Method and device for core operating safety analysis in case of fuel loading error

Abstract

The application discloses a method and device for analyzing the safety of a reactor core under a fuel loading error condition, wherein the method comprises the following steps: obtaining a plurality of core block misloading conditions corresponding to a plurality of new fuel assemblies of the reactor core in a fuel cycle scheme; combining the plurality of new fuel assemblies according to the number of the new fuel assemblies, the number of the assemblies allowed to have the core block misloading and the core block misloading conditions corresponding to the plurality of new fuel assemblies to obtain a plurality of core block misloading conditions of the reactor core; and simulating the burnup of the reactor core under the plurality of core block misloading conditions to determine the safety of the reactor core under the core block misloading condition. Thus, the safety of the reactor core under the core block misloading of the fuel rod is analyzed.

Description

Technical Field

[0001] This application belongs to the field of nuclear reactor analysis technology, specifically relating to a method and apparatus for core operation safety analysis under fuel loading error conditions. Background Technology

[0002] Fuel assemblies are the core components of a pressurized water reactor (PWR) core, secured within the core by components such as positioning grids and upper and lower tube mounts. The core loading scheme generated through core fuel management design determines the optimal arrangement of each fuel assembly within the core for each fuel cycle.

[0003] With the development of technology and processes, in order to improve the safety and economy of pressurized water reactor core operation, fuel rods with axial partitions have been designed and gradually applied. These fuel rods are assembled from different types of fuel pellets. Compared with fuel rods without axial partitions, there is a greater risk and a higher probability of misloading of fuel pellets during the manufacturing and assembly process.

[0004] However, there is a lack of corresponding core safety analysis methods for misloading of fuel rods. Summary of the Invention

[0005] This application aims to provide a method and apparatus for core operation safety analysis under fuel loading error conditions, at least to solve the problem of the lack of corresponding core safety analysis methods for fuel rod misloading.

[0006] To solve the above-mentioned technical problems, this application is implemented as follows: In a first aspect, embodiments of this application propose a method for analyzing the operational safety of a reactor core under fuel loading errors, comprising: for multiple new fuel assemblies replaced in the fuel cycle scheme, obtaining the chip misloading conditions corresponding to each of the multiple new fuel assemblies; combining the conditions of the multiple new fuel assemblies according to the number of assemblies in the reactor core that are allowed to have chip misloading, the number of the multiple new fuel assemblies, and the chip misloading conditions corresponding to the multiple new fuel assemblies, to obtain multiple chip misloading conditions of the reactor core; and simulating and calculating the burnup of the reactor core under the multiple chip misloading conditions of the reactor core to determine the operational safety of the reactor core under chip loading errors.

[0007] In some embodiments, obtaining the pellet misloading conditions corresponding to multiple new fuel assemblies replaced in the fuel cycle scheme includes: finding the pellet misloading conditions corresponding to multiple new fuel assemblies from a variety of pellet misloading conditions corresponding to multiple fuel assemblies, based on the assembly types corresponding to the multiple new fuel assemblies; wherein, for each of the fuel assemblies, the pellet misloading condition of the fuel assembly is selected from a variety of pellet misloading candidate conditions based on the degree of influence of the multiple pellet misloading candidate conditions of the fuel assembly.

[0008] In some embodiments, the pellet misloading condition of the fuel assembly is obtained through the following steps: Based on the number of fuel rods allowed to be misloaded in the fuel assembly, the number of fuel rods in the fuel assembly with axial partitioning, and various pellet misloading conditions of the fuel rods in the fuel assembly with axial partitioning, multiple fuel rods are combined to generate multiple candidate pellet misloading conditions; under the multiple candidate pellet misloading conditions, the fuel rod power of the fuel assembly is simulated and calculated to obtain the fuel rod power distribution corresponding to each of the multiple candidate pellet misloading conditions; based on the fuel rod power distribution corresponding to each of the multiple candidate pellet misloading conditions, the pellet misloading condition of the fuel assembly is selected from the multiple candidate pellet misloading conditions.

[0009] In some embodiments, under multiple candidate conditions for incorrect pellet loading, the fuel rod power of the fuel assembly is simulated and calculated to obtain the fuel rod power distribution corresponding to each of the multiple candidate conditions for incorrect pellet loading. This includes: referring to the multiple candidate conditions for incorrect pellet loading, the fuel rod is replaced with a condition in a first physical calculation model to obtain multiple second physical calculation models. The first physical calculation model is used to simulate the correct loading condition of the fuel assembly, and the second physical calculation models are used to simulate the candidate conditions for incorrect pellet loading corresponding to the second physical calculation models. The fuel rod power of the fuel assembly is calculated using the multiple second physical calculation models to obtain the fuel rod power distribution corresponding to each of the multiple candidate conditions for incorrect pellet loading.

[0010] In some embodiments, selecting the misloading condition of the fuel assembly from the multiple candidate fuel rod power distributions corresponding to the multiple misloading candidate conditions includes: comparing the fuel rod power distributions corresponding to the multiple misloading candidate conditions with the fuel rod power distribution of the fuel assembly under the correct loading condition to obtain the power distribution deviations corresponding to the multiple misloading candidate conditions; selecting the misloading condition of the fuel assembly from the multiple misloading candidate conditions based on the power distribution deviations corresponding to the multiple misloading candidate conditions; wherein the fuel rod power distribution of the fuel assembly under the correct loading condition is calculated by a first physical calculation model, which is used to simulate the correct loading condition of the fuel assembly.

[0011] In some embodiments, the various pellet misloading conditions of the fuel rod are obtained through the following steps: obtaining the detection accuracy of the fuel rod and the pellet length of the fuel rod; determining a pellet misloading number threshold at a single axial partition interface in the fuel rod based on the detection accuracy and the pellet length; and determining various pellet misloading conditions of the fuel rod based on the pellet misloading number threshold and the number of axial partitions of the fuel rod.

[0012] In some embodiments, the step of simulating and calculating the burnup of the reactor core under various misloading conditions of the reactor core to determine the operational safety of the reactor core under misloading conditions includes: simulating and calculating the burnup of the reactor core under various misloading conditions of the reactor core to obtain the nuclear enthalpy rise factor value corresponding to each of the various misloading conditions of the reactor core; and determining the operational safety of the reactor core under misloading conditions based on the nuclear enthalpy rise factor value corresponding to each of the various misloading conditions of the reactor core.

[0013] In some embodiments, the step of simulating and calculating the burnup of the reactor core under various misloading conditions of the reactor core to obtain the nuclear enthalpy rise factor values ​​corresponding to the various misloading conditions of the reactor core includes: referring to the various misloading conditions of the reactor core, replacing the conditions of the new fuel assembly in a third physical calculation model to obtain multiple fourth physical calculation models, wherein the third physical calculation model is used to simulate the correct loading condition of the reactor core, and the fourth physical calculation model is used to simulate the misloading condition of the reactor core corresponding to the fourth physical calculation model; and calculating the burnup of the reactor core using the multiple fourth physical calculation models to obtain the nuclear enthalpy rise factor values ​​corresponding to the various misloading conditions of the reactor core.

[0014] In some embodiments, determining the operational safety of the reactor core under incorrect chip loading conditions based on the nuclear enthalpy rise factor values ​​corresponding to various chip misloading conditions includes: comparing the nuclear enthalpy rise factor values ​​corresponding to various chip misloading conditions with the nuclear enthalpy rise factor value of the reactor core under correct loading conditions to determine the operational safety of the reactor core under incorrect chip loading conditions; wherein the nuclear enthalpy rise factor value of the reactor core under correct loading conditions is calculated by a third physics calculation model, which is used to simulate the correct loading conditions of the reactor core.

[0015] Secondly, embodiments of this application propose a core operation safety analysis device under fuel loading error conditions, comprising: a component condition acquisition unit, used to acquire, for multiple new fuel assemblies replaced in the fuel cycle scheme, the corresponding chip misloading conditions for each of the new fuel assemblies; a component condition combination unit, used to combine the conditions of the multiple new fuel assemblies according to the number of components in the core that are allowed to have chip misloading, the number of the multiple new fuel assemblies, and the chip misloading conditions corresponding to the multiple new fuel assemblies, to obtain multiple chip misloading conditions of the core; and a core safety determination unit, used to simulate and calculate the burnup of the core under the multiple chip misloading conditions of the core, and determine the operational safety of the core under chip loading error conditions.

[0016] Thirdly, embodiments of this application propose an electronic device, including: one or more processors; and a memory storing one or more programs, wherein when the one or more programs are executed by the one or more processors, the one or more processors implement the core operation safety analysis method under fuel loading error conditions as described in the first aspect.

[0017] Fourthly, embodiments of this application propose a computer-readable storage medium storing a computer program thereon, which, when executed by a processor, implements the core operation safety analysis method under fuel loading error conditions as described in the first aspect.

[0018] Fifthly, embodiments of this application propose a computer program product, including a computer program that, when executed by a processor, implements the core operation safety analysis method under fuel loading error conditions as described in the first aspect.

[0019] In the embodiments of this application, based on the number of components in the core that are allowed to be misloaded with fuel pellets, the number of new fuel assemblies replaced in the fuel cycle, and the corresponding misloaded fuel pellet conditions for each new fuel assembly, multiple misloaded fuel pellet conditions are combined to obtain various misloaded fuel pellet conditions for the core. This ensures that the multiple misloaded fuel pellet conditions cover all possible misloaded fuel pellet situations in the core, while avoiding an excessive number of conditions due to exhaustive enumeration of all possible conditions. Under these multiple misloaded fuel pellet conditions, the burnup of the core is simulated and calculated to determine the operational safety of the core under misloaded fuel pellet conditions. Thus, a core safety analysis scheme that can be practically applied in engineering is realized for fuel rod misloaded fuel pellets.

[0020] Additional aspects and advantages of this application will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of this application. Attached Figure Description

[0021] The accompanying drawings are used to provide a further understanding of the technical solutions of this application and constitute a part of the specification. They are used together with the embodiments of this application to explain the technical solutions of this application and do not constitute a limitation on the technical solutions of this application.

[0022] Figure 1 Example diagrams of fuel rods with and without axial partitioning provided for embodiments of this application.

[0023] Figure 2 This is a loading example diagram of a pressurized water reactor core provided in an embodiment of this application.

[0024] Figure 3 A flowchart illustrating the core operation safety analysis method under fuel loading error conditions provided in this application embodiment. Figure 1 .

[0025] Figure 4 This is a flowchart illustrating the process of determining the misloading condition of fuel assemblies in the core operation safety analysis method under fuel loading error provided in the embodiments of this application.

[0026] Figure 5 An example diagram of a fuel rod pellet misloading condition provided in an embodiment of this application.

[0027] Figure 6 This is an example diagram of a two-dimensional radial arrangement of a fuel assembly provided in an embodiment of this application.

[0028] Figure 7 A flowchart illustrating the core operation safety analysis method under fuel loading error conditions provided in this application embodiment. Figure 2 .

[0029] Figure 8 A schematic diagram of the core operation safety analysis device under fuel loading error conditions provided in this application embodiment.

[0030] Figure 9 This is a schematic diagram of the structure of an electronic device provided in an embodiment of this application. Detailed Implementation

[0031] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.

[0032] It should be understood that in the description of the embodiments of this application, the use of terms such as "first" and "second" is only for the purpose of distinguishing technical features and should not be construed as indicating or implying relative importance, or implicitly indicating the number of technical features indicated, or implicitly indicating the order of the technical features indicated. "At least one" refers to one or more, and "more" refers to two or more. "And / or" describes the relationship between related objects, indicating that three relationships can exist. For example, A and / or B can represent the existence of A alone, the simultaneous existence of A and B, or the existence of B alone. A and B can be singular or plural. The character " / " generally indicates that the preceding and following related objects are in an "or" relationship. "At least one of the following" and similar expressions refer to any group of these items, including any group of singular or plural items. For example, at least one of a, b, and c can represent: a, b, c, a and b, a and c, b and c, or a and b and c, where a, b, and c can be single or multiple.

[0033] During the actual core loading process, each fuel assembly is labeled with an identification code, and then loaded according to the core loading plan. During the loading phase, the following management measures are used to ensure that the fuel assemblies are loaded in their intended positions within the core: before each fuel assembly is moved to the core, its identification code is checked for correctness; after each fuel assembly is moved to the core, its identification code is recorded on the loading diagram so that the correctness of the loading can be further checked based on the loading diagram after loading is completed. Despite these management measures, core misloading accidents can still occur.

[0034] Core misloading accidents can be categorized into several types: incorrect core loading (e.g., fuel assemblies misplaced), a fuel rod loaded with one or more incorrectly enriched pellets, or an entire fuel assembly loaded with incorrectly enriched pellets. Theoretically, the possible misloading scenarios are virtually infinite, necessitating the selection of a limited number of specific scenarios for safety analysis.

[0035] Currently, the safety analysis of reactor cores faces the following challenges that need to be overcome: Problem 1: There is a lack of solutions for core safety analysis in response to misloading of fuel rod pellets.

[0036] In relevant core safety analysis methods, it is assumed that if the positions of fuel assemblies containing control rods and fuel assemblies without control rods are swapped, it will be detected when arranging the upper in-core components. Under this assumption, core safety analysis is performed for the swapping of the positions of the two fuel assemblies.

[0037] When a fuel assembly does not contain axially partitioned fuel rods, and each fuel assembly contains only one type of fuel pellet, misloading of fuel pellets can be avoided through quality control during manufacturing. Therefore, considering only fuel assembly position swapping aligns with practical safety analysis requirements. However, when a fuel assembly contains axially partitioned fuel rods, there is a risk of undetected misloading of fuel pellets at the axial partition interfaces of the fuel rods. It is necessary to conduct core safety analysis for fuel rod pellet misloading; however, a corresponding core safety analysis scheme is currently lacking.

[0038] For example, Figure 1 Example diagrams of fuel rods with and without axial partitioning provided for embodiments of this application. Figure 1 As shown, the axially partitioned fuel rods consist of different types of fuel pellets (such as... Figure 1 Fuel rods are assembled from type 1 and type 2 fuel pellets, while fuel rods without axial partitioning are assembled from a single type of fuel pellet. It is evident that fuel rods with axial partitioning pose a risk of misloading of fuel pellets without being detected.

[0039] Question 2: In order to assess the impact of misloading of cores on the safety of core operation, it is necessary to perform numerical simulation of the misloading conditions through core calculations. However, directly enumerating all the misloading conditions would result in a huge amount of computation for core safety analysis.

[0040] For example, Figure 2 This diagram illustrates a loading example of a pressurized water reactor core provided in this application embodiment. N represents the new fuel assemblies replaced in one loading cycle, with a total of 72 new fuel assemblies. Assuming that each new fuel assembly contains 16 fuel rods with axial partitioning, and each fuel rod is axially divided into two zones (i.e., each fuel rod contains one axial partition interface), and the number of possible misloading conditions for a single fuel rod is 2, then the number of misloading conditions for a single fuel assembly is... for: .

[0041] Each new fuel assembly loaded into the reactor core may experience misloading, therefore, the number of all misloading scenarios in the core calculation is... for: .

[0042] The calculation results above show that if all core misloading conditions are directly enumerated in the core calculation, the number of core misloading conditions will be huge, resulting in high computational cost and long computation time for core safety analysis, making it impossible to apply in engineering.

[0043] To address the aforementioned issues, this application provides a method and apparatus for analyzing reactor core operational safety under fuel loading errors. Based on the number of components allowed for core misloading, the number of new fuel assemblies replaced in the fuel cycle, and the corresponding core misloading conditions for each new fuel assembly, multiple core misloading conditions are combined to obtain various core misloading conditions. This ensures that the multiple core misloading conditions cover all possible core misloading scenarios. Furthermore, by limiting the number of components allowed for core misloading and the number of new fuel assemblies replaced in the fuel cycle, the number of core misloading conditions is constrained, avoiding an excessive number of conditions due to exhaustive enumeration. Under these multiple core misloading conditions, the reactor core's burnup is simulated to determine its operational safety under core loading errors. Thus, a core safety analysis scheme was developed to address the misloading of fuel rod pellets. While ensuring the comprehensiveness of the core safety analysis, the computational cost of the core safety analysis was effectively constrained, making the core safety analysis applicable to engineering projects.

[0044] The core operation safety analysis method under fuel loading error conditions provided in this application embodiment can be applied to electronic devices. Specifically, this method can be executed by electronic devices, or by components of electronic devices, such as processors, chips, or chip systems. It can also be implemented by logic modules or software that implement all or part of the functions of the electronic devices. In practical applications, electronic devices can be terminals, servers, service platforms, cloud computing, distributed systems, the Internet of Things, etc. Furthermore, terminals can be smartphones, tablets, laptops, desktop computers, etc.

[0045] The following description, in conjunction with the accompanying drawings, details the core operation safety analysis method provided in this application under fuel loading error conditions through an embodiment and its application scenario.

[0046] See Figure 3 , Figure 3 A flowchart illustrating the core operation safety analysis method under fuel loading error conditions provided in this application embodiment. Figure 1 .like Figure 3 As shown, the core operation safety analysis method under fuel loading error conditions includes, but is not limited to, the following steps: S301: For multiple new fuel assemblies replaced in the fuel cycle scheme of the reactor core, obtain the chip misloading conditions corresponding to each of the multiple new fuel assemblies.

[0047] Among them, the fuel cycle scheme of the reactor core refers to the fuel cycle loading scheme of the reactor core. Each cycle requires the replacement of multiple fuel assemblies. For easy distinction, the replaced fuel assemblies are referred to as new fuel assemblies.

[0048] Among them, the chip misloading condition can also be called the chip misloading scheme or chip misloading case.

[0049] In this embodiment, the pellet misloading conditions corresponding to the multiple new fuel assemblies can be predetermined. When core operation safety analysis is required, the pre-determined pellet misloading conditions for the multiple new fuel assemblies can be obtained.

[0050] In one possible implementation, for each new fuel assembly, the pellet misloading scenario for that new fuel assembly can be selected from multiple candidate scenarios based on their respective impact on core safety. This effectively filters multiple candidate scenarios based on their impact on core safety, preventing less impactful scenarios from participating in subsequent scenario combinations. This avoids an excessive number of scenarios involved in core safety analysis, reducing the computational load and cost of core safety analysis.

[0051] S302, based on the number of components in the reactor core that are allowed to be misloaded with fuel pellets, the number of multiple new fuel assemblies, and the fuel pellet misloading conditions corresponding to the multiple new fuel assemblies, the operating conditions of the multiple new fuel assemblies are combined to obtain multiple fuel pellet misloading conditions of the reactor core.

[0052] The number of components for which a core misloading is permissible refers to the number of new fuel assemblies for which a core misloading is permissible. The number of multiple new fuel assemblies refers to the total number of new fuel assemblies replaced during a single core loading cycle.

[0053] In this embodiment, the number of components allowed for misloading of fuel pellets in the reactor core can be obtained from the quality assurance parameters of the fuel manufacturer; the number of multiple new fuel assemblies can be obtained from the fuel cycle scheme of the reactor core; and the range of the number of new fuel assemblies with misloading of fuel pellets in the reactor core can be determined based on the number of components allowed for misloading of fuel pellets in the reactor core. Based on this range, the number of multiple new fuel assemblies, and the corresponding misloading conditions for each of the multiple new fuel assemblies, the operating conditions of the multiple new fuel assemblies are arranged and combined to obtain various misloading conditions for the reactor core. In the above arrangement and combination process, mathematical permutation and combination methods can be used to determine the various misloading conditions for the reactor core.

[0054] In one possible implementation, the upper bound of the range of new fuel assemblies with misloaded pellets in the core is equal to the number of assemblies in the core that are allowed to be misloaded pellets, and the lower bound of the range is equal to 1.

[0055] In one possible implementation, the number of various core misloading conditions is: ; in, This indicates the number of various core misloading conditions in the reactor core. This indicates the number of components that are allowed to be misloaded in the reactor core. This indicates the number of new fuel components, where C represents the symbol for permutations and combinations in mathematical statistics.

[0056] It is evident that, under the constraints of the number of components in the reactor core that are allowed to be misloaded, the number of multiple new fuel assemblies in the reactor core, and the misloaded conditions corresponding to each of the multiple new fuel assemblies, multiple misloaded conditions of the reactor core can be accurately obtained through permutations and combinations in mathematical statistics. This avoids the situation where redundant misloaded conditions of the reactor core are caused by exhaustively enumerating multiple misloaded conditions of the reactor core.

[0057] S303 simulates and calculates the fuel consumption of the reactor core under various incorrect core loading conditions to determine the operational safety of the reactor core under incorrect core loading conditions.

[0058] In this embodiment, after obtaining various core misloading conditions, the fuel consumption of the reactor core is simulated and calculated using the physical calculation model of the reactor core for each core misloading condition, and the fuel consumption calculation result is obtained. The operational safety of the reactor core under the condition of incorrect core loading can be determined by judging whether the fuel consumption calculation results corresponding to the various core misloading conditions meet the safety conditions.

[0059] In this embodiment, based on the number of components allowed for misloading of fuel rods in the reactor core, the number of new fuel assemblies replaced in the fuel cycle, and the corresponding misloading conditions for each new fuel assembly, multiple misloading conditions are combined to obtain various misloading conditions for the reactor core. This ensures that the multiple misloading conditions cover all possible misloading scenarios, avoiding an excessive number of conditions due to exhaustive enumeration. Under these multiple misloading conditions, the burnup of the reactor core is simulated to determine its operational safety under misloading conditions. Therefore, a core safety analysis scheme is implemented for fuel rod misloading, effectively constraining the computational cost of core safety analysis while ensuring its comprehensiveness, thus enabling engineering applications of core safety analysis.

[0060] In some embodiments, for multiple new fuel assemblies replaced in the reactor core during the fuel cycle, obtaining the pellet misloading conditions corresponding to each of the multiple new fuel assemblies includes: based on the assembly type corresponding to each of the multiple new fuel assemblies, searching for the pellet misloading conditions corresponding to each of the multiple fuel assemblies from a pool of pellet misloading conditions corresponding to each of the multiple fuel assemblies. Specifically, for each type of fuel assembly, the pellet misloading condition is selected from a pool of candidate pellet misloading conditions based on the degree of influence of the multiple candidate pellet misloading conditions for the fuel assembly.

[0061] In this embodiment, the pellet misloading conditions corresponding to various fuel assemblies can be predetermined. During core safety analysis, by matching the component types of multiple new fuel assemblies with the various fuel assemblies, the pellet misloading conditions corresponding to the multiple new fuel assemblies can be found from the pellet misloading conditions corresponding to the various fuel assemblies. This improves the efficiency of determining the pellet misloading conditions of new fuel assemblies and enhances the efficiency of core operation safety analysis.

[0062] In this embodiment, for each fuel assembly, the pellet misloading condition can be determined in advance using the following method: based on the degree of influence of multiple candidate pellet misloading conditions for the fuel assembly, the pellet misloading condition for that fuel assembly is selected from multiple candidate conditions; the degree of influence of the multiple candidate conditions can refer to the degree of impact of each candidate condition on the safe operation of the reactor core. Therefore, by selecting the pellet misloading condition of the fuel assembly through the degree of influence of multiple candidate conditions, the pellet misloading condition of the new fuel assembly is determined to be more representative, avoiding redundancy in the number of pellet misloading conditions for the new fuel assembly during the core operation safety analysis, and improving the efficiency and accuracy of the core operation safety analysis.

[0063] See Figure 4 , Figure 4 This is a flowchart illustrating the process of determining the misloading condition of fuel assemblies in the core operation safety analysis method under fuel loading error conditions provided in this application embodiment. Figure 4 As shown, the fuel assembly pellet misloading condition is obtained through the following steps: S401, based on the number of fuel rods in the fuel assembly that are allowed to be misloaded, the number of fuel rods in the fuel assembly that are axially partitioned, and the various misloaded fuel rods in the fuel assembly that are axially partitioned, the operating conditions of multiple fuel rods are combined to generate multiple candidate operating conditions for misloaded fuel rods in the fuel assembly.

[0064] Among them, the various pellet misloading conditions of fuel rods with axial partitions in the fuel assembly can be determined based on the number of axial partitions in the fuel rods with axial partitions in the fuel assembly and the threshold number of pellet misloading at the interface of a single axial partition, thereby improving the accuracy and comprehensiveness of the various pellet misloading conditions of fuel rods with axial partitions.

[0065] In this embodiment, the number of fuel rods allowed to be misloaded in the fuel assembly can be obtained from the quality assurance parameters of the fuel manufacturer; the number of fuel rods with axial partitioning in the fuel assembly can be determined based on the assembly type; and the range of the number of fuel rods with misloaded fuel rods in the fuel assembly can be determined based on the number of fuel rods allowed to be misloaded. Based on this range, the number of fuel rods with axial partitioning in the fuel assembly, and various misloaded fuel rod conditions with axial partitioning, the operating conditions of multiple fuel rods are permuted and combined to obtain various misloaded fuel rod conditions for the fuel assembly. In the above permutation and combination process, mathematical permutation and combination methods can be used to determine the various misloaded fuel rod conditions for the fuel assembly.

[0066] In one possible implementation, the upper bound of the range of fuel rods in a fuel assembly that are misloaded with pellets is equal to the number of fuel rods in the fuel assembly that are allowed to be misloaded with pellets, and the lower bound of the range is equal to 1.

[0067] In one possible implementation, the number of various pellet misloading conditions in the fuel assembly is: ; in, This indicates the number of different cartridge misloading conditions in the fuel assembly. This indicates the number of fuel rods in the fuel assembly that are allowed to be misloaded with fuel pellets. This indicates the number of fuel rods in the fuel assembly that are axially partitioned. This indicates the number of various pellet misloading conditions using axially partitioned fuel rods. Furthermore, This indicates the number of multiple pellet misloading conditions using a single fuel rod with axial partitioning; C represents the symbol for permutations and combinations in mathematical statistics.

[0068] It is evident that, under the constraints of the number of fuel rods allowed to be misloaded in the fuel assembly, the number of fuel rods with axial partitioning in the fuel assembly, and the number of various misloaded conditions of fuel rods with axial partitioning, the various possible misloaded conditions of the fuel assembly can be accurately obtained through permutations and combinations in mathematical statistics. This avoids exhaustively listing the misloaded conditions of the fuel assembly, which would lead to redundant misloaded conditions.

[0069] In one possible implementation, multiple misloading conditions of the fuel rod are obtained through the following steps: acquiring the detection accuracy and fuel rod pellet length; determining a threshold for the number of misloading pellets at a single axial partition interface in the fuel rod based on the detection accuracy and fuel rod pellet length; and determining multiple misloading conditions of the fuel rod based on the misloading number threshold and the number of axial partitions in the fuel rod. Thus, by combining the detection accuracy and fuel rod pellet length, the accuracy of the threshold for the number of misloading pellets at a single axial partition interface in the fuel rod is improved. Furthermore, by combining the misloading number threshold with the number of axial partitions in the fuel rod, the accuracy of multiple misloading conditions of the fuel rod is improved, avoiding redundant misloading conditions and preventing omissions of misloading conditions, thus covering possible misloading situations of the fuel rod.

[0070] The detection accuracy of fuel rods can be obtained from the detection parameters of the fuel manufacturer, and the pellet length of fuel rods can be obtained from the attribute information of fuel rods.

[0071] In this implementation, the quotient obtained by dividing the detection accuracy of the fuel rod by the length of the fuel rod pellets can be rounded down to obtain the pellet misloading threshold at a single axial partition interface in the fuel rod. Then, based on the pellet misloading threshold at a single axial partition interface and based on the number of axial partitions in the fuel rod, various pellet misloading conditions of the fuel rod can be determined.

[0072] Based on the detection accuracy of the fuel rod and the length of the fuel rod pellets, the threshold for the number of misloaded pellets at the interface of a single axial section in the fuel rod can be calculated using the following formula: ; in, This represents the threshold for the number of misloaded pellets at the interface of a single axial section in a fuel rod, and indicates the detection accuracy of the fuel rod. Indicates the length of the fuel rod pellets. This indicates the integer division operation.

[0073] In one possible implementation, the number of various pellet misloading conditions of the fuel rod can be determined using the following formula, based on a pellet misloading threshold and the number of axial partitions of the fuel rod: ; in, This indicates the number of different fuel rod pellet misloading conditions. This represents the number of axial partitions in the fuel rod. As can be seen from the formula above, after determining the threshold for the number of misloaded pellets at a single axial partition interface and the number of axial partitions in the fuel rod, the number of various misloaded pellet conditions in the fuel rod can be accurately obtained. Under the constraint of the threshold for the number of misloaded pellets at a single axial partition interface, the number of misloaded pellets at each axial partition interface in the fuel rod can be arranged and combined to determine the various misloaded pellet conditions in the fuel rod.

[0074] For example, Figure 5 An example diagram illustrating a misloading condition of fuel rod pellets provided in an embodiment of this application. Figure 5 As shown, assuming the fuel rod contains two axial partitions (two axial partitions mean one axial partition interface), the threshold for the number of misloaded pellets at a single axial partition interface in the fuel rod is 1 (i.e., =1), under correct loading conditions, type 2 fuel pellets are located above type 1 fuel pellets, and there are 2 type 2 fuel pellets. There are two misloading conditions: in misloading condition 1, one more type 1 fuel pellet is loaded at the axial partition interface, and one less type 2 fuel pellet is loaded at the axial partition interface; in misloading condition 2, one less type 1 fuel pellet is loaded at the axial partition interface, and one more type 2 fuel pellet is loaded at the axial partition interface. Moreover, according to the above formula, in Given that =1 and i equals 2, we can calculate... =2, accurately calculating the number of chip misloading conditions.

[0075] S402, under various candidate conditions of misloading of fuel pellets in the fuel assembly, the fuel rod power of the fuel assembly is simulated and calculated to obtain the fuel rod power distribution corresponding to each candidate condition of misloading of fuel pellets.

[0076] In this embodiment, after obtaining multiple candidate operating conditions for misloaded fuel cells, the power of the fuel rods in the fuel assembly is simulated and calculated using the physical calculation model of the fuel assembly for each candidate operating condition, thereby obtaining the power distribution of the fuel rods corresponding to each of the multiple candidate operating conditions for misloaded fuel cells. Thus, based on the physical calculation model of the fuel assembly, targeted power consumption simulation calculations are performed for each candidate operating condition for misloaded fuel cells, improving the accuracy of the power distribution of the fuel rods corresponding to each of the multiple candidate operating conditions for misloaded fuel cells.

[0077] In one possible implementation, S402 includes: referring to multiple candidate operating conditions of misloaded fuel assemblies, replacing the operating conditions of the fuel rods in a first physical calculation model to obtain multiple second physical calculation models. The first physical calculation model is used to simulate the correct loading condition of the fuel assembly, and the second physical calculation models are used to simulate the candidate operating conditions of misloaded fuel assemblies corresponding to the second physical calculation models. Through the multiple second physical calculation models, the fuel rod power of the fuel assembly is calculated respectively to obtain the fuel rod power distribution corresponding to each of the multiple candidate operating conditions of misloaded fuel assemblies. Therefore, by replacing the operating conditions of the fuel rods based on the first physical calculation model and referring to multiple candidate operating conditions of misloaded fuel assemblies, accurate simulation of fuel rod loading in the fuel assembly under real-world conditions is achieved, improving the calculation accuracy and efficiency of the fuel rod power distribution corresponding to each of the multiple candidate operating conditions of misloaded fuel assemblies.

[0078] The first physical calculation model is obtained by three-dimensional modeling under the correct loading conditions of the fuel assembly. Further, a "one-step" calculation procedure can be used to establish the first physical calculation model. The "one-step" calculation procedure refers to the integrated calculation of resonance, transport, and fuel consumption within the fuel assembly; no specific limitations are imposed on the "one-step" calculation procedure here.

[0079] In the first physical calculation model, the operating condition replacement of the fuel rods can be achieved by referring to the candidate operating condition of misloading fuel pellets and modifying the information such as the fuel pellet arrangement and fuel pellet type of the fuel rods in the first physical calculation model.

[0080] In this implementation, for each candidate pellet misloading condition of the fuel assembly, the fuel rod is replaced in the first physical calculation model with reference to the candidate pellet misloading condition to obtain the second physical calculation model corresponding to the candidate pellet misloading condition. In this way, the second physical calculation models corresponding to the multiple candidate pellet misloading conditions of the fuel assembly can be obtained, that is, multiple second physical calculation models are obtained. Then, the fuel rod power of the fuel assembly is calculated through the multiple second physical calculation models to obtain the fuel rod power distribution corresponding to the multiple candidate pellet misloading conditions of the fuel assembly.

[0081] For example, in each of the second physical calculation models, total internal reflection can be used as a boundary condition to calculate the fuel rod power of the fuel assembly.

[0082] S403, based on the fuel rod power distribution corresponding to the various candidate conditions for misloading of fuel pellets in the fuel assembly, select the fuel assembly's pellet misloading condition from among the various candidate conditions for misloading of fuel pellets.

[0083] In this embodiment, the impact of various candidate pebble misloading conditions on the safe operation of the reactor core can be determined based on the fuel rod power distribution corresponding to each candidate pebble misloading condition. The candidate pebble misloading condition with the greatest impact can be identified as the pebble misloading condition of the fuel assembly.

[0084] In one possible implementation, S403 includes: comparing the fuel rod power distribution corresponding to each of the various candidate conditions for misloading fuel assemblies with the fuel rod power distribution of the fuel assembly under the correct loading condition, to obtain the power distribution deviations corresponding to each of the various candidate conditions for misloading fuel assemblies; and selecting a misloading condition for the fuel assembly from the various candidate conditions for misloading fuel assemblies based on the power distribution deviations corresponding to each of the various candidate conditions for misloading fuel assemblies. Thus, by using the power distribution deviations corresponding to each of the various candidate conditions for misloading fuel assemblies, the impact of the various candidate conditions for misloading fuel assemblies on the safe operation of the reactor core is accurately reflected, improving the accuracy of selecting the misloading condition for the fuel assembly.

[0085] The fuel rod power distribution of the fuel assembly under correct loading conditions is calculated using a first physical calculation model, which simulates the correct loading conditions of the fuel assembly. Therefore, the accuracy of the calculated fuel rod power distribution under correct loading conditions is improved through the first physical model. The first physical model can be referred to the description in the foregoing embodiments and will not be repeated here.

[0086] For example, in the first physical calculation model, total internal reflection can be used as a boundary condition to calculate the fuel rod power of the fuel assembly.

[0087] In one possible implementation, based on the power distribution deviations corresponding to various candidate conditions for fuel assembly pellet misloading, the candidate condition with the largest power distribution deviation is identified as the actual fuel assembly pellet misloading condition. Thus, by utilizing the characteristic that the candidate condition with the largest power distribution deviation has the greatest impact on core safety operation, selecting it as the actual fuel assembly pellet misloading condition ensures representativeness of the fuel assembly pellet misloading conditions in core safety analysis, improving the accuracy of core safety analysis, and avoiding excessive computational load and cost due to an excessive number of fuel assembly pellet misloading conditions.

[0088] For example, Figure 6 This is an example diagram of a two-dimensional radial arrangement of a fuel assembly provided in an embodiment of this application. Figure 6 As shown, the fuel assembly may include instrument tubes, guide tubes, axially partitioned fuel rods, and non-axially partitioned fuel rods. When calculating the fuel rod power distribution corresponding to various candidate conditions of misloading fuel pellets, the fuel rod power distribution according to this two-dimensional radial arrangement can be calculated.

[0089] In this embodiment, under the constraints of the number of fuel rods allowed to be misloaded and the number of fuel rods with axial partitioning in the fuel assembly, multiple fuel rods in the fuel assembly are combined with various misloaded operating conditions using axially partitioned fuel rods to generate multiple candidate operating conditions for misloaded fuel rods. This ensures that these multiple misloaded operating conditions can cover various possible misloaded fuel rod situations in the fuel assembly, while avoiding redundant misloaded operating conditions and reducing the subsequent power distribution calculation workload and cost. Under the multiple candidate operating conditions for misloaded fuel rods in the fuel assembly, the fuel... The fuel rod power is simulated and calculated to obtain the fuel rod power distribution corresponding to various candidate conditions for misloading of fuel pellets, thereby improving the accuracy of the fuel rod power distribution corresponding to various candidate conditions for misloading of fuel pellets. Based on the fuel rod power distribution corresponding to various candidate conditions for misloading of fuel pellets, the fuel assembly's fuel pellet misloading condition is selected from these conditions to ensure that the fuel assembly has representative fuel pellet misloading conditions participating in the condition combination in the core operation safety analysis. This avoids excessive calculation volume and cost in the core safety analysis due to an excessive number of fuel assembly fuel pellet misloading conditions, thereby improving the accuracy of the core operation safety analysis.

[0090] See Figure 7 , Figure 7 A flowchart illustrating the core operation safety analysis method under fuel loading error conditions provided in this application embodiment. Figure 2 .like Figure 7 As shown, the core operation safety analysis method under fuel loading error conditions includes, but is not limited to, the following steps: S701, for multiple new fuel assemblies replaced in the fuel cycle scheme of the reactor core, obtain the chip misloading conditions corresponding to each of the multiple new fuel assemblies.

[0091] S702, based on the number of components in the reactor core that are allowed to be misloaded with fuel pellets, the number of multiple new fuel assemblies, and the fuel pellet misloading conditions corresponding to the multiple new fuel assemblies, the operating conditions of the multiple new fuel assemblies are combined to obtain multiple fuel pellet misloading conditions of the reactor core.

[0092] The implementation principles and technical effects of S701~S702 can be referred to the aforementioned embodiments, and will not be repeated here.

[0093] S703 simulates and calculates the core burnup under various core misloading conditions, obtaining the nuclear enthalpy rise factor values ​​corresponding to each core misloading condition.

[0094] In this embodiment, the nuclear enthalpy rise factor is a core parameter of the reactor thermal safety criteria. In various core misloading conditions, the burnup during the fuel cycle of the core can be simulated and calculated using the core's physical calculation model for each core misloading condition, thereby obtaining the nuclear enthalpy rise factor corresponding to each core misloading condition.

[0095] For each core misloading condition, the nuclear enthalpy rise factor value for the core misloading condition refers to the maximum value of the nuclear enthalpy rise factor of the core during the fuel cycle under the core misloading condition.

[0096] In one possible implementation, S703 includes: referencing various core misloading conditions, replacing the operating conditions of new fuel assemblies in a third physics calculation model to obtain multiple fourth physics calculation models. The third physics calculation model is used to simulate the correct core loading condition, and the fourth physics calculation models are used to simulate the core misloading conditions corresponding to the fourth physics calculation models. The burnup of the core is calculated using the multiple fourth physics calculation models to obtain the nuclear enthalpy rise factor values ​​corresponding to the various core misloading conditions. Therefore, by replacing the operating conditions of new fuel assemblies with those of new fuel assemblies based on the third physics calculation model and referring to various core misloading conditions, accurate simulation of core replacement with new fuel assemblies under real-world conditions is achieved, improving the accuracy and efficiency of calculating the nuclear enthalpy rise factor values ​​corresponding to the various core misloading conditions.

[0097] The third physics calculation model is obtained by three-dimensional modeling under the correct core loading conditions. The third and fourth physics calculation models can be used to calculate the fuel cycle burnup of the core and obtain the nuclear enthalpy rise factor value of the core under the corresponding operating conditions.

[0098] In this implementation, for each of the various misloading conditions of the reactor core, the new fuel assembly is replaced in the third physical calculation model to obtain the fourth physical calculation model corresponding to the misloading condition. In this way, the fourth physical calculation models corresponding to the multiple misloading conditions of the reactor core can be obtained, that is, multiple fourth physical calculation models are obtained. Then, through the multiple fourth physical calculation models, the burnup in the fuel cycle process of the reactor core can be calculated to obtain the nuclear enthalpy rise factor value corresponding to the various misloading conditions of the reactor core.

[0099] S704 determines the operational safety of the reactor core under conditions of incorrect core loading based on the nuclear enthalpy rise factor values ​​corresponding to various core misloading scenarios.

[0100] In this embodiment, it can be determined whether the nuclear enthalpy rise factor values ​​corresponding to various core misloading conditions meet the safety limits of the nuclear enthalpy rise factor. If the nuclear enthalpy rise factor values ​​corresponding to various core misloading conditions all meet the safety limits of the nuclear enthalpy rise factor, it can be determined that the core can operate safely under core loading errors; otherwise, it can be determined that the core faces operational risks under core loading errors. If the nuclear enthalpy rise factor value of at least one core misloading condition does not meet the safety limits of the nuclear enthalpy rise factor, this at least one core misloading condition can be recorded as a core misloading condition that does not meet the requirements for safe core operation.

[0101] In one possible implementation, S704 includes: determining the operational safety of the reactor core under incorrect core loading conditions by comparing the nuclear enthalpy rise factor values ​​corresponding to various core misloading conditions with the nuclear enthalpy rise factor value of the reactor core under correct loading conditions. Thus, by using the nuclear enthalpy rise factor value of the reactor core under correct loading conditions as a benchmark, the accuracy of analyzing the operational safety of the reactor core under incorrect core loading conditions is improved.

[0102] The nuclear enthalpy rise factor value of the reactor core under correct loading conditions is calculated using a third physics calculation model, which simulates the correct loading conditions of the reactor core. Therefore, the accuracy of the calculated nuclear enthalpy rise factor value under correct loading conditions is improved through the third physics model. The third physics model can be referred to the description in the foregoing embodiments and will not be repeated here.

[0103] The nuclear enthalpy rise factor value of the reactor core under correct loading conditions refers to the maximum value of the nuclear enthalpy rise factor of the reactor core during the fuel cycle under correct loading conditions.

[0104] In this implementation, the nuclear enthalpy rise factor values ​​corresponding to various incorrect core loading conditions are compared with the nuclear enthalpy rise factor values ​​under correct core loading conditions to obtain the nuclear enthalpy rise factor deviation values ​​corresponding to various incorrect core loading conditions. The operational safety of the core under incorrect core loading conditions can be determined by judging whether the nuclear enthalpy rise factor deviation values ​​corresponding to various incorrect core loading conditions meet the safe variation range of the nuclear enthalpy rise factor.

[0105] See Figure 8 , Figure 8 A schematic diagram of the core operation safety analysis device under fuel loading error conditions provided in this application embodiment. Figure 8 As shown, the reactor core operation safety analysis device under fuel loading error conditions includes, but is not limited to, the following modules: The component condition acquisition unit 801 is used to acquire the core misloading condition corresponding to each of the multiple new fuel assemblies replaced in the fuel cycle scheme of the reactor core. The component condition combination unit 802 is used to combine the conditions of multiple new fuel assemblies according to the number of components in the core that are allowed to be misloaded, the number of multiple new fuel assemblies, and the misloaded conditions corresponding to the multiple new fuel assemblies, so as to obtain multiple misloaded conditions of the core. The core safety determination unit 803 is used to simulate and calculate the core burnup under various core misloading conditions, and determine the core's operational safety under core misloading conditions.

[0106] In some embodiments, the component condition acquisition unit 801 is specifically used to: find the pellet misloading conditions corresponding to the multiple new fuel components from the pellet misloading conditions corresponding to the multiple fuel components according to the component types corresponding to the multiple new fuel components respectively; wherein, for various fuel components, the pellet misloading conditions of the fuel components are selected from the multiple pellet misloading candidate conditions according to the influence degree of the multiple pellet misloading candidate conditions of the fuel components.

[0107] In some embodiments, the pellet misloading condition of the fuel assembly is obtained through the following steps: Based on the number of fuel rods allowed to be misloaded in the fuel assembly, the number of fuel rods in the fuel assembly with axial partitioning, and various pellet misloading conditions of the fuel rods in the fuel assembly with axial partitioning, multiple fuel rods are combined to generate multiple candidate pellet misloading conditions; under the multiple candidate pellet misloading conditions, the fuel rod power of the fuel assembly is simulated and calculated to obtain the fuel rod power distribution corresponding to each of the multiple candidate pellet misloading conditions; based on the fuel rod power distribution corresponding to each of the multiple candidate pellet misloading conditions, the pellet misloading condition of the fuel assembly is selected from the multiple candidate pellet misloading conditions.

[0108] In some embodiments, under multiple candidate conditions for incorrect pellet loading, the fuel rod power of the fuel assembly is simulated and calculated to obtain the fuel rod power distribution corresponding to each candidate condition for incorrect pellet loading. This includes: referring to multiple candidate conditions for incorrect pellet loading, replacing the fuel rod condition in a first physical calculation model to obtain multiple second physical calculation models. The first physical calculation model is used to simulate the correct loading condition of the fuel assembly, and the second physical calculation models are used to simulate the candidate conditions for incorrect pellet loading corresponding to the second physical calculation models. The fuel rod power of the fuel assembly is calculated using the multiple second physical calculation models to obtain the fuel rod power distribution corresponding to each candidate condition for incorrect pellet loading.

[0109] In some embodiments, selecting a fuel assembly's misloading condition from multiple candidate fuel rod power distributions for misloading fuel rods includes: comparing the fuel rod power distributions corresponding to the multiple candidate fuel rod misloading conditions with the fuel rod power distribution of the fuel assembly under the correct loading condition to obtain the power distribution deviations corresponding to the multiple candidate fuel rod misloading conditions; and selecting a fuel assembly's misloading condition from the multiple candidate fuel rod misloading conditions based on the power distribution deviations corresponding to the multiple candidate fuel rod misloading conditions. The fuel rod power distribution of the fuel assembly under the correct loading condition is calculated using a first physical calculation model, which is used to simulate the correct loading condition of the fuel assembly.

[0110] In some embodiments, the various pellet misloading conditions of the fuel rod are obtained through the following steps: obtaining the detection accuracy and pellet length of the fuel rod; determining a pellet misloading number threshold at a single axial partition interface in the fuel rod based on the detection accuracy and pellet length; and determining various pellet misloading conditions of the fuel rod based on the pellet misloading number threshold and the number of axial partitions of the fuel rod.

[0111] In some embodiments, the core safety determination unit 803 is specifically used to: simulate and calculate the burnup of the core for various core misloading conditions, and obtain the nuclear enthalpy rise factor value corresponding to each of the various core misloading conditions; and determine the operational safety of the core under the condition of incorrect core loading based on the nuclear enthalpy rise factor value corresponding to each of the various core misloading conditions.

[0112] In some embodiments, the core safety determination unit 803 is specifically used to: refer to various core misloading conditions of the core, replace the conditions of the new fuel assembly in the third physical calculation model to obtain multiple fourth physical calculation models, the third physical calculation model is used to simulate the correct loading condition of the core, and the fourth physical calculation model is used to simulate the core misloading condition corresponding to the fourth physical calculation model; and calculate the core burnup through multiple fourth physical calculation models to obtain the nuclear enthalpy rise factor values ​​corresponding to the various core misloading conditions of the core.

[0113] In some embodiments, the core safety determination unit 803 is specifically used to: determine the operational safety of the core under incorrect core loading conditions by comparing the nuclear enthalpy rise factor values ​​corresponding to various incorrect core loading conditions with the nuclear enthalpy rise factor value of the core under correct loading conditions; wherein, the nuclear enthalpy rise factor value of the core under correct loading conditions is calculated by a third physical calculation model, which is used to simulate the correct core loading conditions.

[0114] It should be noted that the various embodiments described in this application can be combined with each other or implemented individually without conflict, and this application does not limit this.

[0115] It should be noted that this embodiment is an embodiment corresponding to the above method embodiment. Therefore, the relevant descriptions in the above method embodiment can be referred to, and the same beneficial effects can be achieved. To avoid repetition, further details will not be provided here.

[0116] This application also provides an electronic device, such as... Figure 9 As shown, the electronic device includes: one or more processors 910; The memory 920 stores one or more programs that, when executed by one or more processors 910, enable the one or more processors 910 to implement the core operation safety analysis method under fuel loading error conditions described in any of the preceding embodiments.

[0117] The memory 920, as a non-transitory network system, can be used to store non-transitory software programs and non-transitory computer-executable programs. Furthermore, the memory 920 may include high-speed random access memory, and may also include non-transitory memory, such as at least one disk storage device, flash memory device, or other non-transitory solid-state storage device. In some embodiments, the memory 920 may optionally include remotely located memories 920 relative to the processor 910, which can be connected to the processor 910 via a network. Examples of such networks include, but are not limited to, the Internet, intranets, local area networks, mobile communication networks, and combinations thereof.

[0118] The memory 920 can be implemented as a read-only memory (ROM), static storage device, dynamic storage device, or random access memory (RAM). The memory 920 can store the operating system and other applications. When the technical solutions provided in the embodiments of this specification are implemented through software or firmware, the relevant program code is stored in the memory 920 and called by the processor 910 to execute the methods of the embodiments of this application.

[0119] The processor 910 can be implemented using a general-purpose CPU (Central Processing Unit), microprocessor, application-specific integrated circuit (ASIC), or one or more integrated circuits, and is used to execute relevant programs to implement the technical solutions provided in the embodiments of this application.

[0120] In one embodiment, the electronic device further includes: Input / output interfaces are used to implement information input and output; The communication interface is used to enable communication and interaction between this device and other devices. Communication can be achieved through wired means (such as USB, Ethernet cable, etc.) or wireless means (such as mobile network, WIFI, Bluetooth, etc.). The bus transmits information between various components of the device, such as the processor 910, memory 920, input / output interfaces, and communication interfaces. The processor 910, memory 920, input / output interface, and communication interface can communicate with each other within the device via a bus.

[0121] One embodiment of this application also provides a computer-readable storage medium storing computer-executable instructions for performing a core operation safety analysis method under fuel loading error conditions as provided in any embodiment of this application.

[0122] An embodiment of this application also provides a computer program product, including a computer program or computer instructions stored in a computer-readable storage medium. A processor of a computer device reads the computer program or computer instructions from the computer-readable storage medium and executes the computer program or computer instructions, causing the computer device to perform a core operation safety analysis method under fuel loading error conditions as provided in any embodiment of this application.

[0123] The system architecture and application scenarios described in the embodiments of this application are for the purpose of more clearly illustrating the technical solutions of the embodiments of this application, and do not constitute a limitation on the technical solutions provided in the embodiments of this application. Those skilled in the art will know that as the system architecture evolves and new application scenarios emerge, the technical solutions provided in the embodiments of this application are also applicable to similar technical problems.

[0124] Those skilled in the art will understand that all or some of the steps in the methods disclosed above, as well as the functional modules / units in the systems and devices, can be implemented as software, firmware, hardware, or suitable combinations thereof.

[0125] In hardware implementations, the division between functional modules / units mentioned in the above description does not necessarily correspond to the division of physical components; for example, a physical component may have multiple functions, or a function or step may be performed collaboratively by several physical components. Some or all physical components may be implemented as software executed by a processor, such as a central processing unit, digital signal processor, or microprocessor, or as hardware, or as an integrated circuit, such as an application-specific integrated circuit. Such software may be distributed on a computer-readable medium, which may include computer storage media (or non-transitory media) and communication media (or transient media). As is known to those skilled in the art, the term computer storage media includes volatile and non-volatile, removable and non-removable media implemented in any method or technology for storing information (such as computer-readable instructions, data structures, program modules, or other data). Computer storage media includes, but is not limited to, RAM, ROM, EEPROM, flash memory or other memory technologies, CD-ROM, digital versatile disc (DVD) or other optical disc storage, magnetic cartridges, magnetic tape, disk storage or other magnetic storage devices, or any other medium that can be used to store desired information and is accessible to a computer. Furthermore, as is known to those skilled in the art, communication media typically contain computer-readable instructions, data structures, program modules, or other data in modulated data signals such as carrier waves or other transmission mechanisms, and may include any information delivery medium.

[0126] The terms “component,” “module,” “system,” etc., used in this specification are used to refer to computer-related entities, hardware, firmware, combinations of hardware and software, software, or software in execution. For example, a component can be, but is not limited to, a process running on a processor, a processor, an object, an executable file, an execution thread, a program, or a computer. As illustrated, applications running on computing devices and computing devices can both be components. One or more components may reside in a process or execution thread, and components may be located on a single computer or distributed across two or more computers. Furthermore, these components can be executed from various computer-readable media on which various data structures are stored.

[0127] The above description, with reference to the accompanying drawings, illustrates one embodiment of this application, but does not limit the scope of this application. Any modifications, equivalent substitutions, and improvements made by those skilled in the art without departing from the scope and spirit of this application shall be within the scope of this application.

Claims

1. A method for core operation safety analysis under fuel loading error conditions, characterized in that, include: For multiple new fuel assemblies replaced in the fuel cycle scheme of the reactor core, obtain the core misloading conditions corresponding to each of the multiple new fuel assemblies; Based on the number of components in the reactor core that are allowed to be misloaded, the number of multiple new fuel assemblies, and the misloaded operating conditions corresponding to each of the multiple new fuel assemblies, the operating conditions of the multiple new fuel assemblies are combined to obtain multiple misloaded operating conditions of the reactor core. Under various incorrect core loading conditions, the burnup of the reactor core is simulated and calculated to determine the operational safety of the reactor core under incorrect core loading conditions.

2. The method according to claim 1, characterized in that, The method for obtaining the core misloading conditions corresponding to multiple new fuel assemblies replaced in the fuel cycle scheme includes: Based on the component types corresponding to the various new fuel assemblies, the various pellet misloading conditions corresponding to the various fuel assemblies are found from the pellet misloading conditions corresponding to the various fuel assemblies. Specifically, for each of the fuel assemblies, the pellet misloading condition of the fuel assembly is selected from multiple pellet misloading candidate conditions based on the degree of influence of the multiple pellet misloading candidate conditions of the fuel assembly.

3. The method according to claim 2, characterized in that, The fuel assembly pellet misloading condition was obtained through the following steps: Based on the number of fuel rods in the fuel assembly that are allowed to be misloaded, the number of fuel rods in the fuel assembly that are axially partitioned, and the various misloaded conditions of the fuel rods in the fuel assembly that are axially partitioned, the operating conditions of multiple fuel rods are combined to generate multiple candidate operating conditions for misloaded fuel rods. Under various candidate conditions of pellet misloading, the fuel rod power of the fuel assembly is simulated and calculated to obtain the fuel rod power distribution corresponding to each of the various candidate conditions of pellet misloading. Based on the fuel rod power distribution corresponding to the various candidate conditions for misloading of fuel pellets, the fuel assembly's misloading condition is selected from the various candidate conditions for misloading of fuel pellets.

4. The method according to claim 3, characterized in that, Under various candidate conditions of pellet misloading, the fuel rod power of the fuel assembly is simulated and calculated to obtain the fuel rod power distribution corresponding to each of the candidate conditions of pellet misloading, including: Referring to various candidate conditions for incorrect pellet loading, the fuel rods are replaced in the first physical calculation model to obtain multiple second physical calculation models. The first physical calculation model is used to simulate the correct loading condition of the fuel assembly, and the second physical calculation model is used to simulate the candidate conditions for incorrect pellet loading corresponding to the second physical calculation model. By using multiple second physical calculation models, the fuel rod power of the fuel assembly is calculated respectively, and the fuel rod power distribution corresponding to various candidate conditions of misloading of the pellets is obtained.

5. The method according to claim 3, characterized in that, The step of selecting the pellet misloading condition of the fuel assembly from the multiple candidate pellet misloading conditions based on the fuel rod power distribution corresponding to each of the multiple candidate pellet misloading conditions includes: The power distribution of fuel rods corresponding to various candidate conditions of incorrect fuel loading is compared with the power distribution of fuel rods under the correct loading condition of the fuel assembly to obtain the power distribution deviations corresponding to various candidate conditions of incorrect fuel loading. Based on the power distribution deviations corresponding to the various candidate conditions for incorrect pellet loading, the pellet misloading condition of the fuel assembly is selected from the various candidate conditions for incorrect pellet loading. The fuel rod power distribution of the fuel assembly under correct loading conditions is calculated by a first physical calculation model, which is used to simulate the correct loading conditions of the fuel assembly.

6. The method according to claim 3, characterized in that, The various pellet misloading conditions of the fuel rods were obtained through the following steps: The detection accuracy of the fuel rod and the core length of the fuel rod are obtained; Based on the detection accuracy and the pellet length, determine the threshold for the number of misloaded pellets at a single axial partition interface in the fuel rod; Based on the threshold number of misloaded pellets and the number of axial partitions of the fuel rod, various misloaded pellet conditions of the fuel rod are determined.

7. The method according to any one of claims 1 to 6, characterized in that, The process of simulating and calculating the burnup of the reactor core under various misloading conditions to determine the operational safety of the reactor core under these conditions includes: For various core misloading conditions of the reactor core, the burnup of the reactor core is simulated and calculated to obtain the nuclear enthalpy rise factor values ​​corresponding to the various core misloading conditions of the reactor core. Based on the nuclear enthalpy rise factor values ​​corresponding to various core misloading conditions of the reactor core, the operational safety of the reactor core under core loading error conditions is determined.

8. The method according to claim 7, characterized in that, The method involves simulating and calculating the burnup of the reactor core under various misloading conditions, respectively, to obtain the nuclear enthalpy rise factor values ​​corresponding to each misloading condition, including: Referring to various misloading conditions of the reactor core, the new fuel assembly is replaced in the third physical calculation model to obtain multiple fourth physical calculation models. The third physical calculation model is used to simulate the correct loading condition of the reactor core, and the fourth physical calculation model is used to simulate the misloading condition of the corresponding fourth physical calculation model. The burnup of the reactor core is calculated using multiple fourth physics calculation models to obtain the nuclear enthalpy rise factor values ​​corresponding to various core misloading conditions.

9. The method according to claim 7, characterized in that, Based on the nuclear enthalpy rise factor values ​​corresponding to various core misloading conditions of the reactor core, the operational safety of the reactor core under core misloading conditions is determined, including: By comparing the nuclear enthalpy rise factor values ​​corresponding to various misloading conditions of the reactor core with the nuclear enthalpy rise factor value of the reactor core under the correct loading condition, the operational safety of the reactor core under the condition of misloading of core blocks is determined. The nuclear enthalpy rise factor value of the reactor core under correct loading conditions is calculated by a third physics calculation model, which is used to simulate the correct loading conditions of the reactor core.

10. A reactor core operation safety analysis device for fuel loading errors, characterized in that, include: The component condition acquisition unit is used to acquire the core misloading condition corresponding to each of the multiple new fuel assemblies replaced in the fuel cycle scheme of the reactor core. The component condition combination unit is used to combine the conditions of multiple new fuel assemblies according to the number of components in the core that are allowed to have misloaded core, the number of multiple new fuel assemblies, and the misloaded core conditions corresponding to the multiple new fuel assemblies, so as to obtain multiple misloaded core conditions of the core. The core safety determination unit is used to simulate and calculate the burnup of the core under various incorrect core loading conditions, and to determine the operational safety of the core under incorrect core loading conditions.

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