Thermal-hydraulic analysis method and device for nuclear reactor

Abstract

The application discloses a thermal-hydraulic analysis method and device of a nuclear reactor, and belongs to the technical field of nuclear power plant design. The method comprises the following steps: when performing the i-th thermal-hydraulic analysis operation of a thermal-hydraulic analysis task, determining the i-th break fluid thermal parameter of the nuclear reactor according to the i-1st containment thermal parameter of the nuclear reactor by a thermal-hydraulic system analysis program; determining the i-th containment thermal parameter of the nuclear reactor according to the i-th break fluid thermal parameter by a containment thermal-hydraulic analysis program; in the case that the current total analysis time length of the thermal-hydraulic system analysis program is greater than or equal to a preset time length, ending the execution of the thermal-hydraulic analysis task, and determining the result of the thermal-hydraulic analysis operation performed 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 nuclear reactor. The application improves the accuracy of the calculation result of the thermal-hydraulic analysis method of the nuclear reactor.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear power plant design, in particular to a thermal-hydraulic analysis method and device of a nuclear reactor. BACKGROUND

[0002] The pressurized water reactor nuclear power plant is a widely used nuclear power generation technology, and its core components include a primary loop, a secondary loop, a containment and auxiliary equipment. In the primary loop, high-temperature and high-pressure water is heated by nuclear fuel, and then pushed by a main coolant pump to pass through a steam generator to transfer heat to the water in the secondary loop, so that the water becomes steam. Subsequently, the water in the primary loop returns to the nuclear reactor again to continue to take away the heat generated by the nuclear fuel. The steam in the secondary loop is used to drive a steam turbine generator to provide power. The main function of the containment is to ensure that the nuclear power plant can operate normally under internal and external risks, and to prevent radioactive substances from leaking into the environment or resisting external impact.

[0003] The main structure of the primary loop and the secondary loop is a small space and a pipeline, and the main flow medium is single-phase water or a steam-water mixture. The main structure of the containment is a large compartment or a large pool, and the main flow medium is air or single-phase water. In the traditional break accident analysis, different calculation models or programs are usually used to analyze the thermal-hydraulics of the primary loop, the secondary loop and the containment. Because the containment is large and the temperature and pressure change is small, the thermal-hydraulic system analysis program usually analyzes and calculates the containment as a constant temperature and pressure boundary. When analyzing the thermal-hydraulic state in the containment after the break using the thermal-hydraulic analysis program of the containment, the thermal parameters of the fluid at the break are usually used as the input of the thermal-hydraulic analysis program of the containment. When calculating the thermal-hydraulic parameters of the primary loop (nuclear reactor primary and secondary loops) using the thermal-hydraulic system analysis program, the boundary pressure and temperature of the containment at the break are used, which are lower than the actual values, resulting in inaccurate calculation of the mass and energy parameters at the break and the thermal-hydraulic parameters in the nuclear reactor. Due to the inaccuracy of the mass and energy parameters at the break, the temperature and pressure response parameters calculated by the thermal-hydraulic analysis program of the containment are also inaccurate. Therefore, the calculation results of the traditional thermal-hydraulic analysis method have low accuracy.

[0004] The above content is only used to assist in understanding the technical solutions of the present application and does not represent an acknowledgement that the above content is prior art. SUMMARY

[0005] The main purpose of the embodiments of the present application is to provide a thermal-hydraulic analysis method and device of a nuclear reactor, which aims to solve the problem of low accuracy of the thermal-hydraulic analysis of the nuclear reactor in the prior art.

[0006] In a first aspect, the embodiments of the present application provide a thermal-hydraulic analysis method of a nuclear reactor, which comprises:

[0007] In the case that the nuclear reactor has a break accident, a thermal-hydraulic analysis task of the nuclear reactor is performed by 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] In the i-th thermal-hydraulic analysis operation of performing the thermal-hydraulic analysis task, an i-th break fluid thermal parameter of the nuclear reactor is determined by the thermal-hydraulic system analysis program according to an i-1-th containment thermal parameter of the nuclear reactor; wherein the i-th break fluid thermal parameter is a converged break fluid thermal parameter determined based on an i-th break thermal-hydraulic analysis time step; i is a positive integer, and in the case that i is equal to 1, the i-1-th containment thermal parameter is a steady-state containment thermal parameter of the nuclear reactor;

[0009] An i-th containment thermal parameter of the nuclear reactor is determined by the containment thermal-hydraulic analysis program according to the i-th break fluid thermal parameter; wherein the i-th containment thermal parameter is a converged containment thermal parameter 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 break thermal-hydraulic analysis time step, and a sum of the at least one i-th containment thermal-hydraulic analysis time step is equal to the i-th break thermal-hydraulic analysis time step;

[0010] After the i-th thermal-hydraulic analysis operation is performed, a current total analysis time length of the thermal-hydraulic system analysis program is determined;

[0011] In the case that the current total analysis time length is greater than or equal to a preset time length, the execution of the thermal-hydraulic analysis task is ended, and a result of the thermal-hydraulic analysis operation performed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program last time is determined as a thermal-hydraulic analysis result of the nuclear reactor.

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

[0013] A task module, in the case that the nuclear reactor has a break accident, a thermal-hydraulic analysis task of the nuclear reactor is performed by 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] a thermal-hydraulic system analysis module, configured to determine, by the thermal-hydraulic system analysis program, an i-th break fluid thermal parameter of the nuclear reactor according to the (i-1)-th containment thermal parameter of the nuclear reactor when performing an i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task; wherein the i-th break fluid thermal parameter is a converged break fluid thermal parameter determined based on an i-th break thermal-hydraulic analysis time step; i is a positive integer, and when i equals 1, the (i-1)-th containment thermal parameter is a steady-state containment thermal parameter of the nuclear reactor;

[0015] a containment thermal-hydraulic analysis module, configured to determine, by the containment thermal-hydraulic analysis program, an i-th containment thermal parameter of the nuclear reactor according to the i-th break fluid thermal parameter; wherein the i-th containment thermal parameter is a converged containment thermal parameter 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 break thermal-hydraulic analysis time step, and a sum of the at least one i-th containment thermal-hydraulic analysis time step is equal to the i-th break thermal-hydraulic analysis time step;

[0016] a determination time length module, configured to determine a current total analysis time length of the thermal-hydraulic system analysis program after performing the i-th thermal-hydraulic analysis operation;

[0017] a determination result module, configured to end the execution of the thermal-hydraulic analysis task and determine a result of the thermal-hydraulic analysis operation performed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program last time as a thermal-hydraulic analysis result of the nuclear reactor when the current total analysis time length is greater than or equal to a preset time length.

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

[0019] In a fourth aspect, an embodiment of the present application provides a storage medium, the storage medium storing a computer processing program, the computer processing program being executable by a processor to implement the steps of the thermal-hydraulic analysis method of the nuclear reactor according to the first aspect.

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

[0021] The application provides a thermal-hydraulic analysis method and device for a nuclear reactor. In the case of a break accident of the nuclear reactor, the thermal-hydraulic analysis task of the nuclear reactor is performed by a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program. The thermal-hydraulic parameter of fluid at a break of the nuclear reactor is calculated by the thermal-hydraulic system analysis program, and is transmitted to the containment thermal-hydraulic analysis program as input. The containment thermal-hydraulic parameter of the nuclear reactor is calculated by the containment thermal-hydraulic analysis program. The thermal-hydraulic system analysis program performs analysis and calculation by using the containment thermal-hydraulic parameter. The cycle is repeated until a preset time is reached. Therefore, the parameters calculated by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program can be adjusted in a timely manner according to the actual situation, the real-time 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 is improved. In addition, in the parameter calculation process, the accuracy of the parameters is ensured by judging the convergence of the calculation results, adjusting the time step and performing multiple calculations, the accuracy of the thermal-hydraulic analysis method of the nuclear reactor is improved, and the safety analysis and evaluation of the main loop system and the containment system under the accident condition are realized. In addition, the containment thermal-hydraulic parameter of the nuclear reactor is calculated by the containment thermal-hydraulic analysis program to the same time step as the thermal-hydraulic system analysis program, the consistency of the parameter transmission time between the two programs is ensured, and the real-time and accuracy of the parameters are improved. BRIEF DESCRIPTION OF DRAWINGS

[0022] Figure 1 FIG. 1 is one of flow diagrams of the thermal-hydraulic analysis method for the nuclear reactor provided by the application;

[0023] Figure 2 FIG. 2 is another of flow diagrams of the thermal-hydraulic analysis method for the nuclear reactor provided by the application;

[0024] Figure 3 FIG. 3 is a structural diagram of the thermal-hydraulic analysis device for the nuclear reactor provided by the application;

[0025] Figure 4 FIG. 4 is one of structural diagrams of the electronic device provided by the application;

[0026] Figure 5 FIG. 5 is another of structural diagrams of the electronic device provided by the application;

[0027] The implementation, functional features and advantages of the application will be further described with reference to the embodiments and the accompanying drawings. DETAILED DESCRIPTION

[0028] With reference to the drawings and the embodiments of the present application, the technical solutions in the embodiments of the present application will be clearly described. Obviously, the described embodiments are only some of the embodiments of the present application, but not all of the embodiments of the present application. Based on the embodiments in the present application, all other embodiments obtained by those of ordinary skill in the art are within the scope of protection of the present application.

[0029] The terms "first", "second", and the like 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 interchanged under appropriate circumstances, so that the embodiments of the present application can be implemented in an order other than that illustrated or described herein, and the objects distinguished by "first", "second", etc. are generally a category, and are not limited to the number of objects, for example, the first object can be one or more. In addition, "and / or" in the specification and claims indicates at least one of the connected objects, and the character " / ", generally indicates that the objects before and after are in an "or" relationship.

[0030] The thermal-hydraulic analysis of the nuclear reactor provided by the embodiments of the present application will be described in detail below in combination with the drawings, through specific embodiments and application scenarios.

[0031] The thermal-hydraulic analysis method of the nuclear reactor provided by the embodiments of the present application can include the following steps: Figure 1 The thermal-hydraulic analysis method of the nuclear reactor provided by the embodiments of the present application can include the following steps:

[0032] Step 10, in the case of a break accident of the nuclear reactor, performing a thermal-hydraulic analysis task of the nuclear reactor by 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, in the i-th thermal-hydraulic analysis operation of performing the thermal-hydraulic analysis task, determining the i-th break fluid thermal parameter of the nuclear reactor according to the i-1-th containment thermal parameter of the nuclear reactor by the thermal-hydraulic system analysis program; wherein the i-th break fluid thermal parameter is a converged break fluid thermal parameter determined based on an i-th break thermal-hydraulic analysis time step; i is a positive integer, and in the case of i being equal to 1, the i-1-th containment thermal parameter is a steady-state containment thermal parameter of the nuclear reactor;

[0034] Step 30, determining the i-th containment thermal-hydraulic parameter of the nuclear reactor according to the i-th fluid thermal-hydraulic parameter at the break by the containment thermal-hydraulic analysis program; wherein the i-th containment thermal-hydraulic parameter is a converged containment thermal-hydraulic parameter determined based on at least one i-th containment thermal-hydraulic analysis time step; each of the i-th containment thermal-hydraulic analysis time step is less than or equal to the i-th break 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 break thermal-hydraulic analysis time step;

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

[0036] Step 50, in the case where the current total analysis time length is greater than or equal to the preset time length, ending the execution of the thermal-hydraulic analysis task, and determining the result of the thermal-hydraulic analysis operation last performed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program as the thermal-hydraulic analysis result of the nuclear reactor.

[0037] The embodiment of the present application performs the thermal-hydraulic analysis task of the nuclear reactor by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program in the case where the nuclear reactor has a break accident, calculates the break fluid thermal-hydraulic parameter of the nuclear reactor by the thermal-hydraulic system analysis program, and transmits it to the containment thermal-hydraulic analysis program as input, calculates the containment thermal-hydraulic parameter of the nuclear reactor by the containment thermal-hydraulic analysis program, and the thermal-hydraulic system analysis program uses the containment thermal-hydraulic parameter for analysis and calculation, and so on, and ends after a preset time. 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 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 is improved. In addition, in the parameter calculation process, the accuracy of the parameters is ensured by the judgment of the convergence of the calculation result, the adjustment of the time step and the multiple calculations, the accuracy of the thermal-hydraulic analysis method of the nuclear reactor is improved, and thus the safety analysis and evaluation of the primary loop system and the containment system under the accident condition are realized. In addition, the containment thermal-hydraulic analysis program is used to calculate the containment thermal-hydraulic parameter of the nuclear reactor to the same time step as the thermal-hydraulic system analysis program, which can ensure the consistency of the parameter transmission time between the two programs, and thus the real-time and accuracy of the parameters are improved.

[0038] In some embodiments, in step 10 above, first, in the case of a break accident of the nuclear reactor, a task of thermal-hydraulic analysis of the nuclear reactor by a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program, the task including at least one thermal-hydraulic analysis operation.

[0039] In the present embodiment, it should be noted that the thermal-hydraulic analysis can be an analysis and calculation of heat transfer and fluid flow processes in the nuclear reactor, and can be an analysis and calculation of time-varying thermal-hydraulic parameters of the primary loop system and the containment system. The thermal-hydraulic system analysis program can be a program or software responsive to thermal-hydraulic analysis of the primary loop of the nuclear reactor. The containment thermal-hydraulic analysis program can be a program or software responsive to thermal-hydraulic analysis inside the containment.

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

[0041] In some embodiments, in step 20 above, in each thermal-hydraulic analysis operation, the thermal-hydraulic system analysis program determines the fluid thermal-hydraulic parameters at the current break according to the previous (i-1) containment thermal-hydraulic parameters, which are the convergence parameters determined based on the current break thermal-hydraulic analysis time step. If it is the first thermal-hydraulic analysis operation, the thermal-hydraulic system analysis program determines the fluid thermal-hydraulic parameters at the current break according to the steady-state containment thermal-hydraulic parameters of the nuclear reactor collected. The steady-state containment thermal-hydraulic parameters are parameters of the containment in a normal operating state without an accident, which can be obtained by modeling the nuclear reactor according to various parameters and running the containment thermal-hydraulic analysis program for a period of time.

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

[0043] In some embodiments, in step 30, in each thermal-hydraulic analysis operation, the containment thermal-hydraulic analysis program determines the current containment thermal-hydraulic parameter of the nuclear reactor according to the fluid thermal-hydraulic parameter at the current break. The fluid thermal-hydraulic parameter at the current break is a converged parameter determined based on the current break thermal-hydraulic analysis time step. The current containment thermal-hydraulic parameter of the nuclear reactor is a converged containment thermal-hydraulic parameter 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 break thermal-hydraulic analysis time step, and the sum of the at least one current containment thermal-hydraulic analysis time step is equal to the current break 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 step 40, after each execution of the thermal-hydraulic analysis operation, the current total analysis time length of the thermal-hydraulic system analysis program can be determined. The current total analysis time length is the cumulative value of each break thermal-hydraulic analysis time step of the thermal-hydraulic system analysis program.

[0045] In some embodiments, in step 50, the current total analysis time length and the preset time length are compared. When the current total analysis time length is greater than or equal to the preset time length, the thermal-hydraulic analysis task is no longer executed. The results of the last execution of the thermal-hydraulic analysis operation of the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program are taken as the thermal-hydraulic analysis results of the nuclear reactor.

[0046] In some embodiments, after the execution of the i-th thermal-hydraulic analysis operation and the determination of the current total analysis time length of the thermal-hydraulic system analysis program, the following steps are included:

[0047] When the current total analysis time length is less than the preset time length, i is updated to i+1, and the i-th thermal-hydraulic analysis operation is executed again.

[0048] In the present embodiment, the current total analysis duration is compared with the preset duration, and when the current total analysis duration is less than the preset duration, the next thermal-hydraulic analysis operation is continued. By checking the total analysis duration after each thermal-hydraulic analysis operation, it can be ensured that the analysis process continues as necessary until the preset analysis duration is reached, which allows for a more detailed simulation and prediction of the thermal-hydraulic behavior during an accident. The iterative process described above allows the program to refine the analysis results in each iteration, and through multiple iterations, the accuracy and reliability of the thermal-hydraulic analysis can be gradually improved. At the same time, the present embodiment allows the analysis to continue until the preset duration is reached, rather than a fixed number of iterations, which means that the analysis can adapt to the complexity and required detail in different situations, providing flexibility. By ending the iterations when the preset duration is reached, unnecessary calculations can be avoided, thereby optimizing the use of computing resources.

[0049] In the present embodiment, it should be noted that the preset duration can be a pre-set calculation end duration.

[0050] In some embodiments, the determination of the i-th break fluid thermal-hydraulic parameter of the nuclear reactor by the thermal-hydraulic system analysis program based on the i-1-th containment thermal-hydraulic parameter of the nuclear reactor includes:

[0051] Based on the j-th time step, the thermal-hydraulic system analysis program calculates the break fluid thermal-hydraulic parameter of the nuclear reactor based on the i-1-th containment thermal-hydraulic parameter of the nuclear reactor to obtain the j-th time step corresponding break fluid thermal-hydraulic parameter;

[0052] In the case where the j-th time step corresponding break fluid thermal-hydraulic parameter converges, the j-th time step corresponding break fluid thermal-hydraulic parameter is determined as the i-th break fluid thermal-hydraulic parameter of the nuclear reactor; wherein the i-th break thermal-hydraulic analysis time step is the j-th time step;

[0053] In the case where the j-th time step corresponding break fluid thermal-hydraulic parameter does not converge, the j-th time step is updated to the j+1-th time step, and the process of calculating the break fluid thermal-hydraulic parameter of the nuclear reactor based on the j-th time step by the thermal-hydraulic system analysis program based on the i-1-th containment thermal-hydraulic parameter of the nuclear reactor is returned to be executed until the j-th time step corresponding break fluid thermal-hydraulic parameter converges; wherein the j+1-th time step is less than the j-th time step, and j is a positive integer.

[0054] In the embodiment, in the jth time step, the thermal-hydraulic system analysis program is used to calculate the thermal-hydraulic parameters of the fluid at the breach according to the i-1th containment thermal-hydraulic parameters of the nuclear reactor. It is checked whether the thermal-hydraulic parameters of the fluid at the breach calculated in the jth time step have converged. If the parameters converge, the thermal-hydraulic parameters of the fluid at the breach calculated in the jth time step are determined as the i th thermal-hydraulic parameters of the fluid at the breach, and this time step is taken as the time step of the i th breach thermal-hydraulic analysis. If the parameters do not converge, the time step is updated to a smaller j+1th time step, and then the calculation process is repeated until the parameters converge. Through iterative calculation until convergence, the accuracy of the calculation of the thermal-hydraulic parameters of the fluid at the breach can be improved, the stability of the parameters can be improved, and the thermal-hydraulic analysis can be facilitated, and appropriate measures can be taken to solve the nuclear reactor accident. By gradually reducing the time step until convergence, the calculation resources can be used more effectively, and unnecessary calculation can be avoided.

[0055] In the embodiment, it should be noted that the time step can be a time period used for iterative calculation in numerical simulation, and the parameter change in each time step is calculated and analyzed. The jth time step can be the initial breach thermal-hydraulic analysis time step, and the initial breach thermal-hydraulic analysis time steps of each thermal-hydraulic analysis operation can be equal or not equal. Convergence can be referred to as convergence in numerical analysis when the results of continuous iterations change very little or tend to be stable.

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

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

[0058] determining a kth time step according to a comparison result of the initial containment thermal-hydraulic analysis time step and the i th breach thermal-hydraulic analysis time step; wherein, in the case that the initial containment thermal-hydraulic analysis time step is greater than the i th breach thermal-hydraulic analysis time step, the kth time step is the i th breach thermal-hydraulic analysis time step; in the case that the initial containment thermal-hydraulic analysis time step is less than or equal to the i th breach thermal-hydraulic analysis time step, the kth time step is the initial containment thermal-hydraulic analysis time step; k is a positive integer;

[0059] determining the i th containment thermal-hydraulic parameters of the nuclear reactor according to the i th thermal-hydraulic parameters of the fluid at the breach by the containment thermal-hydraulic analysis program based on the kth time step.

[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 break thermal-hydraulic analysis time step. If the initial time step is greater than the i-th break thermal-hydraulic analysis time step, the k-th time step adopts the i-th break thermal-hydraulic analysis time step. If the initial time step is less than or equal to the break thermal-hydraulic analysis time step, the k-th time step adopts the initial containment thermal-hydraulic analysis time step. Using the determined k-th time step, the i-th containment thermal-hydraulic parameter of the nuclear reactor is calculated according to the i-th break fluid thermal-hydraulic parameter by the containment thermal-hydraulic analysis program. In this way, by selecting a suitable time step, the calculation efficiency can be improved. Secondly, the analysis program is allowed to adjust the time step according to the actual situation to adapt to different analysis needs, providing flexibility. By accurately calculating the thermal-hydraulic parameters of the containment, scientific basis is provided for the management and mitigation of accidents, which can better predict and control the development of accidents, thereby improving the safety of the nuclear reactor.

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

[0062] In some embodiments, the above determination of the i-th containment thermal-hydraulic parameter of the nuclear reactor based on the k-th time step and the i-th break fluid thermal-hydraulic parameter by the containment thermal-hydraulic analysis program includes:

[0063] Based on the k-th time step, the containment thermal-hydraulic parameter of the nuclear reactor is calculated by the containment thermal-hydraulic analysis program according to the i-th break fluid thermal-hydraulic parameter of the nuclear reactor, to obtain the containment thermal-hydraulic parameter corresponding to the k-th time step;

[0064] In the case where the containment thermal-hydraulic parameter corresponding to the k-th time step converges, the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is compared with the i-th break thermal-hydraulic analysis time step;

[0065] In the case where 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 break thermal-hydraulic analysis time step, the containment thermal-hydraulic parameter corresponding to the k-th time step is determined as the i-th containment thermal-hydraulic parameter of the nuclear reactor, wherein the i-th break 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 break thermal-hydraulic analysis time step, return to perform the calculation of the containment thermal-hydraulic parameters of the nuclear reactor at the k-th time step based on the i-th break fluid thermal-hydraulic parameters of the nuclear reactor by the containment thermal-hydraulic analysis program 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 break thermal-hydraulic analysis time step.

[0067] In the present embodiment, the containment thermal-hydraulic parameters at the k-th time step are calculated based on the i-th break fluid thermal-hydraulic parameters by the containment thermal-hydraulic analysis program. It is checked whether the calculated containment thermal-hydraulic parameters at the k-th time step have converged. If the parameters have converged, the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is compared with the i-th break 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 break thermal-hydraulic analysis time step, the containment thermal-hydraulic parameters at the k-th time step are determined as the i-th containment thermal-hydraulic parameters of the nuclear 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 break thermal-hydraulic analysis time step, the calculation based on the k-th time step is continued 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 break thermal-hydraulic analysis time step. Through iterative calculation until convergence, the calculation accuracy of the containment thermal-hydraulic parameters is ensured. At the same time, the present embodiment provides a reliable method to evaluate the thermal-hydraulic state of the nuclear reactor in a break accident, which enhances the reliability of the accident analysis. By precisely controlling the time step, the use of calculation resources is optimized, and unnecessary calculation is avoided. In addition, determining the i-th containment thermal-hydraulic parameters of the nuclear reactor provides detailed information about the progress of the accident for operators and decision makers, which helps to develop effective coping strategies.

[0068] In some implementations, in the case that the containment thermal-hydraulic parameters at the k-th time step have converged, 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 break 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 break thermal-hydraulic analysis time step.

[0069] In some embodiments, in the case that the containment thermal-hydraulic parameters corresponding to the k-th time step do not converge, the k-th time step is updated to a k+1-th time step, and the method returns to performing the calculation of the containment thermal-hydraulic parameters of the nuclear reactor based on the k+1-th time step, by the containment thermal-hydraulic analysis program according to the fluid thermal-hydraulic parameters at the i-th break of the nuclear reactor, until the containment thermal-hydraulic parameters corresponding to the k+1-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.

[0070] In some embodiments, after the calculation of the containment thermal-hydraulic parameters of the nuclear reactor based on the k-th time step, by the containment thermal-hydraulic analysis program according to the fluid thermal-hydraulic parameters at the i-th break of the nuclear reactor, the method further comprises:

[0071] In the case that the containment thermal-hydraulic parameters corresponding to the k-th time step do not converge, the k-th time step is updated to a k+1-th time step, and the method returns to performing the calculation of the containment thermal-hydraulic parameters of the nuclear reactor based on the k+1-th time step, by the containment thermal-hydraulic analysis program according to the fluid thermal-hydraulic parameters at the i-th break of the nuclear reactor, until the containment thermal-hydraulic parameters corresponding to the k+1-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 the present embodiment, the containment thermal-hydraulic analysis program is used to calculate the containment thermal-hydraulic parameters corresponding to the k-th time step according to the i-th break fluid thermal-hydraulic parameters. It is determined whether the calculated containment thermal-hydraulic parameters at the k-th time step converge. If the parameters do not converge, the k-th time step is updated to a smaller k+1-th time step. The calculation based on the updated time step is returned and performed again until the containment thermal-hydraulic parameters converge. When the containment thermal-hydraulic parameters corresponding to the k-th time step converge, the iteration is ended. In this way, through iteration until convergence, high precision of the containment thermal-hydraulic parameter calculation 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 containment thermal-hydraulic parameters provide precise thermal-hydraulic parameters for operators and decision makers, helping them better understand the progress of the accident and develop response strategies.

[0073] It should be noted that the various embodiments, embodiments and implementation modes provided by the embodiments of the present application can be independently implemented, or can be combined for implementation without conflict with each other. The specific implementation can be determined according to actual needs, and the embodiments of the present application do not limit this.

[0074] For easy understanding, please refer to Figure 2 , Figure 2 is another flowchart of an embodiment of the thermal-hydraulic analysis method of the nuclear reactor provided by the present application.

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

[0076] 2) The thermal-hydraulic system analysis program starts transient calculation based on time step dt, and adjusts the time step according to the convergence of the thermal-hydraulic system analysis program during the calculation until the calculation result converges.

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

[0078] 4) The containment thermal-hydraulic analysis program is executed, and 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 is based on the time step dt' to carry out the calculation of the containment thermal-hydraulic system, and the response parameters such as the pressure and temperature in the containment are obtained, and 6) is executed.

[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), the time step of the containment thermal-hydraulic analysis program is reduced to the time step of the thermal-hydraulic system analysis program, and then the calculation is started, and the response parameters such as the pressure and temperature in the containment are obtained, and 6) is executed.

[0080] 6) If the calculation result of the containment thermal-hydraulic analysis program converges, the calculation of the containment thermal-hydraulic analysis program is carried out to the time point of the thermal-hydraulic system analysis program, and 7) is executed.

[0081] 7) If the calculation result of the containment thermal-hydraulic analysis program does not converge, the time step of the containment thermal-hydraulic module is reduced, and the calculation is returned and re-calculated to the time point of the thermal-hydraulic system analysis program, and 8) is executed.

[0082] 8) The response parameters such as the pressure and temperature in the containment are transmitted to the thermal-hydraulic system analysis program;

[0083] 9) If the calculation time (the current total analysis time) is less than the end time Tend (T

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

[0085] 11) The thermal-hydraulic system analysis program enters the next time step based on the pressure, temperature and other response parameters fed back by the containment thermal-hydraulic analysis program at the current time to carry out the calculation.

[0086] 12) The relevant parameters of the nuclear reactor break pipe at the next time calculated by the thermal-hydraulic system analysis program are transmitted to the containment thermal-hydraulic analysis program;

[0087] 13) perform the containment thermal-hydraulic calculation to obtain the response parameters such as containment internal pressure, temperature, etc;

[0088] 14) transfer the response parameters such as containment internal pressure, temperature, etc to the thermal-hydraulic system analysis program;

[0089] 15) the thermal-hydraulic system analysis program performs data transfer with the containment thermal-hydraulic calculation once per time step;

[0090] 16) repeat steps 1)~15).

[0091] With reference to Figure 3 In one embodiment of the present application, a thermal-hydraulic analysis device for a nuclear reactor is provided, the device comprising:

[0092] a task module 301 configured to perform a thermal-hydraulic analysis task for the nuclear reactor by a thermal-hydraulic system analysis program and a containment thermal-hydraulic analysis program in the case of a break accident of the nuclear reactor; the thermal-hydraulic analysis task comprising at least one thermal-hydraulic analysis operation;

[0093] a thermal-hydraulic system analysis module 302 configured to determine an ith break fluid thermal parameter of the nuclear reactor by the thermal-hydraulic system analysis program according to an (i-1)th containment thermal parameter of the nuclear reactor in an ith thermal-hydraulic analysis operation of performing the thermal-hydraulic analysis task; wherein the ith break fluid thermal parameter is a converged break fluid thermal parameter determined based on an ith break thermal-hydraulic analysis time step; i is a positive integer, and in the case of i being equal to 1, the (i-1)th containment thermal parameter is a steady-state containment thermal parameter of the nuclear reactor;

[0094] a containment thermal-hydraulic analysis module 303 configured to determine an ith containment thermal parameter of the nuclear reactor by the containment thermal-hydraulic analysis program according to the ith break fluid thermal parameter; wherein the ith containment thermal parameter is a converged containment thermal parameter determined based on at least one ith containment thermal-hydraulic analysis time step; each of the ith containment thermal-hydraulic analysis time steps is less than or equal to the ith break 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 break thermal-hydraulic analysis time step;

[0095] a determination time length module 304 configured to determine a current total analysis time length of the thermal-hydraulic system analysis program after performing the ith thermal-hydraulic analysis operation;

[0096] The determining result module 305 ends the execution of the thermal-hydraulic analysis task when the current total analysis time length is greater than or equal to the preset time length, and determines the result of the thermal-hydraulic analysis operation of the last execution of the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program as the thermal-hydraulic analysis result of the nuclear reactor.

[0097] It should be noted that the device embodiment and the method embodiment described above are based on the same inventive concept,

[0098] Therefore, the content of the method embodiment described above is also applicable to the device embodiment, and will not be described here again.

[0099] Optionally, as Figure 4 shown, the present application embodiment further provides an electronic device 400, comprising a processor 401 and a memory 402, the memory 402 stores programs or instructions executable on the processor 401, the programs or instructions are executed by the processor 401 to realize the steps of the above-mentioned thermal-hydraulic analysis method for nuclear reactors Embodiments of the application, and can achieve the same technical effects. To avoid repetition, this will not be described here again.

[0100] It should be noted that the electronic device in the present application embodiment includes the mobile electronic device and the non-mobile electronic device described above.

[0101] Figure 5 To realize the hardware structure of the electronic device of the present application embodiment.

[0102] 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 and the like. Component.

[0103] Those skilled in the art can understand that the electronic device 500 can also include a power supply (such as a battery) for powering each component, and the power supply can be logically connected to the processor 510 through a power management device, so as to realize the functions of 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, and the electronic device can include more or fewer components than the figure, or combine certain components, or different component arrangements, which will not be described here again.

[0104] The processor 510 is configured to:

[0105] In the case that a break accident occurs in the nuclear reactor, a thermal-hydraulic analysis task of the nuclear reactor is performed by 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;

[0106] In the i th thermal-hydraulic analysis operation of performing the thermal-hydraulic analysis task, the i th break fluid thermal parameter of the nuclear reactor is determined by the thermal-hydraulic system analysis program according to the i-1 th containment thermal parameter of the nuclear reactor; wherein the i th break fluid thermal parameter is a converged break fluid thermal parameter determined based on an i th break thermal-hydraulic analysis time step; i is a positive integer, and in the case that i is equal to 1, the i-1 th containment thermal parameter is a steady-state containment thermal parameter of the nuclear reactor;

[0107] The i th containment thermal parameter of the nuclear reactor is determined by the containment thermal-hydraulic analysis program according to the i th break fluid thermal parameter; wherein the i th containment thermal parameter is a converged containment thermal parameter 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 break 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 break thermal-hydraulic analysis time step;

[0108] After the i th thermal-hydraulic analysis operation is performed, a current total analysis duration of the thermal-hydraulic system analysis program is determined;

[0109] In the case that the current total analysis duration is greater than or equal to a preset duration, the execution of the thermal-hydraulic analysis task is ended, and the result of the thermal-hydraulic analysis operation last performed by the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program is determined as a thermal-hydraulic analysis result of the nuclear reactor.

[0110] In some embodiments, the processor 510 is further configured to:

[0111] In the case that the current total analysis duration is less than the preset duration, i is updated to i+1, and the i th thermal-hydraulic analysis operation is performed again.

[0112] In some embodiments, the processor 510 is further configured to:

[0113] Based on the j th time step, the break fluid thermal parameter of the nuclear reactor is calculated by the thermal-hydraulic system analysis program according to the i-1 th containment thermal parameter of the nuclear reactor, to obtain a break fluid thermal parameter corresponding to the j th time step;

[0114] in a case that the fluid thermal parameter at the breach corresponding to the jth time step converges, determining the fluid thermal parameter at the breach of the nuclear reactor corresponding to the jth time step as the ith fluid thermal parameter at the breach of the nuclear reactor; wherein the ith time step of the breach thermal-hydraulic analysis is the jth time step;

[0115] in a case that the fluid thermal parameter at the breach corresponding to the jth time step does not converge, updating the jth time step to a (j+1)th time step, and returning to performing the calculation of the fluid thermal parameter at the breach of the nuclear reactor according to the (i-1)th containment thermal parameter of the nuclear reactor by the thermal-hydraulic system analysis program based on the jth time step until the fluid thermal parameter at the breach corresponding to the jth time step converges; wherein the (j+1)th time step is less than the jth time step, and j is a positive integer.

[0116] In some embodiments, the processor 510 is further configured to:

[0117] obtain an initial time step of the containment thermal-hydraulic analysis of the containment thermal-hydraulic analysis program;

[0118] determine a kth time step according to a comparison result of the initial time step of the containment thermal-hydraulic analysis and the ith time step of the breach thermal-hydraulic analysis; wherein in a case that the initial time step of the containment thermal-hydraulic analysis is greater than the ith time step of the breach thermal-hydraulic analysis, the kth time step is the ith time step of the breach thermal-hydraulic analysis; in a case that the initial time step of the containment thermal-hydraulic analysis is less than or equal to the ith time step of the breach thermal-hydraulic analysis, the kth time step is the initial time step of the containment thermal-hydraulic analysis; and k is a positive integer;

[0119] determine the ith containment thermal parameter of the nuclear reactor according to the ith fluid thermal parameter at the breach of the nuclear reactor by the containment thermal-hydraulic analysis program based on the kth time step.

[0120] In some embodiments, the processor 510 is further configured to:

[0121] obtain an initial time step of the containment thermal-hydraulic analysis of the containment thermal-hydraulic analysis program;

[0122] in a case that the containment thermal parameter corresponding to the kth time step converges, comparing a total calculation time step of the containment thermal-hydraulic analysis program in the ith thermal-hydraulic analysis operation and the ith time step of the breach thermal-hydraulic analysis;

[0123] in a case where the total calculation time step length of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th break thermal-hydraulic analysis time step length, determining the containment thermal-hydraulic parameter corresponding to the k-th time step length as the i-th containment thermal-hydraulic parameter of the nuclear reactor, wherein the i-th break thermal-hydraulic analysis time step length is the k-th time step length;

[0124] in a case where the total calculation time step length of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is less than the i-th break thermal-hydraulic analysis time step length, returning to perform the step of calculating, based on the k-th time step length, the containment thermal-hydraulic parameter of the nuclear reactor by the containment thermal-hydraulic analysis program according to the i-th break fluid thermal-hydraulic parameter of the nuclear reactor until the total calculation time step length of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is equal to the i-th break thermal-hydraulic analysis time step length.

[0125] In some embodiments, the processor 510 is further configured to:

[0126] in a case where the containment thermal-hydraulic parameter corresponding to the k-th time step length does not converge, updating the k-th time step length as a (k+1)-th time step length, and returning to perform the step of calculating, based on the k-th time step length, the containment thermal-hydraulic parameter of the nuclear reactor by the containment thermal-hydraulic analysis program according to the i-th break fluid thermal-hydraulic parameter of the nuclear reactor until the containment thermal-hydraulic parameter corresponding to the k-th time step length converges; wherein the (k+1)-th time step length is less than the k-th time step length, and k is a positive integer.

[0127] It should be understood that in the embodiments of the present application, the input unit 504 can include a graphics processor (GPU) 5041 and a microphone 5042. The graphics processor 5041 processes image data of a still picture or a 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 can include a display panel 5061, which can be configured in the form of a liquid crystal display, an organic light-emitting diode, etc. The user input unit 507 includes at least one of a touch panel 5071 and other input devices 5072. The touch panel 5071 is also called a touch screen. The touch panel 5071 can include two parts of a touch detection device and a touch controller. The other input devices 5072 can include, but are not limited to, a physical keyboard, function keys (such as volume control keys, on-off keys, etc.), trackballs, mice, joysticks, etc., which will not be described here any further.

[0128] The memory 509 can be used to store software programs and various data. The memory 509 can mainly include a first storage area storing programs or instructions, and a second storage area storing data, wherein the first storage area can store application programs or instructions required by the operation device, at least one function (such as a sound playing function, an image playing function, etc.), and the like. In addition, the memory 509 can include a volatile memory or a non-volatile memory, or the memory 509 can include both a volatile memory and a non-volatile memory. The non-volatile memory can be a Read-Only Memory (ROM), a Programmable ROM (PROM), an Erasable PROM (EPROM), an Electrically EPROM (EEPROM), or a flash memory. The volatile memory can be a Random Access Memory (RAM), a Static RAM (SRAM), a Dynamic RAM (DRAM), a Synchronous DRAM (SDRAM), a Double Data Rate SDRAM (DDR SDRAM), an Enhanced SDRAM (ESDRAM), a Synch link DRAM (SLDRAM), and a Direct Rambus RAM (DRRAM). The memory 509 in the embodiments of the present application includes but is not limited to these and any other suitable types of memory.

[0129] The processor 510 can 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 operation device, user interface, and application programs, and the modem processor mainly processes wireless communication signals, such as a baseband processor. It can be understood that the above-mentioned modem processor can also not be integrated into the processor 510.

[0130] The embodiments of the present application also provide a readable storage medium, the readable storage medium stores programs or instructions, the programs or instructions are executed by a processor to realize the processes of the above-mentioned nuclear reactor thermal-hydraulic analysis embodiments, and achieve the same technical effects. To avoid repetition, details are not described here.

[0131] The processor is the processor in the electronic device described in the above embodiments. The readable storage medium includes a computer readable storage medium, such as a computer readable only memory (ROM), a random access memory (RAM), a magnetic disk or an optical disk, etc.

[0132] In addition, the embodiments of the present application provide a computer program product stored in a storage medium, which is executed by at least one processor to implement each process of the above nuclear reactor thermal hydraulic analysis embodiments and achieve the same technical effects. To avoid repetition, details are not described herein.

[0133] It should be noted that in this document, the terms "comprising", "including", or any other variant thereof are intended to cover non-exclusive inclusions, so that a process, method, article or device including a series of elements not only includes those elements, but also includes other elements not explicitly listed or inherent to such a process, method, article or device. Without more limitations, the element defined by the statement "including a" does not exclude the presence of another identical element 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 the order of performing the functions shown or discussed, but can also include performing the functions in a substantially simultaneous manner or in reverse order, for example, the described method can be performed in an order different from that described, and various steps can also be added, omitted or combined. In addition, the features described with reference to certain examples can be combined in other examples.

[0134] The above-mentioned serial numbers of the embodiments of the present application are only for description, not representing the advantages or disadvantages of the embodiments.

[0135] From the above description of the embodiments, those skilled in the art can clearly understand that the above-mentioned embodiment method can be realized by means of software and necessary general hardware platform, of course, it can also be realized by hardware, but in many cases, the former is a better embodiment. Based on such understanding, the technical solutions of the present application 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 plurality of instructions to make a terminal device (which can be a mobile phone, computer, server, or network device, etc.) execute the method described in each embodiment of the present application.

[0136] The embodiments of the present application are described above with reference to the accompanying drawings, but the present application is not limited to the specific embodiments described above, and the specific embodiments described above are merely illustrative, but not restrictive, and a person of ordinary skill in the art can make many forms under the inspiration of the present application without departing from the purpose of the present application and the scope protected by the claims.

Claims

1. A method for thermal-hydraulic analysis of a nuclear reactor, characterized in that, include: In the event of a breach accident in the nuclear reactor, the thermal-hydraulic analysis task of the nuclear reactor is performed using the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program; The thermal-hydraulic analysis task includes at least one thermal-hydraulic analysis operation; During the i-th thermal-hydraulic analysis operation of the aforementioned thermal-hydraulic analysis task, the thermal-hydraulic system analysis program determines the fluid thermal parameters at the i-th breach of the nuclear reactor based on the (i-1)-th containment thermal parameters of the nuclear reactor; wherein, the fluid thermal parameters at the i-th breach are the converged fluid thermal parameters at the breach determined based on the time step of the i-th breach thermal-hydraulic analysis; i is a positive integer, and when i equals 1, the (i-1)-th containment thermal parameters are the steady-state containment thermal parameters of the nuclear reactor; The containment thermal-hydraulic analysis program determines the i-th containment thermal parameters of the nuclear reactor based on the fluid thermal parameters at the i-th breach; 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 i-th containment thermal-hydraulic analysis time step 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, determine the current total analysis time of the thermal-hydraulic system analysis program; If 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 last thermal-hydraulic analysis operation 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 nuclear reactor.

2. The thermal-hydraulic analysis method for a nuclear reactor as described in 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 process includes: If the current total analysis time is less than the preset time, update i to i+1 and return to execute the i-th thermal-hydraulic analysis operation.

3. The thermal-hydraulic analysis method for a nuclear reactor as described in claim 1, characterized in that, The step of determining the fluid thermal parameters at the i-th breach of the nuclear reactor based on the (i-1)-th containment thermal parameters using the thermal-hydraulic system analysis program includes: Based on the j-th time step, the thermal-hydraulic system analysis program calculates the fluid thermal parameters at the breach of the nuclear reactor according to the (i-1)-th containment thermal parameters of the nuclear reactor, thus obtaining the fluid thermal parameters at the breach corresponding to the j-th time step. When the fluid thermal parameters at the breach corresponding to the j-th time step converge, the fluid thermal parameters at the breach corresponding to the j-th time step are determined as the fluid thermal parameters at the i-th breach of the nuclear reactor; wherein, the time step of the i-th breach thermal-hydraulic analysis is the j-th time step. If the fluid thermal parameters at the breach 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 process of calculating the fluid thermal parameters at the breach of the nuclear reactor based on the (i-1)-th containment thermal parameters using the thermal-hydraulic system analysis program based on the j-th time step continues until the fluid thermal parameters at the breach 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 for a nuclear reactor as described in claim 1, characterized in that, The process of determining the thermal parameters of the i-th containment of the nuclear reactor based on the fluid thermal parameters at the i-th breach using the containment thermal-hydraulic analysis program includes: Obtain the initial containment thermal-hydraulic analysis time step of the containment thermal-hydraulic analysis program; The k-th time step is determined based on the comparison between the initial containment thermal-hydraulic analysis time step and the i-th breach thermal-hydraulic analysis time step; wherein, if 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; if 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 k-th time step, the thermal parameters of the i-th containment of the nuclear reactor are determined by the containment thermal-hydraulic analysis program according to the fluid thermal parameters at the i-th breach.

5. The thermal-hydraulic analysis method for a nuclear reactor as described in claim 4, characterized in that, The process of determining the thermal parameters of the i-th containment of the nuclear reactor based on the k-th time step using the containment thermal-hydraulic analysis program according to the fluid thermal parameters at the i-th breach includes: Based on the k-th time step, the containment thermal parameters are calculated using the containment thermal-hydraulic analysis program according to the fluid thermal parameters at the i-th breach of the nuclear reactor, thus obtaining the containment thermal parameters corresponding to the k-th time step. If the containment thermal parameters corresponding to the k-th time step converge, the total calculation time step of the containment thermal-hydraulic analysis program in the i-th thermal-hydraulic analysis operation is compared 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 time step of the i-th breach thermal-hydraulic analysis, the containment thermal parameters corresponding to the k-th time step are determined as the i-th containment thermal parameters of the nuclear reactor, wherein the i-th breach thermal-hydraulic analysis time step is the k-th time step. 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 time step of the i-th breach thermal-hydraulic analysis, the program returns to the k-th time step and calculates the containment thermal parameters of the nuclear reactor based on the fluid thermal parameters at the i-th breach of the nuclear 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 time step of the i-th breach thermal-hydraulic analysis.

6. The method according to claim 5, characterized in that, After calculating the containment thermal parameters of the nuclear reactor based on the fluid thermal parameters at the i-th breach of the nuclear reactor using the containment thermal-hydraulic analysis program at the k-th time step, the method further includes: If the containment thermal parameters 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 process of calculating the containment thermal parameters of the nuclear reactor based on the fluid thermal parameters at the i-th breach of the nuclear reactor using the containment thermal-hydraulic analysis program based on the k-th time step continues until the containment thermal parameters corresponding to the k-th time step converge; wherein, the (k+1)-th time step is less than the k-th time step, and k is a positive integer.

7. A thermal-hydraulic analysis device for a nuclear reactor, characterized in that, The device includes: In the event of a breach accident in the nuclear reactor, the task module executes a thermal-hydraulic analysis task for the nuclear reactor using 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, during the i-th thermal-hydraulic analysis operation of the thermal-hydraulic analysis task, determines the fluid thermal parameters at the i-th breach of the nuclear reactor based on the (i-1)-th containment thermal parameters of the nuclear reactor through the thermal-hydraulic system analysis program; wherein, the fluid thermal parameters at the i-th breach are the converged fluid thermal parameters at the breach determined based on the time step of the i-th breach thermal-hydraulic analysis; i is a positive integer, and when i equals 1, the (i-1)-th containment thermal parameters are the steady-state containment thermal parameters of the nuclear reactor; The containment thermal-hydraulic analysis module determines the i-th containment thermal parameters of the nuclear reactor based on the fluid thermal parameters at the i-th breach using 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 i-th containment thermal-hydraulic analysis time step 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; The duration determination module determines the current total analysis duration of the thermal-hydraulic system analysis program after executing the i-th thermal-hydraulic analysis operation. The result determination module terminates the execution of the thermal-hydraulic analysis task when the current total analysis time is greater than or equal to the preset time, and determines the result of the last thermal-hydraulic analysis operation of the thermal-hydraulic system analysis program and the containment thermal-hydraulic analysis program as the thermal-hydraulic analysis result of the nuclear reactor.

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