Method, device, medium and equipment for calculating parameters of large space components of nuclear reactors

Abstract

This application discloses a method, device, medium, and equipment for calculating the parameters of a large-space component in a nuclear reactor. The method includes: identifying the large-space component and other components in the nuclear reactor system; dividing the pressure solution matrix for multiple control bodies in the large-space component into a first structural matrix block and a second structural matrix block; solving the first structural matrix block in parallel to obtain the vapor pressure of each control body in the large-space component; solving the second structural matrix block in parallel to obtain the liquid pressure of each control body in the large-space component; and iteratively updating the interface pressure parameters of the large-space component based on the corresponding vapor and liquid pressures of the large-space component until convergence. This method effectively simulates the intense mixing and heat conduction effects of the large-space component in a nuclear reactor system, reducing the difficulty of discretely solving large matrices in the system analysis program while improving the accuracy of the system analysis program's calculations.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear reaction systems, and in particular to a method, device, medium and equipment for calculating parameters of large-space components of a nuclear reactor. Background Art

[0002] Nuclear power plants contain large tanks like core water supply tanks and injection tanks, or large sodium pools in fast reactors. When complex accident conditions such as LOCA occur, these devices can experience mixing of hot and cold fluids, potentially leading to stratification, significantly impacting system flow and heat transfer. Therefore, a nuclear reactor system analysis program is required to model, analyze, and calculate the parameters of each device in a nuclear power plant.

[0003] In related technologies, the entire system is divided into different computing modules, and the pressure matrices of different computing modules are solved in parallel. However, for large-volume tank equipment such as core water supply tanks and injection tanks, or large-space components such as large sodium pools in fast reactors, it is still impossible to accurately simulate the lateral and radial heat conduction and violent mixing effects of large-space components. Summary of the Invention

[0004] In view of this, the present application provides a parameter calculation method, device, medium and equipment for large-space components of a nuclear reactor, which can effectively simulate the violent mixing and heat conduction effects of large-space components of a nuclear reactor system, while reducing the difficulty of discrete solution of large matrices in the system analysis program and improving the accuracy of the system analysis program calculation.

[0005] According to one aspect of the present application, a method for calculating parameters of a large-space component of a nuclear reactor is provided, comprising:

[0006] Categorize nuclear reactor systems and identify large space components and other components in nuclear reactor systems;

[0007] Divide the pressure solution matrix of the multiple control volumes in the large space component into a first structure matrix block and a second structure matrix block, wherein the length of the pressure solution matrix is ​​A times the number of control volumes in the large space component, A is a multiple of 2, and the length of the first structure matrix block or the second structure matrix block is the number of control volumes in the large space component;

[0008] Solve the first structure matrix block in parallel to obtain the vapor phase pressure of each control volume in the large space component;

[0009] The second structural matrix block is solved in parallel to obtain the liquid phase pressure of each control volume in the large space component;

[0010] According to the vapor phase pressure and liquid phase pressure corresponding to the large space component, the interface pressure parameters of the large space component are iteratively updated until convergence.

[0011] Optionally, the parameter calculation method for a large-space component of a nuclear reactor further includes:

[0012] Establish the vapor and liquid phase conservation equations for large space components;

[0013] Discretize the vapor and liquid phase conservation equations, determine multiple control volumes in the large space component, and obtain the mass-energy conservation equations and momentum conservation equations corresponding to the large space component;

[0014] The mass-energy conservation equations and momentum conservation equations are transformed to establish the pressure solution matrix for multiple control volumes in large space components.

[0015] Optionally, the parameter calculation method for a large-space component of a nuclear reactor further includes:

[0016] Based on the initial boundary conditions of the mass-energy solution matrix and the vapor pressure, liquid pressure, and fluid velocity corresponding to the large-space component, the mass-energy conservation equations are solved to obtain other node control parameters of each control body in the large-space component except for the pressure, among which other node control parameters include temperature or cavitation fraction.

[0017] Optionally, the parameter calculation method for a large-space component of a nuclear reactor further includes:

[0018] Update the vapor and liquid phase conservation equations based on the equivalent thermal diffusivity of the mass transfer process in large space components;

[0019] Among them, the vapor and liquid phase conservation equations of large space components are expressed as:

[0020]

[0021] Where ρ is density; v is fluid velocity; t is time; z is spatial coordinate; λ is thermal diffusion coefficient; ε is equivalent thermal diffusion coefficient; S φ is the generalized source term; φ is the node control parameter of the control body.

[0022] Optionally, the parameter calculation method for a large-space component of a nuclear reactor further includes:

[0023] According to the node control parameters of the control body in the large space component, the physical parameters of the large space component are updated through the state equation and physical property function;

[0024] The node control parameters include at least one of pressure, temperature, fluid velocity, and cavitation fraction; the pressure includes vapor phase pressure and liquid phase pressure; and the physical property parameters include at least one of flow rate, mass, and enthalpy value.

[0025] Optionally, solving the first structure matrix block in parallel to obtain the vapor phase pressure of each control volume in the large space component includes:

[0026] Determine the coefficients of the pressure solution matrix according to the initial boundary conditions of the pressure solution matrix in the current iteration cycle;

[0027] Using the LU decomposition method, based on the coefficients and initial parameters of the large spatial component, the matrix solving algorithm is called on different first structure matrix blocks for parallel calculation to obtain the vapor phase pressure of different control volumes in the current iteration cycle;

[0028] The initial parameters include initial inlet pressure, initial outlet pressure, initial inlet flow rate, initial outlet flow rate, initial inlet temperature, and initial outlet temperature.

[0029] Optionally, the second structural matrix block is solved in parallel to obtain the liquid phase pressure of each control volume in the large space component, including:

[0030] Determine the coefficients of the pressure solution matrix according to the initial boundary conditions of the pressure solution matrix in the current iteration cycle;

[0031] Using the LU decomposition method, according to the coefficients and initial parameters of the large spatial components, the matrix solving algorithm is called on different second structure matrix blocks for parallel calculation to obtain the liquid phase pressure of different control volumes in the current iteration cycle;

[0032] The initial parameters include initial inlet pressure, initial outlet pressure, initial inlet flow rate, initial outlet flow rate, initial inlet temperature, and initial outlet temperature.

[0033] Optionally, the parameter calculation method for a large-space component of a nuclear reactor further includes:

[0034] Exchange the interface parameters of the connection between the large space component and the target component obtained in the current iteration cycle to update the initial boundary conditions of the pressure solution matrix and / or the initial boundary conditions of the mass-energy solution matrix obtained by discretizing the vapor and liquid phase conservation equations in the next iteration cycle;

[0035] The target component is another component connected to the large space component, and the interface parameter includes at least one of an interface pressure parameter, an interface temperature parameter, and an interface flow parameter.

[0036] According to another aspect of the present application, a parameter calculation device for a large-space component of a nuclear reactor is provided, comprising:

[0037] A component classification module is used to classify the nuclear reactor system and identify large space components and other components in the nuclear reactor system;

[0038] a calculation module, configured to divide a pressure solution matrix for a plurality of control volumes in the large space component into a first structure matrix block and a second structure matrix block, wherein the length of the pressure solution matrix is ​​A times the number of control volumes in the large space component, where A is a multiple of 2, and the length of the first structure matrix block or the second structure matrix block is the number of control volumes in the large space component; and, in parallel, solve the first structure matrix block to obtain a vapor phase pressure of each control volume in the large space component; and, in parallel, solve the second structure matrix block to obtain a liquid phase pressure of each control volume in the large space component;

[0039] The parameter updating module is used to iteratively update the interface pressure parameters of the large space component according to the vapor phase pressure and liquid phase pressure corresponding to the large space component until convergence.

[0040] Optionally, the calculation module is also used to establish the vapor and liquid phase conservation equations of the large space component; discretize the vapor and liquid phase conservation equations, determine multiple control bodies in the large space component, and obtain the mass-energy conservation equations and momentum conservation equations corresponding to the large space component; transform the mass-energy conservation equations and momentum conservation equations to establish the pressure solution matrix of multiple control bodies in the large space component.

[0041] Optionally, the calculation module is also used to solve the mass-energy conservation equations based on the initial boundary conditions of the mass-energy solution matrix, and the vapor pressure, liquid pressure and fluid velocity corresponding to the large space component, to obtain other node control parameters of each control body in the large space component in addition to the pressure, where the other node control parameters include temperature or cavitation fraction.

[0042] Optionally, the parameter calculation device for the large space component of the nuclear reactor further includes:

[0043] Equivalent module, used to update the vapor and liquid phase conservation equations based on the equivalent thermal diffusivity of the mass transfer process of large space components;

[0044] Among them, the vapor and liquid phase conservation equations of large space components are expressed as:

[0045]

[0046] Where ρ is density; v is fluid velocity; t is time; z is spatial coordinate; λ is thermal diffusion coefficient; ε is equivalent thermal diffusion coefficient; S φ is the generalized source term; φ is the node control parameter of the control body.

[0047] Optionally, the calculation module is further configured to update the physical property parameters of the large space component through the state equation and the physical property function according to the node control parameters of the control body in the large space component;

[0048] The node control parameters include at least one of pressure, temperature, fluid velocity, and cavitation fraction; the pressure includes vapor phase pressure and liquid phase pressure; and the physical property parameters include at least one of flow rate, mass, and enthalpy value.

[0049] Optionally, the calculation module is specifically configured to determine coefficients of the first structure matrix block based on the initial boundary conditions of the pressure solution matrix in the current iteration cycle; employ an LU decomposition method, based on the coefficients of the first structure matrix block and the initial parameters of the large space component, call a matrix solution algorithm on different first structure matrix blocks to perform parallel calculations, and obtain the vapor phase pressures of different control volumes in the current iteration cycle;

[0050] The initial parameters include initial inlet pressure, initial outlet pressure, initial inlet flow rate, initial outlet flow rate, initial inlet temperature, and initial outlet temperature.

[0051] Optionally, the calculation module is specifically configured to determine the coefficients of the second structure matrix block according to the initial boundary conditions of the pressure solution matrix in the current iteration cycle;

[0052] Using the LU decomposition method, according to the coefficients of the second structure matrix block and the initial parameters of the large space component, the matrix solution algorithm is called on different second structure matrix blocks for parallel calculation to obtain the liquid phase pressure of different control volumes in the current iteration cycle;

[0053] The initial parameters include initial inlet pressure, initial outlet pressure, initial inlet flow rate, initial outlet flow rate, initial inlet temperature, and initial outlet temperature.

[0054] Optionally, the parameter calculation device for the large space component of the nuclear reactor further includes:

[0055] A condition update module is used to exchange the interface parameters of the connection between the large space component and the target component obtained in the current iteration cycle to update the initial boundary conditions of the pressure solution matrix and / or the initial boundary conditions of the mass-energy solution matrix obtained by discretizing the vapor and liquid phase conservation equations in the next iteration cycle;

[0056] The target component is another component connected to the large space component, and the interface parameter includes at least one of an interface pressure parameter, an interface temperature parameter, and an interface flow parameter.

[0057] According to another aspect of the present application, a readable storage medium is provided, on which a program or instruction is stored. When the program or instruction is executed by a processor, the steps of the parameter calculation method of the large space component of the nuclear reactor are implemented.

[0058] According to another aspect of the present application, a computer device is provided, including a storage medium, a processor, and a computer program stored on the storage medium and executable on the processor. When the processor executes the program, the steps of the parameter calculation method for large-space components of a nuclear reactor are implemented.

[0059] By using the above technical solution, on the one hand, the large space component of the system is divided into multiple control bodies with the inlet and outlet of the system as the boundary, and the pressure solution matrix is ​​calculated in parallel at the nodes of different control bodies, effectively simulating the violent mixing and heat conduction effects that may occur in different areas of the large space component of the nuclear reactor system, reducing the difficulty of discrete solution of large matrices in the system analysis program, greatly shortening the calculation time, and improving the efficiency of the system analysis program for parameter calculation. On the other hand, the pressure solution matrix of multiple control bodies is further divided into blocks, and the vapor phase pressure and liquid phase pressure are solved separately after dividing into the first structure matrix block and the second structure matrix block, thereby fully considering the different physical properties of fluids in different phases. By performing independent solution calculations on the vapor (gas) phase and the liquid phase respectively, the mutual influence between different phases when the entire pressure solution matrix is ​​solved uniformly is avoided, which may cause the propagation and accumulation of errors, making the system calculation more accurate.

[0060] The above description is only an overview of the technical solution of the present application. In order to more clearly understand the technical means of the present application, it can be implemented in accordance with the contents of the specification. In order to make the above and other purposes, features and advantages of the present application more obvious and easy to understand, the specific implementation methods of the present application are listed below. BRIEF DESCRIPTION OF THE DRAWINGS

[0061] The drawings described herein are used to provide a further understanding of the present application and constitute a part of the present application. The illustrative embodiments of the present application and their descriptions are used to explain the present application and do not constitute an improper limitation on the present application. In the drawings:

[0062] Figure 1 A schematic flow chart of a method for calculating parameters of a large-space component of a nuclear reactor provided in an embodiment of the present application is shown;

[0063] Figure 2 A schematic diagram of the iterative calculation process of different components provided in an embodiment of the present application is shown;

[0064] Figure 3 The structural block diagram of the parameter calculation device for large space components of a nuclear reactor provided in an embodiment of the present application is shown. DETAILED DESCRIPTION

[0065] The present application will be described in detail below with reference to the accompanying drawings and in combination with embodiments. It should be noted that, unless there is a conflict, the embodiments and features in the embodiments of the present application can be combined with each other.

[0066] The following describes in detail embodiments of the present application, examples of which are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain the present application, and are not to be construed as limiting the present application.

[0067] It will be understood by those skilled in the art that, unless expressly stated otherwise, the singular forms "a", "an", "said" and "the" used herein may also include the plural forms. It should be further understood that the term "comprising" used in the specification of this application refers to the presence of the described features, integers, steps, operations, elements and / or components, but does not exclude the presence or addition of one or more other features, integers, steps, operations, elements, components and / or groups thereof. It should be understood that when we refer to an element as being "connected" or "connected" to another element, it may be directly connected or connected to the other element, or there may be intermediate elements. In addition, "connected" or "connected" as used herein may include wireless connection or wireless fusion. The term "and / or" used herein includes all or any unit and all combinations of one or more associated listed items.

[0068] Now, exemplary embodiments according to the present application will be described in more detail with reference to the accompanying drawings. However, these exemplary embodiments may be implemented in a variety of different forms and should not be construed as being limited to the embodiments set forth herein. It should be understood that these embodiments are provided to make the disclosure of this application thorough and complete and to fully convey the concepts of these exemplary embodiments to those of ordinary skill in the art.

[0069] In this embodiment, a method for calculating parameters of a large space component of a nuclear reactor is provided. Figure 1 As shown, the method includes:

[0070] Step 101: Classify the nuclear reactor system to determine large space components and other components in the nuclear reactor system.

[0071] In this embodiment, the nuclear reactor system is divided into large-space components that require a larger space and other components based on the volume of the components, so as to facilitate targeted simulation analysis and calculation of the large-space components.

[0072] Specifically, the large space components can be large tank equipment such as the core water supply tank, the injection tank, or components such as the large sodium pool in the fast reactor, which are not listed one by one in this application.

[0073] Step 102: Divide the pressure solution matrix of multiple control volumes in the large space component into a first structure matrix block and a second structure matrix block.

[0074] Among them, the length of the pressure solution matrix is ​​A times the number of control volumes of the large space component, A is a multiple of 2, and the length of the first structure matrix block or the second structure matrix block is the number of control volumes of the large space component.

[0075] For example, a large space component is divided into M control volumes, and A is set to 2. The resulting 2M×2M pressure matrix is ​​as follows:

[0076]

[0077] Among them, a i Represents different coefficient values ​​of the pressure solution matrix, and n represents the control body number.

[0078] The 2M×2M pressure solution matrix is ​​divided into 4 blocks, forming 2 first structure matrix blocks of length M and 2 second structure matrix blocks of length M, as follows:

[0079]

[0080] Among them, p represents pressure, k represents time value, S gi 、S ft Represent the vapor phase and liquid phase source terms respectively, i≤n.

[0081] In this embodiment, the inlet and outlet of the system's large space component are used as boundaries, and the large space component itself is divided into multiple control bodies, so that the pressure solution matrix can be calculated separately at different control body nodes. This not only reduces the scale of single matrix calculation of the system, but also effectively simulates the violent mixing and heat conduction effects that may occur in different areas of the large space component in the nuclear reactor system. This reduces the difficulty of discrete solution of large matrices in the system analysis program, greatly shortens the calculation time, and improves the efficiency of the system analysis program in calculating parameters. In addition, for each control body, the pressure solution matrix is ​​further divided into a first structure matrix block and a second structure matrix block, so that the pressure under different phases can be calculated separately through the first structure matrix block and the second structure matrix block. This avoids the mutual influence between different phases when the entire pressure solution matrix is ​​solved uniformly, which may cause the propagation and accumulation of errors, making the system calculation more accurate.

[0082] In one embodiment, before step 102, the parameter calculation method of the large space component of the nuclear reactor also includes: establishing vapor and liquid phase conservation equations for the large space component; discretizing the vapor and liquid phase conservation equations to determine multiple control bodies in the large space component, and obtaining the mass-energy conservation equations and momentum conservation equations corresponding to the large space component; transforming the mass-energy conservation equations and momentum conservation equations to establish a pressure solution matrix for multiple control bodies in the large space component.

[0083] The vapor and liquid phase conservation equations can be expanded into mass conservation equations, momentum conservation equations, and / or energy conservation equations, depending on the output parameters. The mass conservation equations describe how the mass of each fluid changes over time. The momentum conservation equations describe how the momentum of the fluid changes with flow and interaction. The energy conservation equations describe the energy transfer and conversion process of the fluid.

[0084] The mass conservation equations are expressed as:

[0085] The momentum conservation equations are expressed as:

[0086] The energy conservation equations are expressed as:

[0087] Where t is time; z is the spatial coordinate; v is the velocity of the two fluids; p is the pressure of the two fluids (vapor pressure and liquid pressure); g is the gravity of the two fluids plus the velocity of the fluid; θ is the angle between the flow channel and the horizontal position; F w is the flow resistance of the two fluids; U is the internal energy; q is the heat source energy; ρ m is the density of the mixture of the two fluids.

[0088] In this embodiment, the vapor and liquid phase conservation equations for the large-space component are discretized and converted into a set of algebraic equations (mass-energy conservation equations and momentum conservation equations). By transforming the mass-energy conservation equations and momentum conservation equations into a two-fluid dual-pressure form, each control volume is associated with a set of pressure equations. The pressure equations for multiple control volumes in the large-space component are combined to form a pressure solution matrix. Thus, through discretization, complex continuous equations can be solved on discrete control volumes, facilitating the use of mature numerical methods to capture detailed local variations in the large-space component. This reduces the difficulty of solving the problem while calculating more accurate vapor and liquid phase distributions and the transfer of energy and momentum, thereby improving computational feasibility.

[0089] Furthermore, considering the potential for hot and cold fluid stratification due to mixing of hot and cold fluids in large-space components, after establishing the vapor and liquid phase conservation equations for the large-space components, the parameter calculation method for the large-space components of a nuclear reactor also includes: updating the vapor and liquid phase conservation equations based on the equivalent thermal diffusivity of the mass transfer process in the large-space components.

[0090] Among them, the updated general expression of the vapor and liquid phase conservation equations of large space components is:

[0091]

[0092] Where ρ is density; v is fluid velocity; t is time; z is spatial coordinate; λ is thermal diffusion coefficient; ε is equivalent thermal diffusion coefficient, which characterizes the heat transfer effect of flow mixing enhancement in large space components of the system; S φ is the generalized source term; φ is the node control parameter of the control body, and the pressure equations are the equations when φ is pressure.

[0093] In this embodiment, the equivalent thermal diffusivity can more accurately reflect the heat transfer and material diffusion characteristics of large-volume components during mass transfer. By incorporating it into the updating of the vapor and liquid phase conservation equations, the updated conservation equations can better adapt to the mass transfer characteristics of large-volume components. This allows the model to better capture actual physical processes and better simulate the intense mixing and heat conduction effects of large-volume components in nuclear reactor systems, reducing unnecessary computational effort and improving the accuracy of the results.

[0094] Step 103 , solving the first structural matrix block in parallel to obtain the vapor phase pressure of each control volume in the large space component.

[0095] Step 104 , solving the second structural matrix block in parallel to obtain the liquid phase pressure of each control volume in the large space component.

[0096] In this embodiment, parallel solving can fully utilize multi-core processors or distributed computing resources, distributing computational tasks to multiple computing units for simultaneous execution. This can significantly shorten computation time, particularly for large-scale calculations and simulations of large spatial components. Furthermore, solving for the vapor and liquid pressures of each control volume is an independent process, yet they are interconnected within the large spatial component as a whole. Parallel solving can more accurately account for the interactions between the various control volumes, helping to improve computational accuracy and reduce the risk of computational interruptions and data loss due to software errors.

[0097] Specifically, step 103 specifically includes: determining the coefficients of the first structure matrix block based on the initial boundary conditions of the pressure solution matrix in the current iteration cycle; using the LU decomposition method, based on the coefficients of the first structure matrix block and the initial parameters of the large space component, calling the matrix solution algorithm on different first structure matrix blocks for parallel calculation to obtain the vapor phase pressure of different control bodies in the current iteration cycle.

[0098] Similarly, step 104 specifically includes: determining the coefficients of the second structure matrix block according to the initial boundary conditions of the pressure solution matrix in the current iteration cycle;

[0099] The LU decomposition method is used. According to the coefficients of the second structure matrix block and the initial parameters of the large spatial components, the matrix solving algorithm is called on different second structure matrix blocks for parallel calculation to obtain the liquid phase pressure of different control volumes in the current iteration cycle.

[0100] In this embodiment, on the one hand, parallel computing can fully utilize multi-core processors or distributed computing resources, distributing computing tasks to multiple computing units for simultaneous execution, significantly shortening calculation time and improving computational efficiency. On the other hand, the matrix is ​​decomposed into the product of a lower triangular matrix and an upper triangular matrix using the LU decomposition method, and then the linear equation system is solved through forward and backward permutations, thereby reducing error accumulation during the calculation process and helping to improve computing performance when processing large matrices.

[0101] The initial parameters include the initial inlet pressure, initial outlet pressure, initial inlet flow, initial outlet flow, initial inlet temperature, initial outlet temperature, etc. of the large space component.

[0102] Step 105 , iteratively updating the interface pressure parameters of the large space component according to the vapor phase pressure and liquid phase pressure corresponding to the large space component until convergence.

[0103] In this embodiment, by continuously iteratively updating the interface pressure parameters, the interface pressure parameters gradually converge, making the calculation results closer to the actual situation, thereby achieving goals such as better fluid flow control and improved energy transfer efficiency, optimizing the performance of large-space components, and ensuring stable operation and good performance of large-space components.

[0104] The parameter calculation method for a large-space component of a nuclear reactor provided in the embodiment of the present application can be applied to a terminal, can be applied to a server, or can be software running in a terminal or a server. In some embodiments, the terminal can be a smart phone, a tablet computer, a laptop computer, a desktop computer, etc.; the server can be configured as an independent physical server, or as a server cluster or distributed system composed of multiple physical servers, or as a cloud server that provides basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communications, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application that implements the parameter calculation method for a large-space component of a nuclear reactor, etc., but is not limited to the above forms.

[0105] In one embodiment, after step 103 and step 104, the parameter calculation method of the large space component of the nuclear reactor further includes: solving the mass-energy conservation equations based on the initial boundary conditions of the mass-energy solution matrix and the vapor pressure, liquid pressure and fluid velocity corresponding to the large space component to obtain other node control parameters of each control body in the large space component except for the pressure.

[0106] Among them, other node control parameters include temperature or cavitation fraction. The initial boundary conditions include initial conditions and boundary conditions. The initial boundary conditions are used to provide a starting point and boundary constraints for the calculation, so as to provide specific constraints and restrictions for solving the problem, making the solution unique. The initial boundary conditions can be reasonably set according to the functional machine control requirements of large-space equipment, and are not specifically limited in the embodiments of this application.

[0107] In this embodiment, in addition to the calculated pressure and constant fluid velocity, other nodal control parameters such as temperature and concentration are also crucial for fully describing the physical state of the large-space component. To this end, by substituting the known vapor pressure, liquid pressure, and fluid velocity into the mass-energy conservation equations with the initial boundary conditions as constraints, these other nodal control parameters can be obtained. This provides a deeper understanding of the thermodynamic and fluid dynamic characteristics of the large-space component, facilitating a more precise analysis of its performance and behavior.

[0108] In one embodiment, after obtaining the node control parameters of each control body in the large space component, the parameter calculation method of the large space component of the nuclear reactor also includes: updating the physical property parameters of the large space component through state equations and physical property functions based on the node control parameters of the control body in the large space component.

[0109] The node control parameters include at least one of pressure, temperature, fluid velocity, and cavitation fraction; the pressure includes vapor phase pressure and liquid phase pressure; and the physical property parameters include at least one of flow rate, mass, and enthalpy value.

[0110] In this embodiment, node control parameters can reflect the actual physical state at different locations within the large-space component. Combined with the equation of state and physical property functions, the physical properties of the large-space component can be more accurately determined. This allows for precise and complex physical property parameters of large-space components, which are crucial for accurately predicting key physical processes such as temperature distribution, pressure changes, and fluid flow. This allows simulations of large-space components to be more realistic, enabling operators to promptly understand changes in the large-space component, assisting in selecting optimal design parameters and improving the performance and efficiency of nuclear reactors.

[0111] It is worth mentioning that the same method as for large-space components can be used to calculate node control parameters (pressure, temperature, cavitation fraction, etc.) for other components in the nuclear reactor system. Specifically, the pressure solution matrix for multiple control bodies in the other components is divided into a third structure matrix block and a fourth structure matrix block, where the length of the pressure solution matrix is ​​A times the number of control bodies in the other components, where A is a multiple of 2, and the length of the third structure matrix block or the fourth structure matrix block is the number of control bodies in the other components. The third structure matrix block is solved in parallel to obtain the vapor phase pressure of each control body in the other components; the fourth structure matrix block is solved in parallel to obtain the liquid phase pressure of each control body in the other components. Based on the corresponding vapor phase pressure and liquid phase pressure of the other components, the interface pressure parameters of the other components are iteratively updated until convergence. Based on the initial boundary conditions of the mass-energy solution matrix obtained by discretizing the vapor and liquid phase conservation equations of the other components, as well as the vapor phase pressure, liquid phase pressure, and fluid velocity corresponding to the other components, the mass-energy conservation equations are solved to obtain the other node control parameters of each control body in the other components, except for the pressure.

[0112] In one embodiment, the parameter calculation method for large space components of a nuclear reactor also includes: exchanging the interface parameters at the connection between the large space component and the target component obtained in the current iteration cycle to update the initial boundary conditions of the pressure solution matrix of the next iteration cycle and / or the initial boundary conditions of the mass-energy solution matrix obtained by discretizing the vapor and liquid phase conservation equations.

[0113] The target component is another component connected to the large space component, and the interface parameter includes at least one of an interface pressure parameter, an interface temperature parameter, and an interface flow parameter.

[0114] In this embodiment, the interface parameters of the interconnected components in the system are exchanged, the initial values ​​of the pressure and mass-energy solution matrices are updated, and the next iteration of the calculation begins. This continues until the iterative calculation terminates and the parameters are output. By exchanging interface parameters, the large-space component and the target component can better handle the interactions and coupling relationships between various parts of the system, enabling more accurate information transmission and feedback between them. This allows for continuous correction of initial and boundary conditions during the iterative process, bringing the calculation results closer to reality and improving accuracy.

[0115] For example, the core water supply tank under special conditions such as ocean conditions is taken as the research object of the large space component, and multiple different control body nodes are divided.

[0116] Step 1: Using the inlet and outlet of the core feed water tank as the boundary, treat the core feed water tank as a special process component and divide the entire nuclear reactor system into blocks, namely the core feed water tank and other system components;

[0117] Step 2: Establish the vapor and liquid mass, momentum, and energy conservation equations for the core feed water tank and other system components respectively; perform a certain form of numerical discretization (such as mass sum and mass difference discretization; momentum sum and momentum difference discretization, etc., depending on the discretization form of the specific nuclear reactor system analysis program) on the vapor and liquid mass, momentum, and energy conservation equations for the core feed water tank and other system components respectively, so as to divide the core feed water tank into M control volumes and divide the other system components into N control volumes;

[0118] The general form of the conservation equations for mass, momentum, and energy in the vapor and liquid phases is as follows:

[0119]

[0120] Where ρ is density; v is fluid velocity; t is time; z is spatial coordinate; λ is thermal diffusion coefficient; ε is equivalent thermal diffusion coefficient; S φ is the generalized source term; φ is the nodal control parameter of the control volume, including the void fraction, velocity, temperature, or enthalpy. The equivalent thermal diffusivity can be determined experimentally. For the core makeup water tank, the equivalent thermal diffusivity can be related to parameters such as temperature difference and volume expansion coefficient. For other system components, the equivalent thermal diffusivity is zero.

[0121] Step 3: By transforming the mass-energy conservation equation and momentum conservation equation in the two-fluid dual-pressure form, pressure solution matrices for the control volumes divided by the core water tank and other system components are established, forming different 2M×2M and 2N×2N matrix equation groups;

[0122] Step 4: Based on the form of the pressure solution matrix equations, the 2M×2M or 2N×2N pressure solution matrix can be divided into four M×M or N×N structure matrix blocks with similar structures by using the block matrix idea;

[0123] Step 5: First, set the initial and boundary value conditions of each pressure solution matrix, as well as the known inlet and outlet pressures, inlet and outlet temperatures, and inlet and outlet flow rates of the core water supply tank; adopt a block matrix solution algorithm, based on the general matrix LU symbolic decomposition, matrix LU numerical decomposition and equation forward and back substitution solution steps, and solve four M×M and N×N structure matrix blocks with similar structures in parallel to obtain the vapor / liquid phase pressure of each control body node in the core water supply tank and other system components, update the pressure interface parameters, iterate the calculation until convergence, and then update the coefficients to start the calculation of the next iteration cycle.

[0124] In this embodiment, step 5 specifically includes the following steps:

[0125] Step 5.1: First set the initial and boundary conditions of the pressure matrix of the core water tank and other system components, and set the inlet and outlet pressures of the core water tank (Pin 、P out ), inlet and outlet temperatures (T in 、T out ), inlet and outlet flow (W in 、W out ); inlet and outlet pressures of other components (P s,in 、P s,out ), inlet and outlet temperatures (T s,in 、T s,out ), inlet and outlet flow (W s,in 、W s,out );

[0126] Step 5.2: Update the equation matrix coefficients according to the initial and boundary value conditions set in step 5.1. Based on the general matrix LU symbolic decomposition, matrix LU numerical decomposition, and equation forward and back substitution solution steps, call the matrix solution algorithm on different computing nodes for parallel calculation to obtain the vapor and liquid phase pressures of each control volume node of different components at the current time step.

[0127] Step 5.3: Keep the core inlet and outlet temperatures and flow rates unchanged, and exchange the pressure parameters calculated for the core makeup water tank and other system components. The other system components will flow into the core makeup water tank outlet pressure P s,out Assign a value to the core water tank inlet pressure P in ; The core water supply tank will make the core water supply tank outlet pressure P out Assigned to the inlet pressure P of other components of the system s,in .

[0128] Step 5.4: Iterative calculation, according to the pressure convergence criterion Determine whether to start calculation of the next iteration cycle.

[0129] Step 6: By associating with step 5, the pressure and velocity parameters of each control body node are calculated, and the M and N mass-energy solution matrix equations obtained by discretizing the mass and energy conservation equations corresponding to the core water supply tank and other system components are solved in parallel to obtain the node temperature, cavity fraction and other parameters of each control body at the new time of the core water supply tank and other system components;

[0130] Step 7: Based on the pressure, temperature, velocity, cavitation fraction and other parameters of each control volume node, other physical parameters such as flow rate, mass, enthalpy value are updated through the state equation and physical property function;

[0131] Step 8: Figure 2 As shown, the interface parameters of the core water supply tank and other system components are exchanged, the initial values ​​of the pressure solution matrix and the mass-energy solution matrix are updated, and the calculation at the next moment is started until the iterative calculation terminates and the parameters are output.

[0132] Step 8 specifically includes: other components of the system will flow into the core water tank flow W s,out , temperature T s,out Assign a value to the core water tank inlet flow rate W in , inlet temperature T in ; The core water supply tank will make the core water supply tank outlet flow W out , outlet temperature T out Assign the inlet flow W to other components of the system s,in , inlet temperature T s,in .

[0133] In this embodiment, the entire nuclear reactor system is divided into blocks with the inlet and outlet of the system large space component as the boundary, and is divided into the system large space component and other system components. The energy conservation equation established for the system large space component takes into account the influence of the equation heat diffusion term, and the equivalent heat diffusion coefficient of the mass transfer process is added to the heat diffusion term to characterize the heat transfer effect of the flow mixing enhancement of the system large space component. Based on the idea of ​​block matrix solution, the large pressure matrix solution matrix is ​​divided into matrix blocks with similar structural forms. Based on the general matrix LU symbolic decomposition, matrix LU numerical decomposition and equation forward and backward solution steps, the vapor / liquid phase pressure of each control body node of different components is obtained by parallel calculation. On different computing nodes, the mass-energy solution matrix equation group obtained by discretizing the mass and energy conservation equations corresponding to the system large space component and other system components is calculated in parallel, which can effectively reduce the difficulty of discrete solution of large matrices in the system analysis program and improve the calculation efficiency of the system analysis program.

[0134] It should be noted that the size of the serial numbers of the steps in the above embodiments does not mean the order of execution. The execution order of each process should be determined by its function and internal logic, and should not constitute any limitation on the implementation process of the embodiments of this application.

[0135] Furthermore, if Figure 3 As shown, as a specific implementation of the above-mentioned parameter calculation method for large-space components of a nuclear reactor, an embodiment of the present application provides a parameter calculation device 300 for large-space components of a nuclear reactor. The parameter calculation device 300 for large-space components of a nuclear reactor includes: a component classification module 301, a calculation module 302 and a parameter update module 303.

[0136] The component classification module 301 is used to classify the nuclear reactor system and determine the large space components and other components in the nuclear reactor system;

[0137] A calculation module 302 is configured to divide a pressure solution matrix for a plurality of control volumes in the large space component into a first structure matrix block and a second structure matrix block, wherein the length of the pressure solution matrix is ​​A times the number of control volumes in the large space component, where A is a multiple of 2, and the length of the first structure matrix block or the second structure matrix block is the number of control volumes in the large space component; and to solve the first structure matrix block in parallel to obtain the vapor phase pressure of each control volume in the large space component; and to solve the second structure matrix block in parallel to obtain the liquid phase pressure of each control volume in the large space component;

[0138] The parameter updating module 303 is used to iteratively update the interface pressure parameters of the large space component according to the vapor phase pressure and liquid phase pressure corresponding to the large space component until convergence.

[0139] Furthermore, the calculation module 302 is also used to establish the vapor and liquid phase conservation equations of the large space component; discretize the vapor and liquid phase conservation equations, determine multiple control bodies in the large space component, and obtain the mass-energy conservation equations and momentum conservation equations corresponding to the large space component; transform the mass-energy conservation equations and momentum conservation equations to establish the pressure solution matrix of multiple control bodies in the large space component.

[0140] Furthermore, the calculation module 302 is also used to solve the mass-energy conservation equations based on the initial boundary conditions of the mass-energy solution matrix, as well as the vapor pressure, liquid pressure and fluid velocity corresponding to the large space component, to obtain other node control parameters of each control body in the large space component in addition to the pressure, wherein the other node control parameters include temperature or cavitation fraction.

[0141] Furthermore, the parameter calculation device 300 for a large space component of a nuclear reactor further includes: an equivalent module (not shown in the figure);

[0142] The equivalent module is used to update the vapor and liquid phase conservation equations based on the equivalent thermal diffusivity of the mass transfer process of large space components. The vapor and liquid phase conservation equations of large space components are expressed as follows:

[0143]

[0144] Where ρ is density; v is fluid velocity; t is time; z is spatial coordinate; λ is thermal diffusion coefficient; ε is equivalent thermal diffusion coefficient; S φ is the generalized source term; φ is the node control parameter of the control body.

[0145] Furthermore, the calculation module 302 is also used to update the physical parameters of the large space component through the state equation and physical property function based on the node control parameters of the control body in the large space component; wherein the node control parameters include at least one of pressure, temperature, fluid velocity, and cavitation fraction, the pressure includes vapor phase pressure and liquid phase pressure, and the physical property parameters include at least one of flow rate, mass, and enthalpy value.

[0146] Furthermore, the calculation module 302 is specifically used to determine the coefficients of the first structure matrix block based on the initial boundary conditions of the pressure solution matrix in the current iteration cycle; using the LU decomposition method, based on the coefficients of the first structure matrix block and the initial parameters of the large space component, the matrix solution algorithm is called on different first structure matrix blocks for parallel calculation to obtain the vapor phase pressure of different control bodies in the current iteration cycle; wherein the initial parameters include initial inlet pressure, initial outlet pressure, initial inlet flow, initial outlet flow, initial inlet temperature, and initial outlet temperature.

[0147] Furthermore, the calculation module 302 is specifically used to determine the coefficients of the second structure matrix block based on the initial boundary conditions of the pressure solution matrix in the current iteration cycle; using the LU decomposition method, based on the coefficients of the second structure matrix block and the initial parameters of the large space component, the matrix solution algorithm is called on different second structure matrix blocks for parallel calculation to obtain the liquid phase pressure of different control bodies in the current iteration cycle; wherein the initial parameters include initial inlet pressure, initial outlet pressure, initial inlet flow, initial outlet flow, initial inlet temperature, and initial outlet temperature.

[0148] Furthermore, the parameter calculation device 300 for a large space component of a nuclear reactor further includes: a condition updating module (not shown in the figure);

[0149] A condition update module is used to exchange the interface parameters at the connection between the large space component and the target component obtained in the current iteration cycle to update the initial boundary conditions of the pressure solution matrix of the next iteration cycle and / or the initial boundary conditions of the mass-energy solution matrix obtained by discretizing the vapor and liquid phase conservation equations; wherein the target component is other components connected to the large space component, and the interface parameters include at least one of the interface pressure parameters, interface temperature parameters, and interface flow parameters.

[0150] The specific definitions of the parameter calculation device for a large-space component of a nuclear reactor can be found in the definitions of the parameter calculation method for a large-space component of a nuclear reactor described above and will not be repeated here. Each module in the parameter calculation device for a large-space component of a nuclear reactor can be implemented in whole or in part via software, hardware, or a combination thereof. Each of these modules can be embedded in or independent of a processor in a computer device in hardware form, or stored in a computer device memory in software form, so that the processor can call and execute the corresponding operations of each module.

[0151] Based on the above Figure 1 The method shown in FIG. 1 is a method for performing the above-mentioned operation. Accordingly, the embodiment of the present application further provides a readable storage medium having a computer program stored thereon. When the computer program is executed by the processor, the computer program is executed as shown in FIG. Figure 1 The parameter calculation method of the large space components of the nuclear reactor is shown.

[0152] Based on this understanding, the technical solution of the present application can be embodied in the form of a software product, which can be stored in a non-volatile storage medium (which can be a CD-ROM, USB flash drive, mobile hard disk, etc.), including a number of instructions for enabling a computer device (which can be a personal computer, server, or network device, etc.) to execute the methods described in each implementation scenario of the present application.

[0153] Based on the above Figure 1 The method shown, and Figure 3 In order to achieve the above-mentioned purpose, the embodiment of the present application further provides a computer device, which can be a personal computer, a server, a network device, etc. The computer device includes a storage medium and a processor; the storage medium is used to store a computer program; the processor is used to execute the computer program to achieve the above-mentioned Figure 1 The parameter calculation method of the large space components of the nuclear reactor is shown.

[0154] Optionally, the computer device may further include a user interface, a network interface, a camera, a radio frequency (RF) circuit, a sensor, an audio circuit, a Wi-Fi module, etc. The user interface may include a display, an input unit such as a keyboard, etc., and the optional user interface may also include a USB interface, a card reader interface, etc. The network interface may optionally include a standard wired interface, a wireless interface (such as a Bluetooth interface, a Wi-Fi interface), etc.

[0155] Those skilled in the art will understand that the computer device structure provided in this embodiment does not constitute a limitation on the computer device, and may include more or fewer components, or a combination of certain components, or different component arrangements.

[0156] The storage medium may also include an operating system and a network communication module. An operating system is a program that manages and stores the hardware and software resources of a computer device, supporting the execution of information processing programs and other software and / or programs. The network communication module facilitates communication between components within the storage medium, as well as with other hardware and software within the physical device.

[0157] Through the description of the above implementation methods, those skilled in the art can clearly understand that the present application can be implemented by means of software plus a necessary general hardware platform, or by hardware.

[0158] Those skilled in the art will understand that the accompanying drawings are only schematic diagrams of a preferred implementation scenario, and the modules or processes in the accompanying drawings are not necessarily required to implement the present application. Those skilled in the art will understand that the modules in the devices in the implementation scenario can be distributed in the devices of the implementation scenario according to the implementation scenario description, or can be changed accordingly and located in one or more devices different from the implementation scenario. The modules of the above-mentioned implementation scenario can be combined into one module, or can be further split into multiple sub-modules.

[0159] The serial numbers of the above application are for descriptive purposes only and do not represent the advantages or disadvantages of the implementation scenarios. The above disclosure only discloses several specific implementation scenarios of the present application, but the present application is not limited thereto. Any changes that can be conceived by those skilled in the art should fall within the scope of protection of the present application.

Claims

1. A method for calculating parameters of large space components of a nuclear reactor, characterized in that: The method comprises: Classify the nuclear reactor system to identify large-space components and other components in the nuclear reactor system that occupy a large space; Dividing a pressure solution matrix of multiple control volumes in the large space component into a first structure matrix block and a second structure matrix block, wherein the length of the pressure solution matrix is ​​twice the number of control volumes in the large space component, the pressure solution matrix is ​​obtained by transforming a mass-energy conservation equation group and a momentum conservation equation group, and the mass-energy conservation equation group and the momentum conservation equation group are obtained by discretizing vapor and liquid phase conservation equations of the large space component, and the length of the first structure matrix block or the second structure matrix block is the number of control volumes in the large space component; Solving the first structural matrix blocks in parallel to obtain the vapor phase pressure of each control volume in the large space component; Solving the second structural matrix block in parallel to obtain the liquid phase pressure of each control volume in the large space component; According to the vapor phase pressure and liquid phase pressure corresponding to the large space component, the interface pressure parameter of the large space component is iteratively updated until convergence.

2. The method for calculating parameters of a large space component of a nuclear reactor according to claim 1, characterized in that: The method further comprises: Establishing vapor and liquid phase conservation equations for the large space component; Discretizing the vapor and liquid phase conservation equations, determining a plurality of control volumes in the large space component, and obtaining a mass-energy conservation equation group and a momentum conservation equation group corresponding to the large space component; The mass-energy conservation equations and the momentum conservation equations are transformed to establish a pressure solution matrix for multiple control volumes in the large space component.

3. The method for calculating parameters of a large space component of a nuclear reactor according to claim 2, characterized in that: The method further comprises: According to the initial boundary conditions of the mass-energy solution matrix, and the vapor pressure, liquid pressure and fluid velocity corresponding to the large space component, the mass-energy conservation equations are solved to obtain other node control parameters of each control body in the large space component except for the pressure, wherein the other node control parameters include temperature or cavitation fraction.

4. The method for calculating parameters of a large space component of a nuclear reactor according to claim 1, characterized in that: The method further comprises: Updating the vapor and liquid phase conservation equations according to the equivalent thermal diffusion coefficient of the mass transfer process of the large space component; The vapor and liquid phase conservation equations of the large space component are expressed as follows: ， Where, ρ is the density; v is the fluid velocity; t For time; z is the spatial coordinate; λ is the thermal diffusivity; ε is the equivalent thermal diffusivity; S ϕ is the generalized source term; ϕ Control parameters for the nodes of the control volume.

5. The method for calculating parameters of a large space component of a nuclear reactor according to claim 1, characterized in that: The method further comprises: updating the physical property parameters of the large space component through a state equation and a physical property function according to the node control parameters of the control body in the large space component; The node control parameters include at least one of pressure, temperature, fluid velocity, and cavitation fraction; the pressure includes vapor phase pressure and liquid phase pressure; and the physical property parameters include at least one of flow rate, mass, and enthalpy.

6. The method for calculating parameters of a large space component of a nuclear reactor according to claim 1, characterized in that: The parallel solution of the first structural matrix block to obtain the vapor phase pressure of each control volume in the large space component includes: Determining coefficients of the first structural matrix block according to the initial boundary conditions of the pressure solution matrix in the current iteration cycle; Using the LU decomposition method, based on the coefficients of the first structural matrix block and the initial parameters of the large spatial component, a matrix solving algorithm is called on different first structural matrix blocks to perform parallel calculations to obtain the vapor phase pressure of different control volumes in the current iteration cycle; The parallel solution of the second structural matrix block to obtain the liquid phase pressure of each control volume in the large space component includes: Determining coefficients of the second structure matrix block according to the initial boundary conditions of the pressure solution matrix in the current iteration cycle; Using the LU decomposition method, based on the coefficients of the second structural matrix block and the initial parameters of the large spatial component, a matrix solving algorithm is called on different second structural matrix blocks to perform parallel calculations to obtain the liquid phase pressure of different control volumes in the current iteration cycle; The initial parameters include initial inlet pressure, initial outlet pressure, initial inlet flow rate, initial outlet flow rate, initial inlet temperature, and initial outlet temperature.

7. The method for calculating parameters of a large space component of a nuclear reactor according to claim 2 or 6, characterized in that: The method further comprises: exchanging interface parameters of the connection between the large space component and the target component obtained in the current iteration cycle to update the initial boundary conditions of the pressure solution matrix and / or the initial boundary conditions of the mass-energy solution matrix obtained by discretizing the vapor and liquid phase conservation equations in the next iteration cycle; Wherein, the target component is the other component connected to the large space component, and the interface parameter includes at least one of an interface pressure parameter, an interface temperature parameter, and an interface flow parameter.

8. A parameter calculation device for a large space component of a nuclear reactor, characterized in that: The device comprises: A component classification module is used to classify the nuclear reactor system and determine large-space components and other components in the nuclear reactor system that occupy a large space; a calculation module, configured to divide a pressure solution matrix for a plurality of control volumes in the large space component into a first structure matrix block and a second structure matrix block, wherein the length of the pressure solution matrix is ​​twice the number of control volumes in the large space component, the pressure solution matrix is ​​obtained by transforming a mass-energy conservation equation group and a momentum conservation equation group, the mass-energy conservation equation group and the momentum conservation equation group are obtained by discretizing vapor and liquid phase conservation equations of the large space component, and the length of the first structure matrix block or the second structure matrix block is the number of control volumes in the large space component; and Solving the first structural matrix blocks in parallel to obtain the vapor phase pressure of each control volume in the large space component; and Solving the second structural matrix block in parallel to obtain the liquid phase pressure of each control volume in the large space component; The parameter updating module is used to iteratively update the interface pressure parameters of the large space component according to the vapor phase pressure and liquid phase pressure corresponding to the large space component until convergence.

9. A readable storage medium having a program or instruction stored thereon, characterized in that: When the program or instruction is executed by a processor, the steps of the method for calculating parameters of a large-space component of a nuclear reactor according to any one of claims 1 to 7 are implemented.

10. A computer device comprising a storage medium, a processor, and a computer program stored in the storage medium and executable on the processor, wherein: When the processor executes the program, the method for calculating parameters of a large-space component of a nuclear reactor according to any one of claims 1 to 7 is implemented.

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