Thermal hydraulic analysis method, device, equipment, medium and product of reactor

Abstract

The invention discloses a thermal hydraulic analysis method, device and equipment of a reactor, a medium and a product, and belongs to the technical field of nuclear power plant design. The method comprises the following steps: when the ith thermal hydraulic analysis operation of a thermal hydraulic analysis task is executed, determining the thermal parameters of fluid at the ith crevasse of a reactor according to the thermal parameters of the (i-1) th containment of the reactor through a thermal hydraulic system analysis program; determining the i-th containment vessel thermal parameter of the reactor according to the fluid thermal parameter at the i-th crevasse through a containment vessel thermal hydraulic analysis program; and when the current total analysis duration of the thermal hydraulic system analysis program is greater than or equal to the preset duration, ending the execution of the thermal hydraulic analysis task. And determining the result of the thermal-hydraulic analysis operation executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program for the last time as the thermal-hydraulic analysis result of the reactor. The accuracy of the calculation result of the thermal hydraulic analysis method of the reactor is improved.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear power plant design, and in particular to a thermal hydraulic analysis method, device, equipment, medium and product for a reactor. Background Art

[0002] Pressurized water reactor nuclear power plants are a type of nuclear power generation technology that is currently widely used. Its core components include primary circuits, secondary circuits, containment, and auxiliary equipment. In the primary circuit, high-temperature and high-pressure water is heated by nuclear fuel, pushed by the main coolant pump, and passes through the steam generator to transfer heat to the water in the secondary circuit, turning it into steam. Subsequently, the water in the primary circuit returns to the nuclear reactor again to continue to take away the heat generated by the nuclear fuel. The steam in the secondary circuit is used to drive the steam turbine generator to provide electricity. The main function of the containment is to ensure that the nuclear power plant can operate normally under internal and external risks, prevent radioactive substances from leaking into the environment, or resist external impacts.

[0003] Consider that the main structures of the primary and secondary circuits are small spaces and pipes, and the flowing medium is mainly single-phase water or a mixture of steam and water. The main structure of the containment is a large compartment or a large pool, and the flowing medium is mainly air or single-phase water. In the traditional breach accident analysis, different calculation models or programs are usually used to perform thermal-hydraulic analysis on the primary circuit, the secondary circuit and the containment. Since the containment space is large and the temperature and pressure changes are small, the thermal-hydraulic system analysis program usually uses the containment as a constant temperature and pressure boundary for analysis and calculation. When using the containment thermal-hydraulic analysis program to analyze the thermal-hydraulic state in the containment after the breach, the thermal parameters of the fluid at the breach are usually used as the input of the containment thermal-hydraulic analysis program. When using the thermal-hydraulic system analysis program to calculate the thermal-hydraulic parameters of the main circuit (reactor primary and secondary circuits), the boundary pressure and temperature of the containment at the breach are used, which are lower than the actual pressure and temperature, resulting in the calculated breach mass-energy parameters and the thermal-hydraulic parameters in the reactor being inaccurate. Due to the inaccurate breach mass-energy parameters, the response parameters such as temperature and pressure calculated by the containment thermal-hydraulic analysis program are biased. Therefore, the calculation results of the traditional thermal-hydraulic analysis method have the problem of low accuracy.

[0004] The above contents are only used to assist in understanding the technical solution of the present invention and do not constitute an admission that the above contents are prior art. Summary of the invention

[0005] The main purpose of the embodiments of the present application is to provide a method, device, equipment, medium and product for thermal-hydraulic analysis of a reactor, aiming to solve the problem of low accuracy of thermal-hydraulic analysis of reactors using existing methods.

[0006] In a first aspect, an embodiment of the present application provides a thermal hydraulic analysis method for a reactor, the method comprising:

[0007] In the event of a breach accident in the reactor, a thermal-hydraulic analysis task of the reactor is performed through a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program; the thermal-hydraulic analysis task includes at least one thermal-hydraulic analysis operation;

[0008] When performing the i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task, the i-th rupture fluid thermal parameters of the reactor are determined according to the i-1th containment thermal parameters of the reactor through the thermal-hydraulic system analysis program; wherein the i-th rupture fluid thermal parameters are converged rupture fluid thermal parameters determined based on the i-th rupture thermal-hydraulic analysis time step; i is a positive integer, and when i is equal to 1, the i-1th containment thermal parameters are steady-state containment thermal parameters of the reactor;

[0009] Determine the i-th containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach through the containment thermal-hydraulic analysis program; wherein the i-th containment thermal parameters are converged containment thermal parameters determined based on at least one i-th containment thermal-hydraulic analysis time step; each of the i-th containment thermal-hydraulic analysis time steps is less than or equal to the i-th breach thermal-hydraulic analysis time step, and the sum of the at least one i-th containment thermal-hydraulic analysis time step is equal to the i-th breach thermal-hydraulic analysis time step;

[0010] After performing the i-th thermal-hydraulic analysis operation, determining a current total analysis time of the thermal-hydraulic system analysis program;

[0011] When the current total analysis duration is greater than or equal to the preset duration, the execution of the thermal-hydraulic analysis task is terminated, and the result of the thermal-hydraulic analysis operation last executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program is determined as the thermal-hydraulic analysis result of the reactor.

[0012] In a second aspect, an embodiment of the present application provides a thermal hydraulic analysis device for a reactor, the device comprising:

[0013] A task module, in the event of a breach accident in the reactor, performs a thermal-hydraulic analysis task of the reactor through a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program; the thermal-hydraulic analysis task includes at least one thermal-hydraulic analysis operation;

[0014] The thermal-hydraulic system analysis module determines the thermal parameters of the fluid at the ith breach of the reactor according to the thermal parameters of the i-1 containment of the reactor through the thermal-hydraulic system analysis program when performing the i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task; wherein the thermal parameters of the fluid at the ith breach are converged thermal parameters of the fluid at the breach determined based on the time step of the thermal-hydraulic analysis of the i-th breach; i is a positive integer, and when i is equal to 1, the i-1th containment thermal parameters are steady-state containment thermal parameters of the reactor;

[0015] A containment thermal-hydraulic analysis module, which determines the i-th containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach through the containment thermal-hydraulic analysis program; wherein the i-th containment thermal parameters are converged containment thermal parameters determined based on at least one i-th containment thermal-hydraulic analysis time step; each of the i-th containment thermal-hydraulic analysis time steps is less than or equal to the i-th breach thermal-hydraulic analysis time step, and the sum of the at least one i-th containment thermal-hydraulic analysis time step is equal to the i-th breach thermal-hydraulic analysis time step;

[0016] A duration determination module, after executing the i-th thermal hydraulic analysis operation, determines the current total analysis duration of the thermal hydraulic system analysis program;

[0017] A result determination module is provided for terminating the execution of the thermal-hydraulic analysis task when the current total analysis duration is greater than or equal to a preset duration, and determining the result of the thermal-hydraulic analysis operation last executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program as the thermal-hydraulic analysis result of the reactor.

[0018] In a third aspect, an embodiment of the present application provides a thermal-hydraulic analysis device for a reactor, the device comprising: a memory, a processor, and a computer processing program stored on the memory and executable on the processor, the computer processing program being configured to implement the steps of the thermal-hydraulic analysis method for a reactor as described in the first aspect.

[0019] In a fourth aspect, an embodiment of the present application provides a storage medium having a computer processing program stored thereon, and when the computer processing program is executed by a processor, the steps of the thermal-hydraulic analysis method of a reactor as described in the first aspect are implemented.

[0020] In a fifth aspect, an embodiment of the present application provides a computer program product, which is stored in a storage medium and is executed by at least one processor to implement the steps of the method described in the first aspect.

[0021] The present application proposes a method, device, equipment, medium and product for thermal hydraulic analysis of a reactor. In the event of a breach accident in a reactor, the thermal hydraulic analysis task of the reactor is performed through a thermal hydraulic system analysis program and a containment thermal hydraulic analysis program. The thermal hydraulic system analysis program calculates the thermal parameters of the fluid at the breach of the reactor, and transmits them to the containment thermal hydraulic analysis program as input. The containment thermal hydraulic analysis program is used to calculate the thermal parameters of the reactor's containment, and the thermal hydraulic system analysis program then uses the containment thermal parameters for analysis and calculation, and the cycle repeats until the preset time is exceeded. Thus, the parameters calculated by the thermal hydraulic system analysis program and the containment thermal hydraulic analysis program can be adjusted in time according to the actual situation, the real-time parameter interaction capability between the programs can be improved, the development of the accident can be better predicted and controlled, and the safety of the nuclear reactor can be improved. In addition, during the parameter calculation process, by judging the convergence of the calculation results, adjusting the time step and multiple calculations, the accuracy of the parameters can be guaranteed, the accuracy of the thermal-hydraulic analysis method of the reactor can be improved, and the safety analysis and evaluation of the main loop system and the containment system under accident conditions can be realized. In addition, using the containment thermal-hydraulic analysis program to calculate the reactor's containment thermal parameters to the same time step as the thermal-hydraulic system analysis program can ensure the consistency of the parameter transfer time between the two programs, thereby improving the real-time performance and accuracy of the parameters. BRIEF DESCRIPTION OF THE DRAWINGS

[0022] Figure 1 It is one of the flow diagrams of the thermal hydraulic analysis method of a reactor provided in the embodiment of the present application;

[0023] Figure 2 This is the second flow diagram of the thermal hydraulic analysis method of a reactor provided in an embodiment of the present application;

[0024] Figure 3 is a schematic structural diagram of a thermal hydraulic analysis device for a reactor provided in an embodiment of the present application;

[0025] Figure 4 It is one of the structural schematic diagrams of the electronic device provided in the embodiment of the present application;

[0026] Figure 5 This is the second structural diagram of the electronic device provided in the embodiment of the present application;

[0027] The realization of the purpose, functional features and advantages of this application will be further explained in conjunction with embodiments and with reference to the accompanying drawings. DETAILED DESCRIPTION

[0028] The following will be combined with the drawings in the embodiments of the present application to clearly describe the technical solutions in the embodiments of the present application. Obviously, the described embodiments are part of the embodiments of the present application, rather than all the embodiments. All other embodiments obtained by ordinary technicians in this field based on the embodiments in the present application belong to the scope of protection of this application.

[0029] The terms "first", "second", etc. in the specification and claims of the present application are used to distinguish similar objects, and are not used to describe a specific order or sequence. It should be understood that the data used in this way can be interchangeable under appropriate circumstances, so that the embodiments of the present application can be implemented in an order other than those illustrated or described here, and the objects distinguished by "first", "second", etc. are generally of one type, and the number of objects is not limited. For example, the first object can be one or more. In addition, "and / or" in the specification and claims represents at least one of the connected objects, and the character " / " generally indicates that the objects associated with each other are in an "or" relationship.

[0030] The thermal-hydraulic analysis of the reactor provided in the embodiment of the present application is described in detail below through specific embodiments and application scenarios in conjunction with the accompanying drawings.

[0031] The present application embodiment provides a thermal hydraulic analysis method for a reactor, and the thermal hydraulic analysis method for a reactor is applied to electronic equipment, such as Figure 1 As shown, the thermal hydraulic analysis method of the reactor in the embodiment of the present application may include the following steps:

[0032] Step 10, in the event of a breach accident in the reactor, executing a thermal-hydraulic analysis task of the reactor through a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program; the thermal-hydraulic analysis task includes at least one thermal-hydraulic analysis operation;

[0033] Step 20, when performing the i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task, determine the i-th breach fluid thermal parameters of the reactor according to the i-1th containment thermal parameters of the reactor through the thermal-hydraulic system analysis program; wherein the i-th breach fluid thermal parameters are converged breach fluid thermal parameters determined based on the i-th breach thermal-hydraulic analysis time step; i is a positive integer, and when i is equal to 1, the i-1th containment thermal parameters are steady-state containment thermal parameters of the reactor;

[0034] Step 30, determining the ith containment thermal parameters of the reactor according to the thermal parameters of the fluid at the ith breach through the containment thermal-hydraulic analysis program; wherein the ith containment thermal parameters are converged containment thermal parameters determined based on at least one ith containment thermal-hydraulic analysis time step; each ith containment thermal-hydraulic analysis time step is less than or equal to the ith breach thermal-hydraulic analysis time step, and the sum of the at least one ith containment thermal-hydraulic analysis time step is equal to the ith breach thermal-hydraulic analysis time step;

[0035] Step 40, after performing the i-th thermal hydraulic analysis operation, determining the current total analysis time of the thermal hydraulic system analysis program;

[0036] Step 50, when the current total analysis time is greater than or equal to the preset time, the execution of the thermal-hydraulic analysis task is terminated, and the result of the thermal-hydraulic analysis operation last executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program is determined as the thermal-hydraulic analysis result of the reactor.

[0037] In the embodiment of the present application, when a reactor rupture accident occurs, the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program are used to perform the thermal-hydraulic analysis task of the reactor, the thermal-hydraulic system analysis program is used to calculate the thermal parameters of the fluid at the rupture of the reactor, and the parameters are transmitted to the containment thermal-hydraulic analysis program as input, the containment thermal-hydraulic analysis program is used to calculate the containment thermal parameters of the reactor, and the thermal-hydraulic system analysis program uses the containment thermal parameters for analysis and calculation, and the cycle is repeated until the preset time is exceeded. Thus, the parameters calculated by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program can be adjusted in time according to the actual situation, the real-time parameter interaction capability between the programs can be improved, the development of the accident can be better predicted and controlled, and thus the safety of the nuclear reactor can be improved. In addition, in the parameter calculation process, by judging the convergence of the calculation results, adjusting the time step and multiple calculations, the accuracy of the parameters can be guaranteed, the accuracy of the thermal-hydraulic analysis method of the reactor can be improved, and then the safety analysis and evaluation of the main loop system and the containment system under the accident condition can be realized. In addition, using the containment thermal-hydraulic analysis program to calculate the reactor containment thermal parameters to the same time step as the thermal-hydraulic system analysis program can ensure the consistency of parameter transfer time between the two programs, thereby improving the real-time and accuracy of the parameters.

[0038] In some embodiments, in the above step 10, first, in the event of a reactor rupture accident, a thermal-hydraulic analysis task is performed on the reactor through a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program, and the task includes at least one thermal-hydraulic analysis operation.

[0039] In this embodiment, it should be noted that the thermal hydraulic analysis may be an analysis and calculation of the heat transfer and fluid flow process in the nuclear reactor, and may be an analysis and calculation of the time-varying thermal hydraulic parameters of the main loop system and the containment system. The thermal hydraulic system analysis program may be a program or software that responds to the thermal hydraulic analysis of the first and second loops of the reactor. The containment thermal hydraulic analysis program may be a program or software that responds to the thermal hydraulic analysis inside the containment.

[0040] It should be noted that, in the case of no reactor breach, the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program can be run separately and independently. In the case of a reactor breach, the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program are coupled to each other.

[0041] In some embodiments, in the above step 20, in each thermal-hydraulic analysis operation, the thermal-hydraulic system analysis program determines the fluid thermal parameters at the current breach according to the thermal parameters of the containment shell of the previous time (i-1 time), and these parameters are convergence parameters determined based on the time step of the thermal-hydraulic analysis of the current breach. If it is the first thermal-hydraulic analysis operation, the thermal-hydraulic system analysis program determines the fluid thermal parameters at the current breach according to the collected steady-state containment shell thermal parameters of the reactor. Among them, the steady-state containment shell thermal parameters are the parameters of the containment shell under normal operating conditions when no accident occurs, and can be the thermal parameters of the reactor containment shell obtained by modeling various parameters of the reactor and using the containment shell thermal-hydraulic analysis program to run stably for a period of time.

[0042] In this embodiment, it should be noted that the containment thermal parameters may be various parameters involved in thermal hydraulic analysis in the containment of a nuclear reactor, such as temperature, pressure, flow rate, etc. The breach fluid thermal parameters may be thermal parameters such as temperature, pressure, flow rate, cavitation, etc. of the fluid at the breach position when a breach accident occurs in the reactor, and may be parameters such as vapor phase mass flow rate, liquid phase mass flow rate, vapor phase internal energy, liquid phase internal energy, non-condensable gas fraction, etc.

[0043] In some embodiments, in the above step 30, in each thermal-hydraulic analysis operation, the containment thermal-hydraulic analysis program determines the current reactor containment thermal parameters based on the fluid thermal parameters at the current breach. The fluid thermal parameters at the current breach are convergence parameters determined based on the current breach thermal-hydraulic analysis time step. The current reactor containment thermal parameters are converged containment thermal parameters determined based on at least one current containment thermal-hydraulic analysis time step. The current containment thermal-hydraulic analysis time step is less than or equal to the current breach thermal-hydraulic analysis time step, and the sum of at least one current containment thermal-hydraulic analysis time step is equal to the current breach thermal-hydraulic analysis time step. In this way, the consistency of the parameter transfer time between the two programs can be ensured, thereby improving the real-time and accuracy of the parameters.

[0044] In some embodiments, in the above step 40, after each thermal-hydraulic analysis operation is performed, the current total analysis time of the thermal-hydraulic system analysis program can be determined. The current total analysis time is the cumulative value of each thermal-hydraulic analysis time step of the thermal-hydraulic system analysis program.

[0045] In some embodiments, in the above step 50, the current total analysis time is compared with the preset time. When the current total analysis time is greater than or equal to the preset time, the thermal-hydraulic analysis task is no longer executed. And the results of the thermal-hydraulic analysis operations last executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program are used as the thermal-hydraulic analysis results of the reactor.

[0046] In some embodiments, after performing the i-th thermal-hydraulic analysis operation, determining the current total analysis duration of the thermal-hydraulic system analysis program includes:

[0047] When the current total analysis duration is less than the preset duration, i is updated to i+1, and the process returns to execute the i-th thermal-hydraulic analysis operation.

[0048] In this embodiment, the current total analysis time is compared with the preset time. When the current total analysis time is less than the preset time, the next thermal-hydraulic analysis operation is performed. By checking the total analysis time after each thermal-hydraulic analysis operation is performed, it can be ensured that the analysis process continues when necessary until the preset analysis time is reached, so that the thermal-hydraulic behavior during the accident process can be simulated and predicted more carefully. In addition, the above-mentioned iterative process allows the program to refine the analysis results in each iteration. Through multiple iterations, the accuracy and reliability of the thermal-hydraulic analysis can be gradually improved. At the same time, this embodiment allows the analysis to continue before the preset time is reached, rather than a fixed number of iterations, which means that the analysis can adapt to the complexity and required details of different situations, providing flexibility. By ending the iteration when the preset time is reached, unnecessary calculations can be avoided, thereby optimizing the use of computing resources.

[0049] In this embodiment, it should be noted that the preset duration may be a preset calculation end duration.

[0050] In some embodiments, the above-mentioned determining the thermal parameters of the fluid at the i-th breach of the reactor according to the i-1th containment thermal parameters of the reactor by the thermal-hydraulic system analysis program includes:

[0051] Based on the jth time step, the thermal parameters of the fluid at the breach of the reactor are calculated according to the thermal parameters of the i-1th containment of the reactor by the thermal hydraulic system analysis program to obtain the thermal parameters of the fluid at the breach corresponding to the jth time step;

[0052] When the thermal parameters of the fluid at the breach corresponding to the j-th time step converge, the thermal parameters of the fluid at the breach corresponding to the j-th time step are determined as the thermal parameters of the fluid at the i-th breach of the reactor; wherein the time step of the thermal-hydraulic analysis of the i-th breach is the j-th time step;

[0053] When the fluid thermal parameters at the rupture corresponding to the j-th time step do not converge, the j-th time step is updated to the j+1-th time step, and the execution is returned to calculate the fluid thermal parameters at the rupture of the reactor based on the j-th time step through the thermal-hydraulic system analysis program according to the i-1-th containment thermal parameters of the reactor, until the fluid thermal parameters at the rupture corresponding to the j-th time step converge; wherein the j+1-th time step is less than the j-th time step, and j is a positive integer.

[0054] In this embodiment, in the jth time step, the thermal parameters of the fluid at the breach are calculated based on the thermal parameters of the reactor's i-1th containment shell using a thermal hydraulic system analysis program. Check whether the thermal parameters of the fluid at the breach calculated in the jth time step have converged. If the parameters converge, the thermal parameters of the fluid at the breach calculated in the jth time step are determined as the thermal parameters of the fluid at the i-th breach, and this time step is used as the time step for the thermal hydraulic analysis of the i-th breach. If the parameters do not converge, the time step will be updated to a smaller j+1th time step, and then the calculation process is repeated until the parameters converge. By iterative calculation until convergence, the accuracy of the calculation of the thermal parameters of the fluid at the breach can be improved, the parameter stability can be improved, and it is also beneficial to thermal hydraulic analysis, and corresponding measures can be taken to solve reactor accidents. By gradually reducing the time step until convergence, computing resources can be used more effectively and unnecessary calculations can be avoided.

[0055] In this embodiment, it should be noted that the time step may be a time period used for iterative calculation in numerical simulation, and the parameter changes within each time step are calculated and analyzed. The jth time step may be an initial breach thermal-hydraulic analysis time step, and the initial breach thermal-hydraulic analysis time step of each thermal-hydraulic analysis operation may be equal or unequal. Convergence may be in numerical analysis, when the result of continuous iteration changes very little or tends to be stable, the solution is called converged.

[0056] In some embodiments, the above-mentioned determining the i-th containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach by the containment thermal-hydraulic analysis program includes:

[0057] Obtaining an initial containment thermal-hydraulic analysis time step of the containment thermal-hydraulic analysis program;

[0058] According to the comparison result of the initial containment thermal-hydraulic analysis time step and the i-th breach thermal-hydraulic analysis time step, the k-th time step is determined; wherein, when the initial containment thermal-hydraulic analysis time step is greater than the i-th breach thermal-hydraulic analysis time step, the k-th time step is the i-th breach thermal-hydraulic analysis time step; when the time step of the initial containment thermal-hydraulic analysis time step is less than or equal to the i-th breach thermal-hydraulic analysis time step, the k-th time step is the initial containment thermal-hydraulic analysis time step; k is a positive integer;

[0059] Based on the kth time step, the thermal parameters of the ith containment shell of the reactor are determined according to the thermal parameters of the fluid at the ith breach through the thermal-hydraulic analysis program of the containment shell.

[0060] In this embodiment, first, the initial containment thermal-hydraulic analysis time step is obtained from the containment thermal-hydraulic analysis program. The initial containment thermal-hydraulic analysis time step is compared with the i-th breach thermal-hydraulic analysis time step. If the initial time step is greater than the i-th breach thermal-hydraulic analysis time step, the i-th breach thermal-hydraulic analysis time step is used for the k-th time step. If the initial time step is less than or equal to the breach thermal-hydraulic analysis time step, the initial containment thermal-hydraulic analysis time step is used for the k-th time step. Using the determined k-th time step, the i-th containment thermal parameters of the reactor are calculated according to the thermal parameters of the fluid at the i-th breach through the containment thermal-hydraulic analysis program. In this way, by selecting an appropriate time step, the calculation efficiency can be improved. Secondly, the analysis program is allowed to adjust the time step according to actual conditions to adapt to different analysis requirements, providing flexibility. By accurately calculating the thermal parameters of the containment, a scientific basis is provided for accident management and mitigation, which can better predict and control the development of accidents and thus improve the safety of nuclear reactors.

[0061] In this embodiment, it should be noted that the kth time step may be the initial containment thermal-hydraulic analysis time step, and each time the thermal-hydraulic analysis operation is performed, the initial containment thermal-hydraulic analysis time step may be equal or unequal.

[0062] In some embodiments, the above-mentioned determining the i-th containment thermal parameters of the reactor based on the k-th time step and according to the thermal parameters of the fluid at the i-th breach by the containment thermal-hydraulic analysis program includes:

[0063] Based on the kth time step, the containment thermal parameters of the reactor are calculated according to the thermal parameters of the fluid at the i-th breach of the reactor by the containment thermal-hydraulic analysis program to obtain the containment thermal parameters corresponding to the kth time step;

[0064] When the containment thermal parameters corresponding to the k-th time step converge, comparing the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation with the i-th breach thermal-hydraulic analysis time step;

[0065] When the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step, the containment thermal parameters corresponding to the k-th time step are determined as the i-th containment thermal parameters of the reactor, wherein the i-th breach thermal-hydraulic analysis time step is the k-th time step;

[0066] In the case that the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is less than the i-th breach thermal-hydraulic analysis time step, the process returns to execution based on the k-th time step, and the containment thermal-hydraulic analysis program calculates the containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach of the reactor, until the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step.

[0067] In this embodiment, the containment thermal-hydraulic analysis program is used to calculate the containment thermal parameters corresponding to the kth time step according to the thermal parameters of the fluid at the i-th breach. Check whether the containment thermal parameters calculated at the k-th time step have converged. If the parameters converge, compare the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation with the i-th breach thermal-hydraulic analysis time step. If the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step, then the containment thermal parameters corresponding to the k-th time step are determined as the i-th containment thermal parameters of the reactor. If the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is less than the i-th breach thermal-hydraulic analysis time step, the calculation will continue based on the k-th time step until the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step. The calculation accuracy of the thermal parameters of the containment is ensured by iterative calculation until convergence. At the same time, the present embodiment provides a reliable method to evaluate the thermal-hydraulic state of a nuclear reactor in a breach accident, thereby enhancing the reliability of accident analysis. By precisely controlling the time step, the use of computing resources is optimized and unnecessary calculations are avoided. In addition, determining the i-th containment thermal parameters of the reactor provides operators and decision makers with detailed information on the progress of the accident, which helps to formulate effective response strategies.

[0068] In some implementations, when the containment thermal parameters corresponding to the kth time step converge, if the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is less than the i-th breach thermal-hydraulic analysis time step, the k-th time step is calculated multiple times until the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step.

[0069] In other implementations, when the containment thermal parameters corresponding to the kth time step converge, if the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is less than the i-th breach thermal-hydraulic analysis time step, then wait until the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step.

[0070] In some embodiments, after calculating the containment thermal parameters of the reactor based on the kth time step by the containment thermal-hydraulic analysis program according to the thermal parameters of the fluid at the i-th breach of the reactor, the method further includes:

[0071] In the case where the thermal parameters of the containment corresponding to the k-th time step do not converge, the k-th time step is updated to the k+1-th time step, and the execution is returned to calculate the thermal parameters of the containment of the reactor according to the thermal parameters of the fluid at the i-th breach of the reactor based on the k-th time step through the containment thermal-hydraulic analysis program until the thermal parameters of the containment corresponding to the k-th time step converge; wherein the k+1-th time step is smaller than the k-th time step, and k is a positive integer.

[0072] In this embodiment, a containment thermal-hydraulic analysis program is used to calculate the containment thermal parameters corresponding to the kth time step based on the thermal parameters of the fluid at the i-th breach. It is determined whether the thermal parameters of the containment calculated at the kth time step converge. If the parameters do not converge, the kth time step is updated to a smaller k+1th time step. Return and execute the calculation based on the updated time step again until the thermal parameters of the containment converge. When the thermal parameters of the containment corresponding to the kth time step converge, the iteration ends. In this way, by iterating until convergence, the high accuracy of the thermal parameter calculation of the containment is ensured. Refining the time step helps to more accurately simulate the thermal-hydraulic behavior during the accident process and improve the reliability of the analysis. In addition, the calculated converged thermal parameters of the containment provide operators and decision makers with accurate thermal parameters, helping them better understand the progress of the accident and formulate response strategies.

[0073] It should be noted that the various embodiments, implementation methods and implementation methods provided in the embodiments of the present application can be implemented independently or in combination without conflicting with each other. The specific implementation method can be determined based on actual needs, and the embodiments of the present application are not limited to this.

[0074] For easier understanding, see Figure 2 , Figure 2 It is another flow chart of an embodiment of the thermal-hydraulic analysis method of a reactor provided in the present application.

[0075] 1) Modeling and steady-state calculation according to the accident type;

[0076] 2) The thermal-hydraulic system analysis program starts the transient calculation based on the time step dt. During the calculation, the time step will be adjusted according to the convergence of the results of the thermal-hydraulic system analysis program until the calculation results converge.

[0077] 3) Transfer the relevant parameters at the reactor break pipe at time dt calculated by the thermal-hydraulic system analysis program to the containment thermal-hydraulic analysis program;

[0078] 4) Execute the calculation of the containment thermal-hydraulic analysis program. If the time step of the containment thermal-hydraulic analysis program is less than or equal to the time step of the thermal-hydraulic system analysis program (dt’ <= dt), the containment thermal-hydraulic analysis program performs the containment thermal-hydraulic calculation based on the time step dt’, and obtains the response parameters such as the pressure and temperature inside the containment, then execute 6).

[0079] 5) If the time step of the containment thermal-hydraulic analysis program is greater than the time step of the thermal-hydraulic system analysis program (dt’ > dt), reduce the time step of the containment thermal-hydraulic analysis program to the time step of the thermal-hydraulic system analysis program and then start the calculation, obtain the response parameters such as the pressure and temperature inside the containment, and execute 6).

[0080] 6) If the calculation results of the containment thermal-hydraulic analysis program converge, then make the containment thermal-hydraulic analysis program calculate until the time point of the thermal-hydraulic system analysis program, and execute 7).

[0081] 7) If the calculation results of the containment thermal-hydraulic analysis program do not converge, the containment thermal-hydraulic module reduces the time step, rolls back and recalculates, calculates until the time point of the thermal-hydraulic system analysis program, and executes 8).

[0082] 8) Transfer the response parameters such as the pressure and temperature inside the containment to the thermal-hydraulic system analysis program;

[0083] 9) If the calculation time (the current total analysis duration) is less than the calculation end time Tend (T < Tend), execute 11).

[0084] 10) If the calculation time is greater than the end time, the calculation terminates.

[0085] 11) The thermal-hydraulic system analysis program enters the next time step for calculation based on the response parameters such as the pressure and temperature feedback by the containment thermal-hydraulic analysis program at the current moment.

[0086] 12) Transfer the relevant parameters at the reactor break pipe at the next moment calculated by the thermal-hydraulic system analysis program to the containment thermal-hydraulic analysis program;

[0087] 13) Carry out thermal hydraulic calculation of containment to obtain response parameters such as pressure and temperature inside the containment;

[0088] 14) Transmit the response parameters such as pressure and temperature in the containment to the thermal hydraulic system analysis program;

[0089] 15) The thermal hydraulic system analysis program transfers data with the containment thermal hydraulic system once every calculation time step;

[0090] 16) Repeat steps 1) to 15).

[0091] Reference Figure 3 One embodiment of the present application provides a thermal hydraulic analysis device for a reactor, the device comprising:

[0092] Task module 301, in the event of a breach accident in the reactor, performs a thermal-hydraulic analysis task of the reactor through a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program; the thermal-hydraulic analysis task includes at least one thermal-hydraulic analysis operation;

[0093] The thermal-hydraulic system analysis module 302, when executing the i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task, determines the i-th breach fluid thermal parameters of the reactor according to the i-1th containment thermal parameters of the reactor through the thermal-hydraulic system analysis program; wherein the i-th breach fluid thermal parameters are converged breach fluid thermal parameters determined based on the i-th breach thermal-hydraulic analysis time step; i is a positive integer, and when i is equal to 1, the i-1th containment thermal parameters are steady-state containment thermal parameters of the reactor;

[0094] The containment thermal-hydraulic analysis module 303 determines the ith containment thermal parameters of the reactor according to the thermal parameters of the fluid at the ith breach through the containment thermal-hydraulic analysis program; wherein the ith containment thermal parameters are converged containment thermal parameters determined based on at least one ith containment thermal-hydraulic analysis time step; each ith containment thermal-hydraulic analysis time step is less than or equal to the ith breach thermal-hydraulic analysis time step, and the sum of the at least one ith containment thermal-hydraulic analysis time step is equal to the ith breach thermal-hydraulic analysis time step;

[0095] The duration determination module 304 determines the current total analysis duration of the thermal hydraulic system analysis program after performing the i-th thermal hydraulic analysis operation;

[0096] The result determination module 305 terminates the execution of the thermal-hydraulic analysis task when the current total analysis duration is greater than or equal to a preset duration, and determines the result of the thermal-hydraulic analysis operation last executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program as the thermal-hydraulic analysis result of the reactor.

[0097] It should be noted that the present device embodiment and the above method embodiment are based on the same inventive concept, so the content of the above method embodiment is also applicable to the present device embodiment and will not be repeated here.

[0098] Alternatively, if Figure 4 As shown, an embodiment of the present application further provides an electronic device 400, including a processor 401 and a memory 402, wherein the memory 402 stores programs or instructions that can be executed on the processor 401, and when the program or instructions are executed by the processor 401, the various steps of the thermal-hydraulic analysis method embodiment of the above-mentioned reactor are implemented, and the same technical effect can be achieved. To avoid repetition, they are not described here.

[0099] It should be noted that the electronic devices in the embodiments of the present application include the above-mentioned mobile electronic devices and non-mobile electronic devices.

[0100] Figure 5 A schematic diagram of the hardware structure of an electronic device implementing an embodiment of the present application.

[0101] The electronic device 500 includes but is not limited to: a radio frequency unit 501, a network module 502, an audio output unit 503, an input unit 504, a sensor 505, a display unit 506, a user input unit 507, an interface unit 508, a memory 509, and a processor 510.

[0102] Those skilled in the art will appreciate that the electronic device 500 may also include a power source (such as a battery) for supplying power to various components, and the power source may be logically connected to the processor 510 via a power management device, thereby implementing functions such as managing charging, discharging, and power consumption management through the power management device. Figure 5 The electronic device structure shown in the figure does not constitute a limitation on the electronic device. The electronic device may include more or fewer components than shown in the figure, or combine certain components, or arrange the components differently, which will not be described in detail here.

[0103] The processor 510 is used for:

[0104] In the event of a breach accident in the reactor, a thermal-hydraulic analysis task of the reactor is performed through a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program; the thermal-hydraulic analysis task includes at least one thermal-hydraulic analysis operation;

[0105] When performing the i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task, the i-th rupture fluid thermal parameters of the reactor are determined according to the i-1th containment thermal parameters of the reactor through the thermal-hydraulic system analysis program; wherein the i-th rupture fluid thermal parameters are converged rupture fluid thermal parameters determined based on the i-th rupture thermal-hydraulic analysis time step; i is a positive integer, and when i is equal to 1, the i-1th containment thermal parameters are steady-state containment thermal parameters of the reactor;

[0106] Determine the i-th containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach through the containment thermal-hydraulic analysis program; wherein the i-th containment thermal parameters are converged containment thermal parameters determined based on at least one i-th containment thermal-hydraulic analysis time step; each of the i-th containment thermal-hydraulic analysis time steps is less than or equal to the i-th breach thermal-hydraulic analysis time step, and the sum of the at least one i-th containment thermal-hydraulic analysis time step is equal to the i-th breach thermal-hydraulic analysis time step;

[0107] After performing the i-th thermal-hydraulic analysis operation, determining a current total analysis time of the thermal-hydraulic system analysis program;

[0108] When the current total analysis duration is greater than or equal to the preset duration, the execution of the thermal-hydraulic analysis task is terminated, and the result of the thermal-hydraulic analysis operation last executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program is determined as the thermal-hydraulic analysis result of the reactor.

[0109] In some implementations, the processor 510 is further configured to:

[0110] When the current total analysis duration is less than the preset duration, i is updated to i+1, and the process returns to execute the i-th thermal-hydraulic analysis operation.

[0111] In some implementations, the processor 510 is further configured to:

[0112] Based on the jth time step, the thermal parameters of the fluid at the breach of the reactor are calculated according to the thermal parameters of the i-1th containment of the reactor by the thermal hydraulic system analysis program to obtain the thermal parameters of the fluid at the breach corresponding to the jth time step;

[0113] When the thermal parameters of the fluid at the breach corresponding to the j-th time step converge, the thermal parameters of the fluid at the breach corresponding to the j-th time step are determined as the thermal parameters of the fluid at the i-th breach of the reactor; wherein the time step of the thermal-hydraulic analysis of the i-th breach is the j-th time step;

[0114] When the fluid thermal parameters at the rupture corresponding to the j-th time step do not converge, the j-th time step is updated to the j+1-th time step, and the execution is returned to calculate the fluid thermal parameters at the rupture of the reactor based on the j-th time step through the thermal-hydraulic system analysis program according to the i-1-th containment thermal parameters of the reactor, until the fluid thermal parameters at the rupture corresponding to the j-th time step converge; wherein the j+1-th time step is less than the j-th time step, and j is a positive integer.

[0115] In some implementations, the processor 510 is further configured to:

[0116] Obtaining an initial containment thermal-hydraulic analysis time step of the containment thermal-hydraulic analysis program;

[0117] According to the comparison result of the initial containment thermal-hydraulic analysis time step and the i-th breach thermal-hydraulic analysis time step, the k-th time step is determined; wherein, when the initial containment thermal-hydraulic analysis time step is greater than the i-th breach thermal-hydraulic analysis time step, the k-th time step is the i-th breach thermal-hydraulic analysis time step; when the time step of the initial containment thermal-hydraulic analysis time step is less than or equal to the i-th breach thermal-hydraulic analysis time step, the k-th time step is the initial containment thermal-hydraulic analysis time step; k is a positive integer;

[0118] Based on the kth time step, the thermal parameters of the ith containment shell of the reactor are determined according to the thermal parameters of the fluid at the ith breach through the thermal-hydraulic analysis program of the containment shell.

[0119] In some implementations, the processor 510 is further configured to:

[0120] Based on the kth time step, the containment thermal parameters of the reactor are calculated according to the thermal parameters of the fluid at the i-th breach of the reactor by the containment thermal-hydraulic analysis program to obtain the containment thermal parameters corresponding to the kth time step;

[0121] When the containment thermal parameters corresponding to the k-th time step converge, comparing the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation with the i-th breach thermal-hydraulic analysis time step;

[0122] When the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step, the containment thermal parameters corresponding to the k-th time step are determined as the i-th containment thermal parameters of the reactor, wherein the i-th breach thermal-hydraulic analysis time step is the k-th time step;

[0123] In the case that the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is less than the i-th breach thermal-hydraulic analysis time step, the process returns to execution based on the k-th time step, and the containment thermal-hydraulic analysis program calculates the containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach of the reactor, until the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step.

[0124] In some implementations, the processor 510 is further configured to:

[0125] In the case where the thermal parameters of the containment corresponding to the k-th time step do not converge, the k-th time step is updated to the k+1-th time step, and the execution is returned to calculate the thermal parameters of the containment of the reactor according to the thermal parameters of the fluid at the i-th breach of the reactor based on the k-th time step through the containment thermal-hydraulic analysis program until the thermal parameters of the containment corresponding to the k-th time step converge; wherein the k+1-th time step is smaller than the k-th time step, and k is a positive integer.

[0126] It should be understood that in the embodiment of the present application, the input unit 504 may include a graphics processor (GPU) 5041 and a microphone 5042, and the graphics processor 5041 processes the image data of a static picture or video obtained by an image capture device (such as a camera) in a video capture mode or an image capture mode. The display unit 506 may include a display panel 5061, and the display panel 5061 may be configured in the form of a liquid crystal display, an organic light emitting diode, etc. The user input unit 507 includes a touch panel 5071 and at least one of other input devices 5072. The touch panel 5071 is also called a touch screen. The touch panel 5071 may include two parts: a touch detection device and a touch controller. Other input devices 5072 may include, but are not limited to, a physical keyboard, function keys (such as a volume control button, a switch button, etc.), a trackball, a mouse, and a joystick, which will not be repeated here.

[0127] The memory 509 can be used to store software programs and various data. The memory 509 may mainly include a first storage area for storing programs or instructions and a second storage area for storing data, wherein the first storage area may store an operating device, an application program or instructions required for at least one function (such as a sound playback function, an image playback function, etc.), etc. In addition, the memory 509 may include a volatile memory or a non-volatile memory, or the memory 509 may include both volatile and non-volatile memories. Among them, the non-volatile memory may be a read-only memory (ROM), a programmable read-only memory (PROM), an erasable programmable read-only memory (EPROM), an electrically erasable programmable read-only memory (EEPROM), or a flash memory. The volatile memory may be a random access memory (RAM), a static random access memory (SRAM), a dynamic random access memory (DRAM), a synchronous dynamic random access memory (SDRAM), a double data rate synchronous dynamic random access memory (DDRSDRAM), an enhanced synchronous dynamic random access memory (ESDRAM), a synchronous link dynamic random access memory (SLDRAM) and a direct memory bus random access memory (DRRAM). The memory 509 in the embodiment of the present application includes but is not limited to these and any other suitable types of memory.

[0128] The processor 510 may include one or more processing units; optionally, the processor 510 integrates an application processor and a modem processor, wherein the application processor mainly processes operations related to the operating device, the user interface, and the application program, and the modem processor mainly processes wireless communication signals, such as a baseband processor. It is understandable that the modem processor may not be integrated into the processor 510.

[0129] An embodiment of the present application also provides a readable storage medium, on which a program or instruction is stored. When the program or instruction is executed by a processor, each process of the thermal-hydraulic analysis embodiment of the above-mentioned reactor is implemented, and the same technical effect can be achieved. To avoid repetition, it will not be repeated here.

[0130] The processor is the processor in the electronic device described in the above embodiment. The readable storage medium includes a computer readable storage medium, such as a computer read-only memory ROM, a random access memory RAM, a magnetic disk or an optical disk.

[0131] In addition, an embodiment of the present application provides a computer program product, which is stored in a storage medium. The program product is executed by at least one processor to implement the various processes of the thermal-hydraulic analysis embodiment of the reactor as described above, and can achieve the same technical effect. To avoid repetition, it will not be repeated here.

[0132] It should be noted that, in this article, the terms "comprise", "include" or any other variant thereof are intended to cover non-exclusive inclusion, so that the process, method, article or device including a series of elements includes not only those elements, but also includes other elements not explicitly listed, or also includes elements inherent to such process, method, article or device. In the absence of further restrictions, the elements defined by the sentence "comprise one..." do not exclude the presence of other identical elements in the process, method, article or device including the element. In addition, it should be pointed out that the scope of the methods and devices in the embodiments of the present application is not limited to performing functions in the order shown or discussed, and may also include performing functions in a substantially simultaneous manner or in reverse order according to the functions involved, for example, the described method may be performed in an order different from that described, and various steps may also be added, omitted, or combined. In addition, the features described with reference to certain examples may be combined in other examples.

[0133] The serial numbers of the above embodiments of the present invention are only for description and do not represent the advantages or disadvantages of the embodiments.

[0134] Through the description of the above implementation methods, those skilled in the art can clearly understand that the above-mentioned embodiment methods can be implemented by means of software plus a necessary general hardware platform, and of course by hardware, but in many cases the former is a better implementation method. Based on such an understanding, the technical solution of the present invention is essentially or the part that contributes to the prior art can be embodied in the form of a software product, which is stored in a storage medium (such as ROM / RAM, magnetic disk, optical disk) as described above, and includes a number of instructions for a terminal device (which can be a mobile phone, a computer, a server, or a network device, etc.) to execute the methods described in each embodiment of the present invention.

[0135] The embodiments of the present application are described above in conjunction with the accompanying drawings, but the present application is not limited to the above-mentioned specific implementation methods. The above-mentioned specific implementation methods are merely illustrative and not restrictive. Under the guidance of the present application, ordinary technicians in this field can also make many forms without departing from the purpose of the present application and the scope of protection of the claims, all of which are within the protection of the present application.

Claims

1. A thermal hydraulic analysis method for a reactor, characterized in that: include: In the event of a breach accident in the reactor, a thermal-hydraulic analysis task of the reactor is performed through a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program; The thermal hydraulic analysis task includes at least one thermal hydraulic analysis operation; When performing the i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task, the i-th rupture fluid thermal parameters of the reactor are determined according to the i-1th containment thermal parameters of the reactor through the thermal-hydraulic system analysis program; wherein the i-th rupture fluid thermal parameters are converged rupture fluid thermal parameters determined based on the i-th rupture thermal-hydraulic analysis time step; i is a positive integer, and when i is equal to 1, the i-1th containment thermal parameters are steady-state containment thermal parameters of the reactor; Determine the i-th containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach through the containment thermal-hydraulic analysis program; wherein the i-th containment thermal parameters are converged containment thermal parameters determined based on at least one i-th containment thermal-hydraulic analysis time step; each of the i-th containment thermal-hydraulic analysis time steps is less than or equal to the i-th breach thermal-hydraulic analysis time step, and the sum of the at least one i-th containment thermal-hydraulic analysis time step is equal to the i-th breach thermal-hydraulic analysis time step; After performing the i-th thermal-hydraulic analysis operation, determining a current total analysis time of the thermal-hydraulic system analysis program; When the current total analysis duration is greater than or equal to the preset duration, the execution of the thermal-hydraulic analysis task is terminated, and the result of the thermal-hydraulic analysis operation last executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program is determined as the thermal-hydraulic analysis result of the reactor.

2. The thermal hydraulic analysis method for a reactor according to claim 1, characterized in that: After performing the i-th thermal hydraulic analysis operation and determining the current total analysis time of the thermal hydraulic system analysis program, the method further comprises: When the current total analysis duration is less than the preset duration, i is updated to i+1, and the process returns to execute the i-th thermal-hydraulic analysis operation.

3. The thermal hydraulic analysis method of a reactor according to claim 1, characterized in that: The step of determining the thermal parameters of the fluid at the i-th breach of the reactor according to the i-1th containment thermal parameters of the reactor by the thermal hydraulic system analysis program includes: Based on the jth time step, the thermal parameters of the fluid at the breach of the reactor are calculated according to the thermal parameters of the i-1th containment of the reactor by the thermal hydraulic system analysis program to obtain the thermal parameters of the fluid at the breach corresponding to the jth time step; When the thermal parameters of the fluid at the breach corresponding to the j-th time step converge, the thermal parameters of the fluid at the breach corresponding to the j-th time step are determined as the thermal parameters of the fluid at the i-th breach of the reactor; wherein the time step of the thermal-hydraulic analysis of the i-th breach is the j-th time step; When the fluid thermal parameters at the rupture corresponding to the j-th time step do not converge, the j-th time step is updated to the j+1-th time step, and the execution is returned to calculate the fluid thermal parameters at the rupture of the reactor based on the j-th time step through the thermal-hydraulic system analysis program according to the i-1-th containment thermal parameters of the reactor, until the fluid thermal parameters at the rupture corresponding to the j-th time step converge; wherein the j+1-th time step is less than the j-th time step, and j is a positive integer.

4. The thermal hydraulic analysis method of a reactor according to claim 1, characterized in that: The step of determining the i-th containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach by the containment thermal-hydraulic analysis program comprises: Obtaining an initial containment thermal-hydraulic analysis time step of the containment thermal-hydraulic analysis program; According to the comparison result of the initial containment thermal-hydraulic analysis time step and the i-th breach thermal-hydraulic analysis time step, the k-th time step is determined; wherein, when the initial containment thermal-hydraulic analysis time step is greater than the i-th breach thermal-hydraulic analysis time step, the k-th time step is the i-th breach thermal-hydraulic analysis time step; when the time step of the initial containment thermal-hydraulic analysis time step is less than or equal to the i-th breach thermal-hydraulic analysis time step, the k-th time step is the initial containment thermal-hydraulic analysis time step; k is a positive integer; Based on the kth time step, the thermal parameters of the ith containment shell of the reactor are determined according to the thermal parameters of the fluid at the ith breach through the thermal-hydraulic analysis program of the containment shell.

5. The thermal hydraulic analysis method of a reactor according to claim 4, characterized in that: The method of determining the i-th containment thermal parameters of the reactor based on the k-th time step and according to the thermal parameters of the fluid at the i-th breach through the containment thermal-hydraulic analysis program comprises: Based on the kth time step, the containment thermal parameters of the reactor are calculated according to the thermal parameters of the fluid at the i-th breach of the reactor by the containment thermal-hydraulic analysis program to obtain the containment thermal parameters corresponding to the kth time step; When the containment thermal parameters corresponding to the k-th time step converge, comparing the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation with the i-th breach thermal-hydraulic analysis time step; When the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step, the containment thermal parameters corresponding to the k-th time step are determined as the i-th containment thermal parameters of the reactor, wherein the i-th breach thermal-hydraulic analysis time step is the k-th time step; In the case that the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is less than the i-th breach thermal-hydraulic analysis time step, the process returns to execution based on the k-th time step, and the containment thermal-hydraulic analysis program calculates the containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach of the reactor, until the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th breach thermal-hydraulic analysis time step.

6. The method according to claim 5, characterized in that After calculating the containment thermal parameters of the reactor based on the kth time step by using the containment thermal-hydraulic analysis program according to the thermal parameters of the fluid at the i-th breach of the reactor, the method further comprises: In the case where the thermal parameters of the containment corresponding to the k-th time step do not converge, the k-th time step is updated to the k+1-th time step, and the execution is returned to calculate the thermal parameters of the containment of the reactor according to the thermal parameters of the fluid at the i-th breach of the reactor based on the k-th time step through the containment thermal-hydraulic analysis program until the thermal parameters of the containment corresponding to the k-th time step converge; wherein the k+1-th time step is smaller than the k-th time step, and k is a positive integer.

7. A thermal hydraulic analysis device for a reactor, characterized in that: The device comprises: A task module, in the event of a breach accident in the reactor, performs a thermal-hydraulic analysis task of the reactor through a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program; the thermal-hydraulic analysis task includes at least one thermal-hydraulic analysis operation; The thermal-hydraulic system analysis module determines the thermal parameters of the fluid at the ith breach of the reactor according to the thermal parameters of the i-1 containment of the reactor through the thermal-hydraulic system analysis program when performing the i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task; wherein the thermal parameters of the fluid at the ith breach are converged thermal parameters of the fluid at the breach determined based on the time step of the thermal-hydraulic analysis of the i-th breach; i is a positive integer, and when i is equal to 1, the i-1th containment thermal parameters are steady-state containment thermal parameters of the reactor; A containment thermal-hydraulic analysis module, which determines the i-th containment thermal parameters of the reactor according to the thermal parameters of the fluid at the i-th breach through the containment thermal-hydraulic analysis program; wherein the i-th containment thermal parameters are converged containment thermal parameters determined based on at least one i-th containment thermal-hydraulic analysis time step; each of the i-th containment thermal-hydraulic analysis time steps is less than or equal to the i-th breach thermal-hydraulic analysis time step, and the sum of the at least one i-th containment thermal-hydraulic analysis time step is equal to the i-th breach thermal-hydraulic analysis time step; A duration determination module, after executing the i-th thermal hydraulic analysis operation, determines the current total analysis duration of the thermal hydraulic system analysis program; A result determination module is provided for terminating the execution of the thermal-hydraulic analysis task when the current total analysis duration is greater than or equal to a preset duration, and determining the result of the thermal-hydraulic analysis operation last executed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program as the thermal-hydraulic analysis result of the reactor.

8. A thermal hydraulic analysis device for a reactor, characterized in that: The device comprises: a memory, a processor, and a computer processing program stored in the memory and executable on the processor, wherein the computer processing program is configured to implement the steps of the thermal-hydraulic analysis method for a reactor according to any one of claims 1 to 6.

9. A storage medium, characterized in that: The storage medium stores a computer processing program, and when the computer processing program is executed by a processor, the steps of the thermal-hydraulic analysis method for a reactor as claimed in any one of claims 1 to 6 are implemented.

10. A computer program product, characterized in that When the instructions in the computer program product are executed by a processor of an electronic device, the electronic device executes the steps of the thermal-hydraulic analysis method for a reactor as claimed in any one of claims 1 to 6.

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