the reactor core to be analyzed, and obtain the fuel rod characteristic parameters of each fuel rod to be analyzed.

[0031] The technical solution of this application embodiment can be applied to the PCI performance analysis system. For details of the PCI performance analysis system, please refer to the description in step 101 of the above embodiment, which will not be repeated here.

[0032] In the field of reactor design and analysis, the reactor core under analysis refers to the specific core part of a reactor that requires performance evaluation, and it includes numerous components such as fuel rods. The fuel rod under analysis is the individual fuel rod being studied within the reactor core. Core characteristic parameters encompass key information such as the reactor's power level, coolant flow rate, and temperature distribution; these parameters are crucial for accurately simulating the reactor core's operating state. Fuel rod characteristic parameters include the fuel rod's size, material composition, and enrichment; these parameters determine the fuel rod's inherent physical properties.

[0033] In practical applications, the PCI performance analysis system first determines the scope of the reactor core to be analyzed and the multiple fuel rods within it using reactor design drawings or relevant databases. Then, it obtains core characteristic parameters from reactor design documents, operational records, and other materials, such as the core's rated power and coolant inlet temperature from the design documents. Simultaneously, it retrieves fuel rod characteristic parameters for each fuel rod from production records, quality inspection reports, and other documents, such as the fuel rod's length, diameter, and fuel pellet enrichment from the production records. This provides fundamental data for subsequent performance analysis, ensuring the accuracy and relevance of the analysis.

[0034] 202. Obtain the fuel rod data file and read the steady-state and transient neutronics data of each fuel rod to be analyzed from the fuel rod data file.

[0035] In this embodiment, the fuel rod data file is a carrier for storing fuel rod-related data, and it can be in various formats, such as Excel, Word, etc. Steady-state neutronics data describes the neutronics characteristics of the fuel rod under steady-state operation, including information such as power distribution and burnup; transient neutronics data reflects the neutronics behavior of the fuel rod during transient processes, such as transient power changes.

[0036] Specifically, the PCI performance analysis system can first determine the storage location of the fuel rod data file, such as storing it in a specific folder on a local computer or on a remote server. Then, it uses appropriate software tools to open the file, such as using Excel software to open an Excel-formatted fuel rod data file. In the file, by searching for specific data tags or column names, it locates and reads the steady-state and transient neutronics data of each fuel rod to be analyzed. This application does not limit the file format of the fuel rod data file; data can be read regardless of the format, enabling more convenient acquisition of neutronics data of fuel rods under different operating conditions, providing raw data support for subsequent data parsing and analysis.

[0037] 203. Analyze the steady-state neutronics data of each fuel rod to be analyzed to obtain the fuel rod parameters under multiple steady-state operating conditions for each fuel rod to be analyzed.

[0038] In this embodiment, the PCI performance analysis system first displays the read fuel assembly number, fuel rod number, and the number of cycles the fuel rod has undergone in the corresponding program interface or output window based on the read data information. The fuel assembly number is a unique identifier for a fuel assembly, the fuel rod number is an individual identifier for the fuel rod, and the number of cycles the fuel rod has undergone reflects the number of times the fuel rod has been used and its operational stage in the reactor. Displaying this information facilitates understanding of the data source and the basic information of the fuel rods for the staff. For example, in a reactor fuel rod performance analysis project, if a fuel assembly number of A1 and a fuel rod number of 01 are read, and the fuel rod has undergone 3 cycles, this information will be clearly displayed on the program interface, providing a basic background for subsequent analysis.

[0039] The PCI performance analysis system analyzes the steady-state neutronics data of each fuel rod to obtain multiple steady-state fuel rod parameters. These steady-state parameters include power output, peak power factor, axial power distribution parameters, and time-burnup conversion factor. The power output reflects the energy output of the fuel rod at different time steps; the peak power factor measures the maximum fluctuation in fuel rod power; the axial power distribution parameter describes the power distribution along the axial direction of the fuel rod; and the time-burnup conversion factor is related to the change in fuel rod burnup over time. Specifically, for each fuel rod to be analyzed, the PCI performance analysis system can calculate its power value at different time steps using specific algorithms or formulas based on steady-state neutronics data. Based on the calculated power values, the peak power factor is statistically analyzed, which can be determined by finding the ratio of the maximum power to the average power. Then, using the power distribution information in the steady-state neutronics data, steady-state axial power distribution parameters are calculated, such as by using piecewise integration to calculate the power proportion of different axial segments. Next, the burnup at each time step is determined with reference to the steady-state neutronics data, and the time-burnup conversion factor is calculated based on the change in burnup over time, for example, by linearly fitting the relationship between burnup and time. Finally, the power value, peak power factor, axial power distribution parameters, and time-burnup conversion factor of the fuel rod under analysis at different time steps are all treated as fuel rod parameters under steady-state conditions, resulting in multiple fuel rod parameters under steady-state conditions. This allows for a comprehensive and in-depth analysis of the fuel rod's performance characteristics under steady-state conditions, providing rich parameter information for subsequent performance evaluation and ensuring the safe operation of the reactor.

[0040] 204. Analyze the transient neutronics data of each fuel rod to be analyzed to obtain the fuel rod parameters under multiple transient operating conditions for each fuel rod to be analyzed.

[0041] In this embodiment, the PCI performance analysis system analyzes the transient neutronics data of each fuel rod to be analyzed, obtaining multiple fuel rod parameters under various transient conditions for each fuel rod. During reactor operation, transient conditions have a crucial impact on fuel rod performance, especially the most restrictive Type II transient. These transients typically represent extreme and potentially risky situations in reactor operation, and their corresponding neutronics data can reflect the fuel rod's response characteristics under extreme conditions. Key parameters of the fuel rod under the most restrictive Type II transient include transient power change curves, peak power, power change rate, and axial power transient distribution characteristics. These parameters are crucial for evaluating the safety and performance of the fuel rod under transient conditions. Therefore, this embodiment analyzes the neutronics data of the fuel rod under the most restrictive Type II transient, i.e., it analyzes the neutronics data of each fuel rod under the most restrictive Type II transient.

[0042] Specifically, after reading transient neutronics data from the fuel rod data file, the PCI performance analysis system can filter out neutronics data for fuel rods under the most confined Type II transient based on data identifiers or specific conditions. Most confined Type II transients are usually clearly identified in the data records, such as specific transient type codes or operating condition descriptions. By identifying these identifiers, data that meets the conditions for most confined Type II transients is extracted, ensuring the accuracy and relevance of subsequent analysis. For example, in reactor operation data records, a most confined Type II transient might be marked as "II - Max." By searching for this marker, relevant data can be filtered from a large amount of transient data.

[0043] Next, for each fuel rod to be analyzed, the PCI performance analysis system uses the transient neutronics data of the fuel rod to calculate the transient axial power distribution parameters at different transient moments. Specifically, piecewise integration calculations can be performed using a method similar to steady-state calculations. Then, referring to the transient neutronics data, multiple factors affecting temperature are determined, such as coolant flow rate and power variation. Combining these factors, the reactor inlet temperature is calculated, specifically using a thermo-hydraulic model. Further, the coolant mass flow rate at different transient moments is extracted from the transient neutronics data, and the system operating pressure is calculated based on the reactor inlet temperature and the coolant mass flow rate at different transient moments. Specifically, the system operating pressure is calculated using thermodynamic formulas. Finally, the transient axial power distribution parameters, reactor inlet temperature, coolant mass flow rate, and system operating pressure of the fuel rod at different transient moments are all treated as one transient fuel rod parameter, resulting in multiple transient fuel rod parameters. This allows for the acquisition of key parameters of the fuel rod during the transient process, providing a basis for evaluating the performance of the fuel rod under transient conditions.

[0044] 205. For each fuel rod to be analyzed, obtain a preset file template, write the core characteristic parameters into the corresponding positions of the relevant parameters in the preset file template, and write the fuel rod characteristic parameters, fuel rod parameters under multiple steady-state conditions, and fuel rod parameters under multiple transient conditions of the fuel rod to be analyzed into the corresponding positions of the relevant parameters in the preset file template. Use the preset file template after writing as the analysis input file for the fuel rod to be analyzed, and obtain multiple analysis input files for multiple fuel rods to be analyzed.

[0045] In this embodiment, the preset file template is a pre-designed file format that includes specific locations for storing core characteristic parameters, fuel rod characteristic parameters, and fuel rod parameters under steady-state and transient operating conditions. For each fuel rod to be analyzed, the PCI performance analysis system obtains the preset file template, writes the core characteristic parameters into the corresponding positions in the preset file template, and writes the fuel rod characteristic parameters, fuel rod parameters under multiple steady-state operating conditions, and fuel rod parameters under multiple transient operating conditions for each fuel rod to be analyzed into the corresponding positions in the preset file template. The written preset file template is then used as the analysis input file for the fuel rod to be analyzed, resulting in multiple analysis input files for multiple fuel rods to be analyzed. These files can be recognized and read by the fuel rod performance analysis program.

[0046] Specifically, the PCI performance analysis system can retrieve preset file templates from the database, and then use a programming language or specialized file processing tools to write core characteristic parameters, such as core power and coolant flow rate, into the corresponding positions in the template. Similarly, the PCI performance analysis system continues to write the fuel rod characteristic parameters for each fuel rod to be analyzed, such as fuel rod size and enrichment, as well as fuel rod parameters under steady-state and transient conditions, such as power value, peak power factor, and transient axial power distribution parameters, into the corresponding positions in the template. After writing, the file is saved as the analysis input file, thus integrating various parameters into a single file, providing standardized input for the fuel rod performance analysis program, facilitating program invocation and analysis, and improving the efficiency and accuracy of the analysis.

[0047] 206. Set steady-state analysis parameters for each fuel rod performance analysis program through its program interface, so that when fuel rod performance analysis is carried out in parallel, the fuel rod performance analysis program refers to the set steady-state analysis parameters to perform performance analysis on the corresponding fuel rod under steady-state conditions.

[0048] In order to enable the fuel rod performance analysis program to accurately simulate the operation of the fuel rod under steady-state conditions, in this embodiment of the application, the PCI performance analysis system sets steady-state analysis parameters for each fuel rod performance analysis program through the program interface of each fuel rod performance analysis program. This allows the fuel rod performance analysis program to perform steady-state performance analysis on the corresponding fuel rod under the corresponding analysis condition by referring to the set steady-state analysis parameters when performing fuel rod performance analysis in parallel.

[0049] Specifically, when conducting batch fuel rod performance analysis, the PCI performance analysis system sets fuel assembly names and steady-state power history correction factors for fuel rods belonging to the same fuel assembly. The fuel assembly name is used to uniquely identify the fuel assembly to which the fuel rod belongs, ensuring it corresponds to the actual fuel assembly being analyzed. The steady-state power history correction factor is used to correct the historical power data of the fuel rod and can be determined based on historical data and experience. The system then acquires the enrichment degree and neutron fluence corresponding to the fuel assembly input for each fuel rod performance analysis program. The enrichment degree reflects the content of fissile nuclides in the fuel, while the neutron fluence is related to the distribution and intensity of neutrons in the fuel, and sets these values ​​in the corresponding fuel rod performance analysis program.

[0050] 207. Through the program interface of each fuel rod performance analysis program, set transient analysis parameters for each fuel rod to be analyzed, so that when fuel rod performance analysis is carried out in parallel, the fuel rod performance analysis program refers to the set transient analysis parameters to perform performance analysis on the corresponding fuel rod under transient operating conditions.

[0051] In order to enable the fuel rod performance analysis program to accurately simulate the behavior of fuel rods during transient processes, in this embodiment of the application, the PCI performance analysis system sets transient analysis parameters for each fuel rod to be analyzed through the program interface of each fuel rod performance analysis program, so that when fuel rod performance analysis is carried out in parallel, the fuel rod performance analysis program refers to the set transient analysis parameters to perform performance analysis on the corresponding fuel rod under transient operating conditions.

[0052] Specifically, the PCI performance analysis system will find the transient analysis parameter setting option in the program interface of each fuel rod performance analysis program. Select the transient to be analyzed by PCI. The transient to be analyzed by PCI determines the scope of the analysis. In this embodiment, all transient moments are selected by default, but they can also be filtered according to actual needs. Then, modify the transient identifier name, which is used to uniquely identify the transient process. Then, set at least one transient moment to be analyzed for each fuel rod to be analyzed. The transient moment to be analyzed is the time point of focus. For each transient moment to be analyzed, the PCI performance analysis system will set a transient power history uncertainty factor, which is used to consider the uncertainty of power history. Continue to read the burnup step corresponding to each preset transient type in the steady-state neutronics data. The burnup step corresponding to each preset transient type is related to the burnup change in the transient process, and set it in each fuel rod performance analysis program to complete the setting of transient analysis parameters. In this way, by setting the transient analysis parameters appropriately, the fuel rod performance analysis program can accurately simulate the behavior of fuel rods during transient processes, ensuring that the analysis can comprehensively and accurately evaluate the performance of fuel rods during transient processes, and providing strong support for the transient safety assessment of the reactor.

[0053] 208. Input multiple analysis input files into the fuel rod performance analysis program, perform parallel analysis of the PCI performance of the entire core fuel rods, and obtain the PCI performance analysis results of multiple fuel rods output by the fuel rod performance analysis program.

[0054] In this embodiment of the application, the PCI performance analysis system inputs multiple analysis input files into the fuel rod performance analysis program, performs parallel analysis of the PCI performance of the entire core fuel rods, and obtains multiple fuel rod PCI performance analysis results output by the fuel rod performance analysis program.

[0055] Specifically, the PCI performance analysis system can use programming languages ​​or specialized scheduling tools to simultaneously input multiple analysis input files into the fuel rod performance analysis program. Then, the program is started, allowing it to perform parallel PCI performance analysis of all fuel rods in the reactor core. During program execution, the PCI performance analysis system can monitor the program's running status in real time to ensure smooth analysis. After analysis, the PCI performance analysis system retrieves the output fuel rod PCI performance analysis results from the fuel rod performance analysis program, enabling rapid and efficient analysis of the PCI performance of all fuel rods in the reactor core, significantly reducing analysis time and improving analysis efficiency.

[0056] 209. Organize the PCI performance analysis results of multiple fuel rods, obtain relevant fuel rod information and output it.

[0057] In this embodiment of the application, after completing the fuel rod PCI performance analysis, in order to facilitate subsequent research, archiving and intuitive presentation of the analysis results, the PCI performance analysis system will output the relevant data in both text file and graphic information formats.

[0058] For text file output, the PCI performance analysis system organizes the PCI performance analysis results of multiple fuel rods, dividing the analysis data belonging to the same fuel rod into the same file as the analysis result file corresponding to the fuel rod to be analyzed, resulting in multiple analysis result files corresponding to multiple fuel rods to be analyzed. For each analysis result file, the fuel assembly name of the fuel assembly to which the fuel rod to be analyzed belongs is determined, the fuel rod number of the fuel rod to be analyzed is determined, and the addition transient time of the fuel rod to be analyzed is queried. The analysis result file is labeled with the fuel assembly name, fuel rod number, and addition transient time. In practical applications, the PCI performance analysis system can generate a unique file for each fuel rod to be analyzed using the naming convention of "component name.fuel rod number.add transient time". For example, if the component name of a fuel rod is "B2", the fuel rod number is "08", and the added transient time is "200s", then the corresponding file name can be "B2.08.200s". This file will record in detail the various data of the PCI analysis of the fuel rod, covering the key parameters involved in the analysis process, calculation results, etc., to ensure the integrity and traceability of the analysis data.

[0059] For graphical information, the PCI performance analysis system generates a minimum PCI safety margin distribution map and a table of fuel rod information for each operating condition based on the PCI performance analysis results of multiple fuel rods. When generating the minimum PCI safety margin distribution map, the system determines the relevant information of the fuel rods with the minimum PCI safety margin in each fuel rod performance analysis program, and uses this information to plot the minimum PCI safety margin distribution map. The fuel rod information includes the fuel rod number and the axial segment number, burnup, line power, and PCI margin corresponding to the minimum PCI margin. This distribution map is presented as a core fuel assembly distribution map, which includes system biases considered in the PCI calculation and details the relevant information of the fuel rods with the minimum PCI safety margin in each fuel assembly, including the fuel rod number, the axial segment number, burnup, line power, and PCI margin corresponding to the minimum PCI margin. This distribution map provides a clear overview of the PCI safety margin distribution in the reactor core, as well as which fuel rods have relatively low PCI safety margins.

[0060] When generating the most extreme fuel rod information table for each operating condition, it is necessary to determine the relevant information of the fuel rod with the smallest PCI margin under steady-state conditions and the relevant information of the fuel rod with the smallest PCI margin under transient conditions based on the PCI performance analysis results of multiple fuel rods. Using the relevant information of the fuel rod with the smallest PCI margin under steady-state conditions and the relevant information of the fuel rod with the smallest PCI margin under transient conditions, the most extreme fuel rod information table for each operating condition is generated. The information on the fuel rod with the smallest PCI margin under steady-state conditions or under transient conditions includes the fuel rod number, the component location of the fuel rod to be analyzed indicated by the fuel rod number, the stress or strain at the moment of minimum PCI margin, power, axial segment, and fuel consumption. In other words, the information table of the most extreme fuel rod under each operating condition provides the relevant information of the fuel rod with the smallest PCI margin under each operating condition in tabular form. Specifically, it includes the component location of the fuel rod in its respective fuel assembly, the fuel rod number, the stress or strain at the moment of minimum PCI margin, power, axial segment, and fuel consumption. Through this information table, the fuel rod that needs the most attention under each operating condition can be quickly located, providing a basis for subsequent safety assessment and improvement measures.

[0061] Finally, multiple analysis result files, the PCI minimum safety margin distribution chart, and the fuel rod information table for the most extreme conditions under each operating condition can be output as fuel rod related information, making it easier for staff to intuitively understand the PCI performance of the fuel rods.

[0062] In summary, in practical applications, the technical solution of this application embodiment is as follows: See Figure 2B First, the relevant parameter data from the fuel rod performance analysis program, along with steady-state and transient neutronics data, are read. Then, based on this data, steady-state and transient power histories are calculated, generating the average power and axial power distribution of each fuel rod for each irradiation time step during both steady-state and transient periods. Subsequently, an analysis input file for Type II transients of the entire reactor core is generated, and the fuel rod performance analysis program is invoked to perform parallel full-core calculations for multiple transients. After the calculations are completed, the output of the fuel rod performance analysis program is read, the PCI technical indicators are calculated, and they are compared with the corresponding PCI technical limits. Finally, fuel rod-related information, such as the core PCI margin, is obtained, completing the full-core fuel rod PCI performance analysis.

[0063] The method provided in this application embodiment can automatically read relevant data from the fuel rod data file and perform batch performance analysis on multiple fuel rods simultaneously. It does not limit the format of the fuel rod data file, and the entire analysis process does not require manual intervention, avoiding errors caused by manual operation. While improving analysis efficiency, it meets the needs of batch analysis of the PCI performance of fuel rods in the entire core of small reactors.

[0064] Furthermore, as Figure 1To specifically implement the method, this application provides a middleware, such as... Figure 3 As shown, the middleware is configured with an automatic reading module and performs full-core fuel rod PCI performance analysis in parallel by calling the fuel rod performance analysis program. The middleware includes: an acquisition module 301, a generation module 302, an analysis module 303, and a sorting module 304.

[0065] The acquisition module 301 is used to determine the reactor core to be analyzed and multiple fuel rods to be analyzed, acquire the core characteristic parameters of the reactor core to be analyzed, and acquire the fuel rod characteristic parameters of each of the fuel rods to be analyzed. The acquisition module 301 is also used to acquire a fuel rod data file and read steady-state neutronics data and transient neutronics data for each fuel rod to be analyzed from the fuel rod data file; The generation module 302 is used to generate multiple analysis input files for the multiple fuel rods to be analyzed based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed. The analysis module 303 is used to input the multiple analysis input files into the fuel rod performance analysis program, perform parallel analysis of the PCI performance of the entire core fuel rods, and obtain the multiple fuel rod PCI performance analysis results output by the fuel rod performance analysis program. The processing module 304 is used to process the PCI performance analysis results of the multiple fuel rods, obtain relevant fuel rod information, and output it.

[0066] In a specific application scenario, the generation module 302 is used to parse the steady-state neutronics data of each fuel rod to be analyzed, and obtain fuel rod parameters under multiple steady-state operating conditions for each fuel rod; to parse the transient neutronics data of each fuel rod to be analyzed, and obtain fuel rod parameters under multiple transient operating conditions for each fuel rod; for each fuel rod to be analyzed, a preset file template is obtained, the core characteristic parameters are written into the positions corresponding to the relevant parameters in the preset file template, and the fuel rod characteristic parameters, fuel rod parameters under multiple steady-state operating conditions, and fuel rod parameters under multiple transient operating conditions of the fuel rod to be analyzed are written into the positions corresponding to the relevant parameters in the preset file template, and the preset file template after writing is used as the analysis input file for the fuel rod to be analyzed, thereby obtaining multiple analysis input files for the multiple fuel rods to be analyzed.

[0067] In a specific application scenario, the generation module 302 is used to, for each fuel rod to be analyzed, calculate the power value of the fuel rod at different time steps based on the steady-state neutronics data of the fuel rod to be analyzed; calculate the steady-state axial power distribution parameters of the fuel rod to be analyzed at different time steps using the steady-state neutronics data; determine the fuel consumption of the fuel rod to be analyzed at each time step with reference to the steady-state neutronics data, and calculate the time-fuel consumption conversion factor of the fuel rod to be analyzed based on the fuel consumption at each time step; and take the power value of the fuel rod to be analyzed at different time steps, the peak power factor, the axial power distribution parameters, and the time-fuel consumption conversion factor as fuel rod parameters under steady-state conditions to obtain the fuel rod parameters under multiple steady-state conditions.

[0068] In a specific application scenario, the generation module 302 is used to, for each fuel rod to be analyzed, calculate the transient power peak factor and transient axial power distribution parameters of the fuel rod at different transient moments using the transient neutronics data of the fuel rod to be analyzed; determine multiple factors affecting temperature by referring to the transient neutronics data, and calculate the reactor inlet temperature by combining the multiple factors; extract the coolant mass flow rate at different transient moments from the transient neutronics data; calculate the system operating pressure based on the reactor inlet temperature and the coolant mass flow rate at different transient moments; and take the transient axial power distribution parameters of the fuel rod to be analyzed at different transient moments, the reactor inlet temperature, the coolant mass flow rate at different transient moments, and the system operating pressure as one transient fuel rod parameter to obtain the multiple transient fuel rod parameters.

[0069] In specific application scenarios, the device also includes: The configuration module is used to set steady-state analysis parameters for each fuel rod performance analysis program through its program interface, so that when fuel rod performance analyses are performed in parallel, the fuel rod performance analysis program refers to the set steady-state analysis parameters to perform performance analysis on the corresponding fuel rod under steady-state operating conditions; and to set transient analysis parameters for each fuel rod under analysis through its program interface, so that when fuel rod performance analyses are performed in parallel, the fuel rod performance analysis program refers to the set transient analysis parameters to perform performance analysis on the corresponding fuel rod under transient operating conditions.

[0070] In specific application scenarios, this setting module is used to set the fuel assembly name for fuel rods belonging to the same fuel assembly and to set the steady-state power history correction factor when performing batch fuel rod performance analysis; to obtain the enrichment degree and neutron flux rate corresponding to the fuel assembly input for each fuel rod performance analysis program, and to set the enrichment degree and neutron flux rate in the corresponding fuel rod performance analysis program to complete the setting of the steady-state analysis parameters.

[0071] In specific application scenarios, this setting module is used to set at least one transient moment to be analyzed for each fuel rod to be analyzed, and to set a transient power history uncertainty factor for each transient moment to be analyzed; to read the burnup step corresponding to each of the multiple preset transient types from the steady-state neutronics data, and to set the burnup step corresponding to each of the preset transient types in each fuel rod performance analysis program, thereby completing the setting of the transient analysis parameters.

[0072] In a specific application scenario, the sorting module 304 is used to sort the PCI performance analysis results of the multiple fuel rods, divide the analysis data belonging to the same fuel rod to be analyzed into the same file as the analysis result file corresponding to the fuel rod to be analyzed, and obtain multiple analysis result files corresponding to the multiple fuel rods to be analyzed. Among them, for each analysis result file, the fuel assembly name of the fuel assembly to which the fuel rod to be analyzed belongs is determined, the fuel rod number of the fuel rod to be analyzed is determined, the addition transient time corresponding to the fuel rod to be analyzed is queried, and the analysis result file is labeled with the fuel assembly name, the fuel rod number, and the addition transient time. Based on the PCI performance analysis results of the multiple fuel rods, a PCI minimum safety margin distribution map and a fuel rod information table of the most extreme under each operating condition are generated, and the multiple analysis result files, the PCI minimum safety margin distribution map, and the fuel rod information table of the most extreme under each operating condition are used as fuel rod related information and output.

[0073] In specific application scenarios, the processing module 304 is used to determine, based on the PCI performance analysis results of the multiple fuel rods, the relevant information of the fuel rod with the minimum PCI safety margin in each fuel assembly currently being analyzed, and to draw the PCI minimum safety margin distribution map using the relevant information of the fuel rods corresponding to each fuel assembly. The relevant fuel rod information includes the fuel rod number and the axial segment number, fuel consumption, linear power, and PCI margin corresponding to the minimum PCI margin. Based on the PCI performance analysis results of the multiple fuel rods, the relevant information of the fuel rod with the minimum PCI margin under steady-state conditions is determined. The information includes the fuel rod with the minimum PCI margin under transient conditions. Using the information of the fuel rod with the minimum PCI margin under steady-state conditions and the information of the fuel rod with the minimum PCI margin under transient conditions, a fuel rod information table for the most extreme conditions is generated. The information of the fuel rod with the minimum PCI margin under steady-state conditions or the information of the fuel rod with the minimum PCI margin under transient conditions includes the fuel rod number, the component position of the fuel rod to be analyzed in its fuel assembly indicated by the fuel rod number, the stress or strain at the moment of minimum PCI margin, power, axial segment, and fuel consumption.

[0074] The middleware provided in this application determines the reactor core to be analyzed and multiple fuel rods to be analyzed, obtains the core characteristic parameters of the reactor core to be analyzed, obtains the fuel rod characteristic parameters of each fuel rod to be analyzed, obtains fuel rod data files, reads the steady-state neutronics data and transient neutronics data of each fuel rod to be analyzed from the fuel rod data files, and generates multiple analysis input files for the multiple fuel rods to be analyzed based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed. These multiple analysis input files are then input into the fuel rod performance analysis program. The system performs parallel analysis of the PCI performance of all fuel rods in the reactor core, and obtains the PCI performance analysis results of multiple fuel rods output by the fuel rod performance analysis program. The system organizes the PCI performance analysis results of multiple fuel rods, obtains relevant fuel rod information, and outputs it. It can automatically read relevant data from the fuel rod data file and perform batch performance analysis of multiple fuel rods simultaneously. It does not restrict the format of the fuel rod data file, and the entire analysis process does not require manual intervention, avoiding errors caused by manual operation. While improving analysis efficiency, it meets the needs of batch analysis of the PCI performance of all fuel rods in the small reactor core.

[0075] It should be noted that other corresponding descriptions of the functional units involved in the whole-core fuel rod PCI performance analysis middleware provided in this application embodiment can be found in the following references. Figure 1 and Figures 2A to 2B The corresponding descriptions in [the document] will not be repeated here.

[0076] It should be noted that the user information (including but not limited to user device information, user personal information, etc.) and data (including but not limited to data used for analysis, data stored, data displayed, etc.) involved in this application are all information and data authorized by the user or fully authorized by all parties.

[0077] The above embodiments and the technical features in the embodiments can be combined arbitrarily. For the sake of brevity, 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.

[0078] The embodiments described above are merely illustrative of several implementation methods of this application, and while the descriptions are specific and detailed, they should not be construed as limiting the scope of this patent application. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of this application, and these all fall within the protection scope of this application. Therefore, the protection scope of this application should be determined by the appended claims.

[0079] In an exemplary embodiment, see Figure 4 The invention also provides a computer device including a bus, a processor, a memory, and a communication interface. It may also include an input / output interface and a display device, wherein the various functional units can communicate with each other via the bus. The memory stores a computer program, and the processor executes the program stored in the memory to perform the full-core fuel rod PCI performance analysis method described in the above embodiments.

[0080] A computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the steps of the whole-core fuel rod PCI performance analysis method.

[0081] Through the above description of the embodiments, those skilled in the art can clearly understand that this application can be implemented in hardware or by using software plus necessary general-purpose hardware platforms. Based on this understanding, the technical solution of this application can be embodied in the form of a software product, which can be stored in a non-volatile storage medium (such as a CD-ROM, USB flash drive, external hard drive, etc.) and includes several instructions to cause a computer device (such as a personal computer, server, or network device, etc.) to execute the methods described in the various embodiments of this application.

[0082] Those skilled in the art will understand that the accompanying drawings are merely schematic diagrams of a preferred embodiment, and the modules or processes shown in the drawings are not necessarily essential for implementing this application.

[0083] Those skilled in the art will understand that the modules in the apparatus of the implementation scenario can be distributed within the apparatus of the implementation scenario as described, or they can be located in one or more apparatuses different from this implementation scenario, with corresponding changes. The modules of the above-described implementation scenario can be combined into one module, or they can be further divided into multiple sub-modules.

[0084] The serial numbers in this application are for descriptive purposes only and do not represent the superiority or inferiority of the implementation scenario.

[0085] The above disclosures are only a few specific implementation scenarios of this application. However, this application is not limited to these. Any variations that can be conceived by those skilled in the art should fall within the protection scope of this application.

Claims

1. A method for analyzing the PCI performance of fuel rods throughout a reactor core, characterized in that, include: The reactor core to be analyzed and multiple fuel rods to be analyzed are determined, the core characteristic parameters of the reactor core to be analyzed are obtained, and the fuel rod characteristic parameters of each fuel rod to be analyzed are obtained. Obtain the fuel rod data file, and read the steady-state neutronics data and transient neutronics data of each fuel rod to be analyzed from the fuel rod data file; Based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed, multiple analysis input files for the multiple fuel rods to be analyzed are generated. The multiple analysis input files are input into the fuel rod performance analysis program to perform parallel analysis of the PCI performance of the entire core fuel rods and obtain the PCI performance analysis results of multiple fuel rods output by the fuel rod performance analysis program. The PCI performance analysis results of the multiple fuel rods are compiled to obtain relevant fuel rod information and output it.

2. The method according to claim 1, characterized in that, Based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed, multiple analysis input files are generated for the multiple fuel rods to be analyzed, including: The steady-state neutronics data of each fuel rod to be analyzed are analyzed to obtain the fuel rod parameters under multiple steady-state operating conditions for each fuel rod to be analyzed. The transient neutronics data of each fuel rod to be analyzed are analyzed to obtain multiple transient fuel rod parameters for each fuel rod to be analyzed. For each fuel rod to be analyzed, a preset file template is obtained, and the core characteristic parameters are written into the positions corresponding to the relevant parameters in the preset file template. The fuel rod characteristic parameters, fuel rod parameters under multiple steady-state conditions, and fuel rod parameters under multiple transient conditions of the fuel rod to be analyzed are also written into the positions corresponding to the relevant parameters in the preset file template. The preset file template after writing is used as the analysis input file for the fuel rod to be analyzed, thus obtaining multiple analysis input files for the multiple fuel rods to be analyzed.

3. The method according to claim 2, characterized in that, The steady-state neutronics data of each fuel rod to be analyzed are analyzed to obtain multiple fuel rod parameters under steady-state operating conditions for each fuel rod to be analyzed, including: For each of the fuel rods to be analyzed, the power value of the fuel rod at different time steps is calculated based on the steady-state neutronics data of the fuel rod. Using the steady-state neutronics data, the steady-state axial power distribution parameters of the fuel rod under analysis at different time steps are calculated; The burnup of the fuel rod to be analyzed at each time step is determined by referring to the steady-state neutronics data, and the time-burnup conversion factor of the fuel rod to be analyzed is calculated based on the burnup at each time step. The power value of the fuel rod under analysis at different time steps, the peak power factor, the axial power distribution parameter, and the time-fuel consumption conversion factor are all taken as fuel rod parameters under steady-state conditions to obtain the fuel rod parameters under multiple steady-state conditions.

4. The method according to claim 2, characterized in that, The transient neutronics data of each fuel rod to be analyzed are analyzed to obtain multiple transient fuel rod parameters for each fuel rod to be analyzed, including: For each of the fuel rods to be analyzed, the transient power peak factor and transient axial power distribution parameters of the fuel rods to be analyzed at different transient moments are calculated using the transient neutronics data of the fuel rods to be analyzed. The transient neutronics data were used to determine multiple factors affecting the temperature, and the reactor inlet temperature was calculated by combining these multiple factors. Extract the coolant mass flow rate at different transient moments from the transient neutronics data; Calculate the system operating pressure based on the reactor inlet temperature and the coolant mass flow rate at different transient moments; The transient axial power distribution parameters of the fuel rod under different transient moments, the reactor inlet temperature, the coolant mass flow rate at different transient moments, and the system operating pressure are all taken as one transient fuel rod parameter to obtain the multiple transient fuel rod parameters.

5. The method according to claim 1, characterized in that, Before inputting the multiple analysis input files into the fuel rod performance analysis program, performing parallel analysis of the PCI performance of the entire reactor core fuel rods, and obtaining the multiple fuel rod PCI performance analysis results output by the fuel rod performance analysis program, the method further includes: Through the program interface of each fuel rod performance analysis program, steady-state analysis parameters are set for each fuel rod performance analysis program so that when fuel rod performance analysis is carried out in parallel, the fuel rod performance analysis program refers to the set steady-state analysis parameters to perform performance analysis on the corresponding fuel rod under steady-state operating conditions. Through the program interface of each fuel rod performance analysis program, transient analysis parameters are set for each fuel rod to be analyzed, so that when fuel rod performance analysis is carried out in parallel, the fuel rod performance analysis program refers to the set transient analysis parameters to perform performance analysis on the corresponding fuel rod under transient operating conditions.

6. The method according to claim 5, characterized in that, The step of setting steady-state analysis parameters for each fuel rod performance analysis program includes: When conducting batch fuel rod performance analysis, set the fuel assembly name for fuel rods belonging to the same fuel assembly, and set the steady-state power history correction factor. Obtain the enrichment degree and neutron flux rate of the fuel assembly corresponding to each fuel rod performance analysis program input, and set the enrichment degree and neutron flux rate in the corresponding fuel rod performance analysis program to complete the setting of the steady-state analysis parameters.

7. The method according to claim 5, characterized in that, The step of setting transient analysis parameters for each of the fuel rods to be analyzed includes: For each of the fuel rods to be analyzed, at least one transient moment to be analyzed is set, and for each of the transient moments to be analyzed, a transient power history uncertainty factor is set; The burnup step corresponding to each of the preset transient types is read from the steady-state neutronics data, and the burnup step corresponding to each preset transient type is set in each fuel rod performance analysis program to complete the setting of the transient analysis parameters.

8. The method according to claim 1, characterized in that, The process of organizing the PCI performance analysis results of the multiple fuel rods to obtain and output relevant fuel rod information includes: The PCI performance analysis results of the multiple fuel rods are organized, and the analysis data belonging to the same fuel rod to be analyzed are divided into the same file as the analysis result file corresponding to the fuel rod to be analyzed, thus obtaining multiple analysis result files corresponding to the multiple fuel rods to be analyzed. For each analysis result file, the fuel assembly name of the fuel assembly to which the fuel rod to be analyzed belongs is determined, the fuel rod number of the fuel rod to be analyzed is determined, and the addition transient time corresponding to the fuel rod to be analyzed is queried. The analysis result file is labeled using the fuel assembly name, the fuel rod number, and the addition transient time. Based on the PCI performance analysis results of the multiple fuel rods, a minimum safety margin distribution map of PCI and a fuel rod information table of the most extreme conditions under each operating condition are generated. The multiple analysis result files, the minimum safety margin distribution map of PCI, and the fuel rod information table of the most extreme conditions under each operating condition are used as fuel rod related information and output.

9. The method according to claim 8, characterized in that, Based on the PCI performance analysis results of the multiple fuel rods, a minimum safety margin distribution map of PCI and a fuel rod information table for the most extreme conditions under each operating condition are generated, including: Based on the PCI performance analysis results of the multiple fuel rods, the relevant information of the fuel rods with the minimum PCI safety margin in each fuel assembly currently being analyzed is determined, and the distribution map of the minimum PCI safety margin is drawn using the relevant information of the fuel rods corresponding to each fuel assembly. The relevant information of the fuel rods includes the fuel rod number and the axial segment number, fuel consumption, linear power, and PCI margin corresponding to the minimum PCI margin. Based on the PCI performance analysis results of the multiple fuel rods, the relevant information of the fuel rod with the smallest PCI margin under steady-state conditions and the relevant information of the fuel rod with the smallest PCI margin under transient conditions are determined. Using the relevant information of the fuel rod with the smallest PCI margin under steady-state conditions and the relevant information of the fuel rod with the smallest PCI margin under transient conditions, the most extreme fuel rod information table for each operating condition is generated. The relevant information of the fuel rod with the smallest PCI margin under steady-state conditions or the relevant information of the fuel rod with the smallest PCI margin under transient conditions includes the fuel rod number, the component position of the fuel rod to be analyzed in its respective fuel assembly indicated by the fuel rod number, the stress or strain at the moment of minimum PCI margin, power, axial segment, and fuel consumption.

10. A middleware, characterized in that, The middleware is configured with an automatic reading module and performs parallel performance analysis of the entire core fuel rod PCI by calling the fuel rod performance analysis program, including: The acquisition module is used to determine the reactor core to be analyzed and multiple fuel rods to be analyzed, acquire the core characteristic parameters of the reactor core to be analyzed, and acquire the fuel rod characteristic parameters of each of the fuel rods to be analyzed. The acquisition module is also used to acquire a fuel rod data file and read steady-state neutronics data and transient neutronics data of each fuel rod to be analyzed from the fuel rod data file. The generation module is used to generate multiple analysis input files for the multiple fuel rods to be analyzed based on the core characteristic parameters and the fuel rod characteristic parameters, steady-state neutronics data, and transient neutronics data of each fuel rod to be analyzed. The analysis module is used to input the multiple analysis input files into the fuel rod performance analysis program, perform parallel analysis of the PCI performance of the entire core fuel rods, and obtain the multiple fuel rod PCI performance analysis results output by the fuel rod performance analysis program. The processing module is used to process the PCI performance analysis results of the multiple fuel rods, obtain relevant fuel rod information, and output it.

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