Fuel safety parameter determination method, device and equipment

Abstract

The invention relates to the technical field of nuclear reaction, in particular to a fuel safety parameter determination method, device and equipment, and the method comprises the steps: obtaining working condition parameters of characteristic fuel rods of all fuel assemblies of a nuclear power unit in an operation state, and executing temperature calculation processing in combination with fuel design parameters of the characteristic fuel rods; a temperature safety parameter representative of the thermal state and thermal load profile of each fuel assembly is obtained. Therefore, the fuel assembly of the nuclear power unit is used as a data acquisition unit, all the fuel rods in the fuel assembly are represented by the characteristic fuel rods, the data size needed by safety parameter calculation is reduced, the fuel safety parameter determination efficiency is improved, the operation condition parameters are combined with the structural characteristics of the fuel assembly, and the fuel safety parameter calculation efficiency is improved. A data basis is provided for calculation of the fuel safety parameters, and the calculation accuracy of the fuel safety parameters is improved.

Description

Technical Field

[0001] The present application relates to the field of nuclear reaction technology, and in particular to a method, device and equipment for determining fuel safety parameters. Background Art

[0002] At present, the frequency of fuel failure in nuclear power units is on the rise, and nuclear power units are generally in high-load operation. Fuel failure is affected by multiple factors, such as material aging and fatigue caused by long-term service of fuel, mechanical increase in thermal load caused by high-load operation of units, and complexity of reactor operating conditions. These factors aggravate the thermal expansion, mechanical allergy and radiation damage of the fuel, which may lead to cladding rupture, increased pellet-cladding mechanical interaction (PCI), deformation or expansion of fuel pellets, and other problems, thus causing fuel failure.

[0003] In the related technology, nuclear power units are equipped with real-time online monitoring systems for the core, which can obtain real-time core operating data. However, the number of fuel rods in the reactor is huge, and as the reactor operates, the historical operating information of each fuel rod is gradually accumulated. The reading, storage and calculation of huge historical data will consume more computing resources and computing time, and may even take several days to complete, resulting in low efficiency in obtaining fuel safety parameters and unable to meet the actual needs of real-time monitoring of the fuel safety status. Summary of the invention

[0004] In view of the above problems, the present invention provides a method, device and equipment for determining fuel safety parameters, so as to improve the efficiency and accuracy of determining fuel safety parameters.

[0005] In a first aspect, the present application provides a method for determining a fuel safety parameter, the method comprising:

[0006] Acquiring an operating condition parameter of at least one fuel assembly, wherein the operating condition parameter represents: an operating condition parameter of a characteristic fuel rod of the corresponding fuel assembly in an operating state;

[0007] Based on the operating condition parameters and fuel design parameters of each fuel assembly, temperature calculation processing is performed to obtain the temperature safety parameters of each fuel assembly, wherein the temperature safety parameters characterize the thermal state and heat load distribution of the fuel assembly.

[0008] In a second aspect, the present application provides a fuel safety parameter determination device, the device comprising:

[0009] A first acquisition unit is used to acquire an operating condition parameter of at least one fuel assembly, wherein the operating condition parameter represents: an operating condition parameter of a characteristic fuel rod of a corresponding fuel assembly under an operating state, wherein the characteristic fuel rod is a specific fuel rod reflecting the performance of the entire fuel assembly;

[0010] The temperature calculation unit is used to perform temperature calculation processing based on the operating condition parameters and fuel design parameters of each fuel assembly to obtain the temperature safety parameters of each fuel assembly, wherein the temperature safety parameters characterize the thermal state and heat load distribution of the fuel assembly.

[0011] In a third aspect, the present application provides a computer device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein when the processor executes the computer program, any one of the fuel safety parameter determination methods described in the first aspect is implemented.

[0012] In a fourth aspect, the present application provides a computer storage medium, wherein the computer-readable storage medium stores computer program instructions, and the computer program instructions are executed by a processor to perform any one of the fuel safety parameter determination methods described in the first aspect.

[0013] In a fifth aspect, an embodiment of the present application provides a computer program product, comprising computer program instructions, which, when executed by a processor, implement any one of the fuel safety parameter determination methods in the first aspect.

[0014] The beneficial effects of the present invention are as follows:

[0015] The embodiment of the present application provides a method for determining fuel safety parameters, which obtains the temperature safety parameters representing the thermal state and heat load distribution of each fuel assembly by acquiring the operating parameters of the characteristic fuel rods of each fuel assembly of the nuclear power unit in real time under the operating state, and combining the fuel design parameters, performing temperature calculation processing. In this way, the fuel assembly of the nuclear power unit is used as the data acquisition unit, and the characteristic fuel rod is used to represent all the fuel rods in the fuel assembly, which reduces the amount of data required for the calculation of the safety parameters and improves the efficiency of obtaining the fuel safety parameters. In addition, the embodiment of the present application also combines the operating parameters with the structural characteristics of the fuel assembly to provide an accurate data basis for the calculation of the fuel safety parameters, so as to improve the calculation accuracy of the fuel safety parameters. BRIEF DESCRIPTION OF THE DRAWINGS

[0016] In order to more clearly illustrate the technical solutions in the embodiments of the present application or the related technologies, the drawings required for use in the embodiments or the related technical descriptions are briefly introduced below. Obviously, the drawings described below are only the embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on the provided drawings without paying any creative work.

[0017] Figure 1 A flowchart of a method for determining fuel safety parameters provided in an embodiment of the present application;

[0018] Figure 2A schematic flow chart of another method for determining fuel safety parameters provided in an embodiment of the present application;

[0019] Figure 3 A schematic diagram of a fuel safety parameter calculation process provided in an embodiment of the present application;

[0020] Figure 4 A schematic diagram of the structure of a fuel safety parameter determination device provided in an embodiment of the present application;

[0021] Figure 5 A schematic diagram of the structure of a computer device provided in an embodiment of the present application. DETAILED DESCRIPTION

[0022] In order to make the purpose, technical scheme and advantages of the present application clearer, the technical scheme in the embodiment of the present application will be clearly and completely described below in conjunction with the drawings in the embodiment of the present application. Obviously, the described embodiment is only a part of the embodiment of the present application, rather than all the embodiments. Based on the embodiments in the present application, all other embodiments obtained by ordinary technicians in the field without making creative work are within the scope of protection of the present application. In the absence of conflict, the embodiments in the present application and the features in the embodiments can be arbitrarily combined with each other. In addition, although the logical order is shown in the flow chart, in some cases, the steps shown or described can be performed in an order different from that here.

[0023] The terms "first" and "second" in the specification and claims of the present application and the above-mentioned drawings are used to distinguish different objects, rather than to describe a specific order. In addition, the term "comprising" and any of their variations are intended to cover non-exclusive protection. For example, a process, method, system, product or device comprising a series of steps or units is not limited to the listed steps or units, but optionally also includes steps or units that are not listed, or optionally also includes other steps or units inherent to these processes, methods, products or devices. "Multiple" in the present application can mean at least two, for example, can be two, three or more, and the embodiments of the present application are not limited.

[0024] The term "and / or" in the embodiments of the present application is only a description of the association relationship of the associated objects, indicating that there can be three relationships. For example, A and / or B can represent: A exists alone, A and B exist at the same time, and B exists alone. In addition, the character " / " in this article generally indicates that the associated objects before and after are in an "or" relationship.

[0025] It is understandable that in the following specific implementations of the present application, data related to nuclear reactors, nuclear power plant units, etc. are involved. When the various embodiments of the present application are applied to specific products or technologies, relevant licenses or consents need to be obtained, and the collection, use and processing of relevant data need to comply with relevant laws, regulations and standards of relevant countries and regions. For example, it can be implemented by recruiting relevant volunteers and signing relevant agreements for volunteer authorization data, and then the data of these volunteers can be used for implementation; or, by implementing within the scope of the authorized organization, the following implementation methods are implemented by using the data of members within the organization to manage data; or, the relevant data used in the specific implementation are all simulated data, such as simulated data generated in a virtual scene.

[0026] The following is a brief introduction to the design concept of the embodiments of the present application.

[0027] At present, the frequency of fuel failure in nuclear power units is on the rise, and nuclear power units are generally in high-load operation. Fuel failure is affected by multiple factors, such as long-term occupancy of fuel causing material aging and fatigue, high-load operation of units leading to increased thermal load machinery, and complex reactor operating conditions. These factors aggravate the thermal expansion and radiation damage of the fuel, leading to cladding rupture, increased pellet-cladding mechanical interaction (PCI), deformation or expansion of fuel pellets, and other problems, thereby causing fuel failure. Therefore, with the improvement of safety requirements for nuclear power plants, ensuring the fuel safety of nuclear power units has become a key challenge.

[0028] In the related technology, the nuclear power unit is equipped with a real-time online monitoring system for the core, which can obtain the core operating data in real time, such as the power distribution of the fuel rods, the coolant temperature and other operating parameters. However, the number of fuel rods in the reactor is huge, and the relevant information of each fuel rod is obtained and calculated. As the reactor runs, the historical power information and historical coolant condition information of each fuel rod are gradually accumulated. The storage and reading of the huge amount of historical fuel rod data will consume huge computing resources. The time required for calculating these huge data is also increasing dramatically. It may take hours or days to complete the calculation, resulting in low efficiency in obtaining fuel safety parameters, and it is impossible to meet the demand for real-time monitoring of the fuel safety status. In addition, fuel safety parameters that directly reflect the fuel failure risk of nuclear power units, such as fuel temperature and fuel cladding stress, are difficult to obtain accurately and in a timely manner. For example, the fuel temperature can be obtained by installing thermocouples in the fuel rods, but for commercial nuclear power units, the number of fuel rods in the core is huge, and there are no pipes reserved for installing thermocouples. This method is not only cumbersome to operate, but also has a low accuracy rate in the obtained fuel temperature. Fuel safety parameters such as fuel cladding stress and strain cannot be directly obtained by installing detectors in the reactor, resulting in nuclear power units still facing high uncertainty and fuel safety risks in the event of sudden operating conditions.

[0029] In view of the above problems, an embodiment of the present application provides a method for determining fuel safety parameters, which obtains the operating parameters of the characteristic fuel rods of each fuel assembly of a nuclear power unit under the operating state, and combines its fuel design parameters to perform temperature calculation processing to obtain temperature safety parameters representing the thermal state and heat load distribution of each fuel assembly. In this way, the fuel assembly of the nuclear power unit is used as the data acquisition unit, and the characteristic fuel rod is used to represent all the fuel rods in the fuel assembly, which reduces the amount of data required for the safety parameter calculation and improves the efficiency of obtaining fuel safety parameters. The temperature safety parameter can provide a quantitative assessment method for the risk of fuel failure, and can dynamically assess whether the fuel assembly has fuel failure risks such as temperature over-limit, local overheating or abnormal heat conduction, and provide direct support for fuel safety monitoring and control, thereby improving the fuel safety and fuel stability of the nuclear power unit.

[0030] The following briefly introduces the application scenarios to which the technical solutions of the embodiments of the present application can be applied. It should be noted that the application scenarios introduced below are only used to illustrate the embodiments of the present application and are not limited. In the specific implementation process, the technical solutions provided by the embodiments of the present application can be flexibly applied according to actual needs.

[0031] The solution provided by the embodiments of the present application can be applied to most scenarios involving fuel safety monitoring and risk assessment. For example, in the scenario of high power output of a nuclear power plant, for nuclear power units operating at high load, the embodiments of the present application can obtain the operating parameters of the fuel assemblies under high load operation in real time, and obtain the key safety parameters of the fuel assemblies through the fuel safety parameter determination method, thereby providing a comprehensive analysis of the state of the fuel assemblies. By evaluating and controlling the thermal load and mechanical stress of the fuel, timely safety control operations such as adjusting the power and cooling flow rate are taken to reduce the risk of fuel failure, avoid overheating, cladding rupture or fuel failure caused by high load operation, and greatly improve the safety of the fuel assemblies and the stability of reactor operation.

[0032] Of course, the method provided in the embodiment of the present application is not limited to the above application scenarios, but can also be used in other possible application scenarios, which are not limited by the embodiment of the present application. The functions that can be realized by each device in the above application scenarios will be described in the subsequent method embodiments, and no further details will be given here.

[0033] Below, in combination with the application scenarios described above, the method provided by the exemplary embodiment of the present application is described with reference to the accompanying drawings. It should be noted that the above application scenarios are only shown to facilitate understanding of the spirit and principles of the present application, and the implementation methods of the present application are not limited in this regard.

[0034] First, an embodiment of the present application provides a structural schematic diagram of a fuel safety parameter determination system, the system comprising:

[0035] The core monitoring module is used to monitor the operating status of the reactor core in real time and provide the fuel performance calculation module with the operating parameters of each fuel assembly so that the fuel performance calculation module can perform subsequent calculations. As an important system for reactor operation support, the core monitoring module can realize functions such as online measurement and monitoring of the core, core prediction, and core tracking analysis, and can interact with other systems such as power plant instruments and control systems through a large number of interfaces.

[0036] The fuel performance calculation module, including the temperature calculation submodule and the PCI calculation submodule, is used to obtain the operating condition parameters and preset fuel design parameters provided by the core monitoring module, and calculate the performance parameters of the fuel assembly at the current moment through the fuel performance analysis program, including temperature safety parameters such as fuel temperature, cladding temperature, fuel load, and transient safety parameters such as cladding transient stress, cladding transient strain and PCI margin, and can generate a restart file for each fuel assembly for the calculation of fuel performance parameters in the next time step.

[0037] In a possible implementation, the data interface for transmitting data between the core monitoring module and the fuel performance calculation module can be divided into two categories: input interface files and output interface files. The core monitoring module can provide the required interface parameters, such as the operating condition parameters of each fuel assembly, to the fuel performance calculation module through the input interface file. In addition, in the embodiment of the present application, the content of the interface file will store the relevant data of the characteristic fuel rods of each fuel assembly in units of fuel assemblies, and no longer store the historical data of all fuel rods in the fuel assembly. Fuel assemblies and characteristic fuel rods can be pre-selected according to actual needs to greatly reduce the amount of calculation of the fuel performance calculation module and improve the efficiency of determining fuel safety parameters. After obtaining the fuel safety parameters, the fuel rod performance calculation module writes the calculation results (temperature safety parameters and transient safety parameters) into the output interface file for other systems or interfaces to read and display.

[0038] See also Figure 1 As shown, it is a flow chart of a method for determining fuel safety parameters provided by an embodiment of the present application. The specific implementation process of the flow chart of the method is as follows:

[0039] Step 101: Obtain the operating parameters of each fuel assembly.

[0040] In the embodiment of the present application, each nuclear reactor core of a nuclear power unit may be composed of a plurality of fuel assemblies, which are basic units for generating fission reactions in a nuclear reactor and may be composed of a plurality of fuel rods arranged in an arrangement. The fuel rod is the basic constituent unit of the fuel assembly, which is usually a cylindrical pellet filled with nuclear fuel and wrapped with a high temperature resistant and corrosion resistant cladding to provide the required fuel for the fission reaction. The operating condition parameters of the fuel assembly may be the operating condition parameters of the characteristic fuel rods of the fuel assembly under the operating state.

[0041] Specifically, a characteristic fuel rod (or representative fuel rod) is a specific fuel rod that can reflect the performance of the entire fuel assembly. Since the operating conditions of each fuel rod in the fuel assembly may be different, directly obtaining the detailed parameters of each fuel rod is relatively cumbersome and has high operating costs in actual operation. For example, there are 157 groups of fuel assemblies in the core of the AP1000 reactor, and each fuel assembly contains 256 fuel rods, that is, there are more than 40,000 fuel rods in the entire core. It is worth mentioning that this commercial reactor is only an example, and the embodiment of the present application does not specifically limit the order of magnitude of applicable fuel assemblies and fuel rods. Therefore, the embodiment of the present application can select characteristic fuel rods to represent the overall level of the fuel assembly for subsequent analysis and calculation.

[0042] In a possible implementation, the operating condition parameters of the embodiment of the present application may include: axial power distribution of characteristic fuel rods, average linear power density of characteristic fuel rods, burnup of characteristic fuel rods, and coolant inlet temperature of characteristic fuel rods.

[0043] Specifically, the axial power distribution represents the power distribution of the fuel rod along the length direction, reflecting the temperature and stress distribution of the fuel; the average linear power density represents the average power per unit length of the fuel rod, reflecting the overall heat load level of the fuel rod; the burnup represents the consumption of fissionable materials in the fuel, reflecting the remaining life of the fuel; the coolant inlet temperature represents the temperature of the coolant when it enters the fuel assembly, reflecting the starting temperature condition of fuel heat transfer.

[0044] Step 102: Based on the operating condition parameters and fuel design parameters of each fuel assembly, temperature calculation processing is performed to obtain the temperature safety parameters of each fuel assembly.

[0045] In the embodiment of the present application, the fuel design parameters represent information such as the geometric structure of the fuel rod (e.g., fuel rod length, diameter, wall thickness, pellet density, etc.), material properties (e.g., fuel pellet material, cladding material, etc.). Through the fuel performance analysis program, the operating condition parameters of the fuel assembly and the fuel design parameters can be processed by temperature calculation to obtain temperature safety parameters reflecting the thermal state and heat load distribution of the fuel assembly.

[0046] Specifically, the fuel design parameters can be determined according to the type of fuel assembly, for example, different types of fuel assemblies have a set of fuel design parameters, for example, AP1000 fuel assemblies and AFA 3G fuel assemblies each correspond to a set of fuel design parameters, so that the corresponding fuel design parameters can be input according to the type of fuel assembly in the nuclear reactor to be tested. The fuel design parameters include, but are not limited to: cladding material, cladding inner and outer diameters, pellet material, pellet inner and outer diameters, pellet height, pellet density, pellet enrichment, active zone length, fuel rod grid spacing, pre-filled gas type, pre-filled gas pressure and other information, which can be set according to the actual scene requirements, and the embodiments of the present application do not specifically limit this.

[0047] In a possible implementation, the temperature safety parameters may include but are not limited to the fuel load of the fuel assembly, the fuel temperature of the fuel assembly, and the cladding temperature of the fuel assembly. Among them, the fuel temperature represents the temperature of the fuel pellets, the fuel load represents the total heat load that the fuel cladding bears during operation, and the cladding temperature of the fuel assembly represents the temperature of the outer cladding surface of the fuel rod, which is an important indicator of the heat dissipation performance and cooling efficiency of the fuel assembly, affecting the safety of the fuel and the mechanical properties of the cladding. These temperature safety parameters can directly reflect the heat load and heat dissipation capacity of the fuel assembly, and provide a reliable basis for real-time monitoring and safety assessment of fuel performance.

[0048] In a possible implementation, the embodiment of the present application can perform temperature calculation processing through a fuel performance analysis program to calculate the temperature safety parameters of the fuel assembly. For example, the axial power distribution of the characteristic fuel rod is used to calculate the power value at different positions, and the fuel load is cumulatively calculated by combining the fuel rod length and operation time. The heat at different positions of the fuel rod is determined by combining the axial power distribution and the average linear power density, and the fuel temperature is calculated using the fuel geometric parameters (such as the pellet thickness) and the heat conduction characteristics.

[0049] In one possible implementation, in order to further improve fuel safety, the embodiment of the present application can obtain the temperature safety parameters of the fuel assembly based on the aforementioned calculation, dynamically evaluate the risk of fuel failure, and perform relevant safety control on the fuel assembly to improve fuel safety and stability.

[0050] In a possible implementation, the embodiment of the present application can determine whether the corresponding fuel assembly meets the preset first failure condition according to the difference between the temperature safety parameter and the preset temperature threshold. When at least one fuel assembly meets the first failure condition, the corresponding fuel assembly is subjected to temperature control processing.

[0051] Specifically, taking the temperature safety parameters of fuel load, fuel temperature and cladding temperature as an example, excessive fuel load may cause deformation, cracking or expansion of fuel pellets, affecting the integrity of the fuel and the bearing capacity of the cladding. High cladding temperature may also cause the cladding material strength to decrease or abnormal corrosion, and overheating of fuel pellets may cause melting or abnormal fission product release, resulting in an increased risk of fuel failure. In the embodiment of the present application, the fuel performance analysis program can compare the above temperature safety parameters calculated in real time with the corresponding preset temperature thresholds to determine whether each fuel assembly meets the first failure condition. For example, when any value of the fuel load, fuel temperature or cladding temperature exceeds the corresponding preset temperature threshold, it is confirmed that the corresponding fuel assembly meets the first failure condition. In addition, when it is confirmed that one or more fuel assemblies meet the first failure condition, the embodiment of the present application will perform relevant temperature control processing on the corresponding fuel assembly, such as triggering an alarm mechanism to prompt the operator to perform relevant intervention, or performing temperature safety control such as cooling operation or adjusting the operating power through an automatic control system. Specifically, temperature safety control may include: when the fuel temperature or cladding temperature is too high, reducing the reactor power, slowing down the nuclear reaction rate, and thus reducing the heat load. Alternatively, when the coolant temperature and the cladding temperature exceed a preset temperature threshold, the coolant flow rate is increased to enhance the heat exchange effect and reduce the temperature, which is not specifically limited in the embodiments of the present application.

[0052] Furthermore, in addition to the temperature safety parameters directly associated with fuel failure caused by excessive fuel load, the fuel safety parameters of the fuel assembly also include transient safety parameters directly associated with fuel failure under transient conditions. Transient conditions represent changes in operating conditions of a nuclear power unit in a short period of time, such as power rise and fall, coolant temperature changes, etc., and the relevant transient safety parameters represent the mechanical load and strain capacity of the fuel assembly of the nuclear power unit under transient conditions. For example, the transient stress and transient strain of the cladding reflect the stress and deformation of the cladding under transient conditions such as power mutation or coolant temperature change, and excessive stress or strain may cause the cladding to rupture or damage, resulting in a fuel failure event. Another example is that the PCI margin represents the safety margin of the mechanical interaction between the fuel pellet and the cladding. When the PCI margin is insufficient, the expansion or displacement of the fuel pellet may cause a sharp increase in stress in the cladding, causing cracks or damage, resulting in fuel failure. In this way, the embodiment of the present application can effectively control and prevent fuel failure events that may occur in nuclear power units under transient conditions by accurately monitoring transient safety parameters.

[0053] Please refer to Figure 2 The figure shows a flow chart of another method for determining fuel safety parameters provided by an embodiment of the present application. The specific implementation process of the flow chart of the method is as follows:

[0054] Step 201: Based on the restart parameter set and transient operating condition parameters of each fuel assembly, a transient input parameter set of each fuel assembly is obtained.

[0055] In the embodiment of the present application, the restart parameter set can be obtained according to the operating condition parameters and fuel design parameters of each fuel assembly in the aforementioned steps 101-102, and the restart parameter set includes the state parameters of the corresponding characteristic fuel rods, such as fuel rod temperature, cladding stress, cladding strain, pellet cladding gap, fission gas release rate and other parameters. The transient operating condition parameter table represents the operating condition parameters of the corresponding fuel assembly within a preset transient time period. Combining the restart parameter set and the transient operating condition parameters, the transient input parameter set of each fuel assembly can be obtained, providing a data basis for subsequent transient safety parameters.

[0056] Specifically, the fuel rod temperature in the restart parameter set affects the thermal expansion of the fuel pellets and the release of fission gases, and can represent the heat transfer rate and mechanical interaction between the pellets and the cladding, and is used to calculate the mechanical load of the pellets on the cladding. The cladding stress and strain represent the initial mechanical state of the cladding, reflecting its stress and strain distribution under transient conditions. The pellet-cladding gap represents the size of the space between the pellets and the cladding, reflecting the contact pressure and friction effect between the two under transient conditions.

[0057] In a possible implementation, the transient operating condition parameters may include a preset transient time step increment, transient power, and transient force threshold. The transient time step increment represents the time interval of the preset transient time period, the transient power represents the power change of the fuel rod within the transient time step increment, and the transient force threshold represents the critical value of the mechanical interaction force between the pellet and the cladding of the fuel assembly leading to cladding failure, that is, the maximum force that the cladding is allowed to withstand, which can be used to assess whether there is a risk of fuel failure.

[0058] Specifically, according to the classification of pressurized water reactor nuclear power plant conditions (NB / T 20662), the conditions I (normal operation) and II (expected operation events) in the classification of conditions can be used as transient conditions in the embodiment of the present application. The transient condition parameters can be set in advance according to the type of nuclear power unit and fuel assembly. For example, in the embodiment of the present application, the maximum local power of the fuel rod under the transient condition can be used as the transient power, the time step required for the fuel rod power to reach the peak value can be used as the transient time step increment, and the critical value of the mechanical interaction force between the fuel cladding and the pellet corresponding to the fuel assembly type that causes the cladding failure can be used as the transient force threshold, also known as the PCI failure limit.

[0059] In a possible implementation, the embodiment of the present application can calculate the restart parameter set of each fuel assembly at the current time step by combining the operating condition parameters and fuel design parameters of each fuel assembly through a fuel performance analysis program, which can include fuel rod state parameters of characteristic fuel rods at the current time step, such as fuel temperature, cladding stress, cladding strain, pellet cladding gap, fission gas release rate and other parameters. The restart parameter set can not only provide a data basis for the transient input parameter set, but can also be called in subsequent time steps to quickly update and obtain the restart parameter set of subsequent time steps, saving computing time and computing resources and improving computing efficiency.

[0060] Step 202: Based on the transient input parameter set of each fuel assembly, a transient calculation process is performed to obtain the transient safety parameters of each fuel assembly.

[0061] In an embodiment of the present application, a fuel performance analysis program can be used to perform transient calculation processing on a transient input parameter set of a fuel assembly to obtain transient safety parameters that reflect the mechanical load and strain capacity of the corresponding fuel assembly under transient conditions.

[0062] In a possible embodiment, the transient safety parameters may include: the transient stress of the cladding of the fuel assembly, the transient strain of the cladding of the fuel assembly and the transient force margin of the fuel assembly, wherein the transient stress of the cladding represents the stress borne by the cladding under transient conditions, reflecting the direct impact of the transient load on the cladding; the transient strain of the cladding represents the deformation of the cladding under transient conditions, reflecting the deformation capacity and state of the cladding; the transient force margin (PCI margin) represents the safety margin between the mechanical interaction force between the pellet and the cladding of the fuel assembly and the transient force threshold (PCI failure limit), and can be used to measure the safety boundary of the mechanical interaction between the fuel pellet and the cladding.

[0063] Specifically, the embodiments of the present application can calculate the thermal expansion and volume change of the fuel pellets according to the fuel temperature and the fission gas release rate, and then use the geometric parameters of the fuel rods (such as the pellet-cladding gap) and thermal expansion data to calculate the contact pressure exerted by the pellets on the inner wall of the cladding, and superimpose the pressure change caused by the transient power on the initial stress state of the cladding to obtain the transient stress distribution of the cladding at each time step, that is, calculate the transient stress of the cladding of the fuel assembly. Based on the calculated transient stress of the cladding, combined with the elastic modulus and plastic properties of the cladding material, the transient strain of the cladding can be calculated. Since the PCI margin represents the safety margin between the current cladding state and the critical point of failure, the current PCI margin can be calculated by comparing the transient stress and the force threshold.

[0064] In a possible implementation, the fuel performance calculation module in the embodiment of the present application has a restart function, and can update the restart parameter set of each fuel assembly in the next time step based on the restart parameter set of the current time step after a preset time step interval. And based on the updated restart parameter set, perform temperature calculation processing and transient calculation processing to update the temperature safety parameters and transient safety parameters of each fuel assembly. In this way, each fuel safety parameter calculation can only call the restart parameter set, and then perform calculations for a limited time step (for example, a single-digit time step), and quickly output the calculation results, thereby ensuring that the calculation results can be output in real time, and even clock-level real-time output can be achieved.

[0065] Specifically, the first time step is the starting moment of the fuel safety parameter determination process, so the first time step will not refer to the restart parameter set of other time steps for update, but use the fuel performance analysis program to generate the restart parameter set corresponding to the first time step. For subsequent time steps, the restart parameter set of the current time step can be generated by calculating one more time step based on the restart parameter set of the previous time step, so that the corresponding fuel safety parameter acquisition process can be carried out through the restart parameter set, thereby avoiding calculation from scratch, effectively improving calculation efficiency, and saving calculation time.

[0066] In one possible implementation, in order to further improve fuel safety, the embodiment of the present application can obtain the transient safety parameters of the fuel assembly based on the aforementioned calculation, dynamically evaluate the risk of fuel failure, and perform relevant safety control on the fuel assembly to improve fuel safety and stability.

[0067] In a possible implementation, the embodiment of the present application can determine whether the corresponding fuel assembly meets the preset second failure condition based on the difference between the transient safety parameter and the preset transient threshold value. When at least one fuel assembly meets the second failure condition, the corresponding fuel assembly is subjected to transient control processing.

[0068] Specifically, taking the transient safety parameters as cladding transient stress, cladding transient strain and transient force margin as an example, the embodiment of the present application can compare the above transient safety parameters calculated in real time by the fuel performance analysis program with the corresponding preset transient thresholds to determine whether each fuel assembly meets the second failure condition. For example, when any value of the cladding transient stress and cladding transient strain exceeds the corresponding preset transient threshold, or the transient force margin is less than the corresponding preset transient threshold, it is confirmed that the corresponding fuel assembly meets the second failure condition, and the corresponding fuel assembly is subjected to relevant transient control processing, such as triggering an alarm mechanism to prompt the operator to perform relevant intervention, or performing relevant safety control through an automatic control system. Specifically, the transient control processing may include: when it is detected that the margin is close to or less than the set PCI failure limit, the rate or amplitude of power change can be limited to avoid rapid power change, the power distribution of the fuel rod can be adjusted, and the local excessive power density can be reduced to ensure that the interaction between the cladding and the pellet is maintained within a safe range to avoid cladding rupture. Or, in a transient condition of power increase, when the transient stress and strain of the cladding exceed the relevant preset thresholds, it indicates that the cladding is close to its bearing capacity and strain limit under the condition of rapid expansion, and the stress and strain of the cladding can be reduced by reducing the reactor power, reducing the heat load of the fuel rods, increasing the coolant flow rate, enhancing the cooling effect, and reducing the cladding temperature. Of course, the embodiment of the present application does not specifically limit the transient control processing method, and it can be selected according to the actual scene requirements.

[0069] In one possible implementation, please refer to Figure 3 As shown, it is a flowchart of the fuel safety parameter calculation process provided by the embodiment of the present application. The specific implementation process of the flowchart is as follows:

[0070] Step 301: Obtain the operating parameters of each fuel assembly at the first time step.

[0071] In an embodiment of the present application, the input interface file of the first time step can be read through the core monitoring module to obtain the axial power distribution, average linear power density, burnup, and coolant inlet temperature of the characteristic fuel rods of each fuel assembly at the first time step as operating condition parameters of each fuel assembly.

[0072] Step 302: Generate a basic input card for each fuel assembly based on the fuel design parameters.

[0073] In the embodiment of the present application, the basic input card of each fuel group at the first time step can be generated through the preset fuel design parameters, such as the geometric design parameter file of the fuel rod, and the input interface file read by the core monitoring module at the first time step. The basic input card of each fuel assembly contains the operating condition parameters and fuel design parameters of the fuel assembly, that is, the basic parameter set, which provides a data basis for the fuel rod performance module to perform fuel rod performance analysis later and obtain its related temperature safety parameters and transient safety parameters.

[0074] Specifically, an input card refers to a text file that records all the input information required by the fuel rod performance module for calculating fuel safety parameters in a specified format. For example, a basic input card may contain information such as fuel design parameters, historical power of fuel rods (for example, axial power distribution, average linear power density, burnup, etc. of fuel rods at each time step), coolant system pressure, coolant inlet temperature, coolant flow rate, etc.

[0075] Step 303: Based on the basic input card, perform temperature calculation processing to obtain the temperature safety parameters and restart file of each fuel assembly.

[0076] In the embodiment of the present application, the temperature safety parameters of each fuel assembly, such as the fuel load, fuel temperature, cladding temperature, etc. of each fuel assembly, and the restart file of each fuel assembly can be calculated by the fuel performance analysis program in combination with the basic input card of each fuel assembly. The restart file contains the fuel rod state parameters of the characteristic fuel rod at the first time step, such as the restart parameter set such as fuel temperature, cladding stress, cladding strain, pellet cladding gap, fission gas release rate, etc.

[0077] Specifically, the restart file is an output file of the fuel rod performance analysis module, which records the fuel performance calculation results of each time step that has been calculated, including but not limited to temperature safety parameters and transient safety parameters, etc. The restart file of each time step can be used as the input of the fuel rod performance analysis module of the next time step. By quickly retrieving the fuel performance analysis results at a specified time step and continuing the calculation based on the data of this time step, a large number of repeated calculations are avoided, the calculation efficiency is improved, and the calculation time is saved.

[0078] Specifically, since the first time step is the starting moment of the fuel safety parameter determination process, the first time step cannot reference the restart file of other time steps, but uses the fuel performance analysis program to generate the restart file corresponding to the first time step. The restart file is not only the data basis for the subsequent generation of the PCI input card, but can also be referenced in subsequent time steps. By calculating one more time step based on the restart file of the current time step, the restart file of the subsequent N+1 time step is gradually generated, thereby avoiding starting from scratch, effectively improving the calculation efficiency, and saving calculation time.

[0079] Step 304: Based on the restart file and preset transient operating parameters, obtain the PCI input card of each fuel assembly.

[0080] In the embodiment of the present application, a PCI input card containing transient input parameters such as transient time step increment, transient power, PCI limit, etc. of the fuel assembly is obtained through the basic input card of each fuel assembly and the preset transient operating parameters, so as to provide basic data for subsequent fuel rod performance analysis and acquisition of relevant transient safety parameters.

[0081] Step 305: Based on the PCI input card, perform transient calculation processing to obtain transient safety parameters of each fuel assembly.

[0082] In the embodiment of the present application, the transient safety parameters such as the cladding transient stress, cladding transient strain and PCI margin of the fuel assembly can be calculated through the fuel performance analysis program in combination with the PCI input card of each fuel assembly.

[0083] Step 306: Store the temperature safety parameter and the transient safety parameter in the output interface file, and display them in real time through the display interface.

[0084] In the embodiment of the present application, after the fuel performance analysis program is completed, the calculation results such as temperature safety parameters and transient safety parameters can be written into the output interface file for reading and display by other systems or interfaces.

[0085] In a possible implementation, after obtaining the fuel safety parameters of the first time step, the embodiment of the present application can also obtain the fuel safety parameters of subsequent time steps according to the restart file of the first time step.

[0086] Taking the N+1th time step as an example, where N is a positive integer greater than or equal to 1, the core monitoring module provides an input interface file for the N+1th time step, which includes the operating parameters of each fuel assembly at the N+1th time step. Through the preset fuel design parameters and the input interface file read by the core monitoring module at the N+1th time step, the basic input card of each fuel group at the N+1th time step is generated. In addition, the restart file of the Nth time step is called, and through the fuel performance analysis program, based on the fuel rod status data provided by the restart file of the Nth time step, another time step is calculated to obtain the temperature safety parameters of the N+1th time step and the restart file of the N+1th time step.

[0087] Next, according to the restart file of the N+1th time step and the preset transient operating condition parameters, the PCI input card of the N+1th time step is generated. Thus, the restart file of the Nth time step is called, and the time step corresponding to the transient operating condition is added to the fuel rod state data provided by the restart file of the N+1th time step through the fuel performance analysis program, and the transient safety parameters are calculated. The obtained fuel safety parameters are stored in the output interface file and displayed in real time through the interface. In this way, the restart file of each time step is used as the input basis of the next time step, and the historical parameter information stored in the restart file is used to repeat the fuel safety parameter acquisition process, thereby optimizing the parameter calculation process and improving the efficiency of fuel safety parameter acquisition.

[0088] See also Figure 4 As shown, based on the same inventive concept, the embodiment of the present application further provides a fuel safety parameter determination device 40, which includes:

[0089] The first acquisition unit 401 is used to acquire the operating condition parameters of at least one fuel assembly, where the operating condition parameters represent: the operating condition parameters of the fuel rods of the corresponding fuel assembly in the operating state.

[0090] The temperature calculation unit 402 is used to perform temperature calculation processing based on the operating condition parameters and fuel design parameters of each fuel assembly to obtain the temperature safety parameters of each fuel assembly, and the temperature safety parameters represent the thermal state and heat load distribution of the fuel assembly.

[0091] Optionally, the device further includes a second acquisition unit 403 and a transient calculation unit 404, wherein:

[0092] The second acquisition unit 403 is used to obtain the transient input parameter set of each fuel assembly based on the restart parameter set and transient operating condition parameters of each fuel assembly; the restart parameter set is obtained based on the corresponding operating condition parameters and fuel design parameters, and the restart parameter set includes the state parameters of the corresponding fuel rod, and the transient operating condition parameters represent the operating condition parameters of the corresponding fuel assembly within a preset transient time period;

[0093] The transient calculation unit 404 is used to perform transient calculation processing based on the transient input parameter set of each fuel assembly to obtain the transient safety parameters of each fuel assembly, and the transient safety parameters represent the mechanical load and strain capacity of the corresponding fuel assembly under transient conditions.

[0094] Optionally, the device further includes a restart unit 405, configured to:

[0095] After a preset time step interval, based on the restart parameter set, updating the restart parameter set of each fuel assembly at the next time step;

[0096] Based on the updated restart parameter set, temperature calculation processing and transient calculation processing are performed to update the temperature safety parameters and transient safety parameters of each fuel assembly.

[0097] Optionally, the device further includes a failure control unit 406, which is used to:

[0098] Based on the difference between the temperature safety parameter and the preset temperature threshold, determining whether the corresponding fuel assembly meets the preset first failure condition;

[0099] When at least one fuel assembly meets a first failure condition, a temperature control process is performed on the corresponding fuel assembly.

[0100] Optionally, the failure control unit 406 is further configured to:

[0101] Based on the difference between the transient safety parameter and the preset transient threshold, determining whether the corresponding fuel assembly meets the preset second failure condition;

[0102] When at least one fuel assembly meets the second failure condition, a transient control process is performed on the corresponding fuel assembly.

[0103] Optionally, the operating condition parameters include at least: axial power distribution of characteristic fuel rods, average linear power density of characteristic fuel rods, burnup of characteristic fuel rods, and coolant inlet temperature of characteristic fuel rods, wherein the characteristic fuel rods are specific fuel rods that reflect the performance of the entire fuel assembly.

[0104] Optionally, the temperature safety parameters include at least: the fuel load of the fuel assembly, the fuel temperature of the fuel assembly, and the cladding temperature of the fuel assembly.

[0105] Optionally, the transient operating condition parameters include at least: transient time step increment, transient power and transient force threshold, wherein the transient time step increment represents the time interval of a preset transient time period, the transient power represents the power change of the fuel rod within the transient time step increment, and the transient force threshold represents the critical value of the mechanical interaction force between the core block and the cladding of the fuel assembly leading to cladding failure.

[0106] Optionally, the transient safety parameters include at least: transient stress of the cladding of the fuel assembly, transient strain of the cladding of the fuel assembly and transient force margin of the fuel assembly, and the transient force margin characterizes the safety margin between the mechanical interaction force between the pellet and the cladding of the fuel assembly and the transient force threshold.

[0107] For the convenience of description, the above parts are divided into each unit module (or module) according to the function and described separately. Of course, when implementing the present application, the functions of each unit (or module) can be implemented in the same one or more software or hardware. It can be understood by those skilled in the art that various aspects of the present application can be implemented as a system, method or program product. Therefore, various aspects of the present application can be specifically implemented in the following forms, namely: a complete hardware implementation method, a complete software implementation method (including firmware, microcode, etc.), or an implementation method combining hardware and software, which can be collectively referred to as "circuit", "module" or "system" here.

[0108] The device can be used to execute the methods shown in the various embodiments of the present application. Therefore, for the functions that can be implemented by the various functional modules of the device, reference can be made to the description of the aforementioned embodiments and no further details will be given.

[0109] See also Figure 5 As shown, based on the same technical concept, an embodiment of the present application further provides a computer device 50 , which may be a fuel safety parameter determination system, and the computer device 50 may include a memory 501 and a processor 502 .

[0110] The so-called memory 501 is used to store computer programs executed by the processor 502. The memory 501 may mainly include a program storage area and a data storage area, wherein the program storage area may store an operating system, an application required for at least one function, etc.; the data storage area may store data created according to the use of the computer device, etc. The processor 502 may be a central processing unit (CPU), or a digital processing unit, etc. The specific connection medium between the above-mentioned memory 501 and the processor 502 is not limited in the embodiments of the present application. The embodiments of the present application are Figure 5 In the embodiment, the memory 501 and the processor 502 are connected via a bus 503. The bus 503 is connected to the processor 502 via a bus 503. Figure 5The connection between other components is shown by bold lines, and is not intended to be limiting. The so-called bus 503 can be divided into an address bus, a data bus, a control bus, etc. For ease of representation, Figure 5 Only one thick line is used in the diagram, but this does not mean that there is only one bus or only one type of bus.

[0111] The memory 501 may be a volatile memory, such as a random-access memory (RAM); the memory 501 may also be a non-volatile memory, such as a read-only memory, a flash memory, a hard disk drive (HDD) or a solid-state drive (SSD), or the memory 501 may be any other medium that can be used to carry or store the desired program code in the form of instructions or data structures and can be accessed by a computer, but is not limited thereto. The memory 501 may be a combination of the above memories.

[0112] The processor 502 is used to execute the fuel safety parameter determination method executed by the device in each embodiment of the present application when calling the computer program stored in the so-called memory 501.

[0113] In some possible embodiments, various aspects of the fuel safety parameter determination method provided in the present application can also be implemented in the form of a program product, which includes program code. When the program product is run on a computer device, the program code is used to enable the computer device to execute the steps of the fuel safety parameter determination method according to various exemplary embodiments of the present application described above in this specification. For example, the computer device can execute the steps of each embodiment.

[0114] The program product may use any combination of one or more readable media. The readable medium may be a readable signal medium or a readable storage medium. The readable storage medium may be, for example, but not limited to, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, device or device, or any combination of the above. More specific examples of readable storage media (a non-exhaustive list) include: an electrical connection with one or more wires, a portable disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the above.

[0115] The program product of the embodiment of the present application may adopt a portable compact disk read-only memory (CD-ROM) and include program code, and can be run on a computing device. However, the program product of the present application is not limited thereto. In the present application, the readable storage medium may be any tangible medium containing or storing a program, which may be used by or in combination with a command execution system, device or device.

[0116] The readable signal medium may include a data signal propagated in baseband or as part of a carrier wave, wherein the readable program code is carried. Such propagated data signals may take a variety of forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination of the above. The readable signal medium may also be any readable medium other than a readable storage medium, which may send, propagate, or transmit a program for use by or in conjunction with a command execution system, apparatus, or device.

[0117] The program code embodied on the readable medium may be transmitted using any appropriate medium, including but not limited to wireless, wired, optical cable, RF, etc., or any suitable combination of the foregoing.

[0118] Program code for performing the operations of the present application may be written in any combination of one or more programming languages, including object-oriented programming languages ​​such as Java, C++, etc., and conventional procedural programming languages ​​such as "C" or similar programming languages. The program code may be executed entirely on the user computing device, partially on the user equipment, as a separate software package, partially on the user computing device and partially on a remote computing device, or entirely on a remote computing device or server. In the case of a remote computing device, the remote computing device may be connected to the user computing device via any type of network including a local area network (LAN) or a wide area network (WAN), or may be connected to an external computing device (e.g., via the Internet using an Internet service provider).

[0119] It should be noted that, although several units or subunits of the device are mentioned in the above detailed description, this division is merely exemplary and not mandatory. In fact, according to the embodiments of the present application, the features and functions of two or more units described above can be embodied in one unit. Conversely, the features and functions of one unit described above can be further divided into multiple units to be embodied.

[0120] In addition, although the operations of the method of the present application are described in a specific order in the drawings, this does not require or imply that the operations must be performed in this specific order, or that all the operations shown must be performed to achieve the desired results. Additionally or alternatively, some steps may be omitted, multiple steps may be combined into one step, and / or one step may be decomposed into multiple steps.

[0121] Those skilled in the art will appreciate that the embodiments of the present application may be provided as methods, systems, or computer program products. Therefore, the present application may adopt the form of a complete hardware embodiment, a complete software embodiment, or an embodiment in combination with software and hardware. Moreover, the present application may adopt the form of a computer program product implemented in one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) that include computer-usable program code.

[0122] Although the preferred embodiments of the present application have been described, those skilled in the art may make additional changes and modifications to these embodiments once they have learned the basic creative concept. Therefore, the appended claims are intended to be interpreted as including the preferred embodiments and all changes and modifications falling within the scope of the present application.

[0123] Obviously, those skilled in the art can make various changes and modifications to the present application without departing from the spirit and scope of the present application. Thus, if these modifications and variations of the present application fall within the scope of the claims of the present application and their equivalents, the present application is also intended to include these modifications and variations.

Claims

1. A method for determining fuel safety parameters, characterized in that: The method comprises: Acquiring an operating condition parameter of at least one fuel assembly, wherein the operating condition parameter represents: an operating condition parameter of a characteristic fuel rod of the corresponding fuel assembly under an operating state, wherein the characteristic fuel rod is a fuel rod reflecting the performance of the entire fuel assembly; Based on the operating condition parameters and fuel design parameters of each fuel assembly, temperature calculation processing is performed to obtain temperature safety parameters of each fuel assembly, wherein the temperature safety parameters characterize the thermal state and thermal load distribution of the fuel assembly.

2. The method according to claim 1, characterized in that After performing temperature calculation processing based on the operating condition parameters and fuel design parameters of each fuel assembly to obtain the temperature safety parameters of each fuel assembly, the method further includes: Based on the restart parameter set and transient operating condition parameters of each fuel assembly, a transient input parameter set of each fuel assembly is obtained; the restart parameter set is obtained based on the operating condition parameters and fuel design parameters of the corresponding fuel assembly, and the restart parameter set includes state parameters of the corresponding characteristic fuel rod, and the transient operating condition parameters represent the operating condition parameters of the corresponding fuel assembly within a preset transient time period; Based on the transient input parameter set of each fuel assembly, transient calculation processing is performed to obtain transient safety parameters of each fuel assembly, wherein the transient safety parameters characterize the mechanical load and strain capacity of the corresponding fuel assembly under transient conditions.

3. The method according to claim 2, characterized in that After obtaining the transient safety parameters of each fuel assembly, the method further includes: After a preset time step interval, based on the restart parameter set, updating the restart parameter set of each fuel assembly at the next time step; Based on the updated restart parameter set, the temperature calculation process and the transient calculation process are performed to update the temperature safety parameters and transient safety parameters of each fuel assembly.

4. The method according to claim 1, characterized in that After obtaining the temperature safety parameters of each fuel assembly, the method further includes: Based on the difference between the temperature safety parameter and the preset temperature threshold, determining whether the corresponding fuel assembly meets the preset first failure condition; When at least one fuel assembly meets the first failure condition, a temperature control process is performed on the corresponding fuel assembly.

5. The method according to claim 2, characterized in that After obtaining the transient safety parameters of each fuel assembly, the method further includes: Based on the difference between the transient safety parameter and the preset transient threshold, determining whether the corresponding fuel assembly meets the preset second failure condition; When at least one fuel assembly meets the second failure condition, a transient control process is performed on the corresponding fuel assembly.

6. The method according to any one of claims 1 to 5, characterized in that: The operating condition parameters include at least: axial power distribution of characteristic fuel rods, average linear power density of characteristic fuel rods, burnup of characteristic fuel rods, and coolant inlet temperature of characteristic fuel rods.

7. The method according to any one of claims 1 to 5, characterized in that: The temperature safety parameters include at least: the fuel load of the fuel assembly, the fuel temperature of the fuel assembly, and the cladding temperature of the fuel assembly.

8. The method according to claim 2, characterized in that The transient operating condition parameters include at least: a transient time step increment, a transient power and a transient force threshold, wherein the transient time step increment represents the time interval of a preset transient time period, the transient power represents the power change of the fuel rod within the transient time step increment, and the transient force threshold represents the critical value of the mechanical interaction force between the pellet and the cladding of the fuel assembly leading to cladding failure.

9. The method according to claim 2, characterized in that The transient safety parameters include at least: transient stress of the cladding of the fuel assembly, transient strain of the cladding of the fuel assembly and transient force margin of the fuel assembly, wherein the transient force margin represents the safety margin between the mechanical interaction force between the pellet and the cladding of the fuel assembly and the transient force threshold.

10. A fuel safety parameter determination device, characterized in that: The device comprises: A first acquisition unit is used to acquire an operating condition parameter of at least one fuel assembly, wherein the operating condition parameter represents: an operating condition parameter of a characteristic fuel rod of a corresponding fuel assembly in an operating state, wherein the characteristic fuel rod is a specific fuel rod reflecting the performance of the entire fuel assembly; The temperature calculation unit is used to perform temperature calculation processing based on the operating condition parameters and fuel design parameters of each fuel assembly to obtain the temperature safety parameters of each fuel assembly, wherein the temperature safety parameters characterize the thermal state and heat load distribution of the fuel assembly.

11. A computer device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, characterized in that: When the processor executes the computer program, the steps of the method according to any one of claims 1 to 9 are implemented.

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