Rapid modeling method, system and terminal for mechanical analysis of reactor coolant system

Abstract

The present invention discloses a rapid modeling method, system and terminal for mechanical analysis of a reactor coolant system, and relates to the field of reactor structural mechanics. The technical solution thereof is as follows: the reactor coolant system is divided into a plurality of submodules according to basic components and / or functions, and each submodule is parameterized and modeled to obtain a corresponding finite element model; the coordinates of nodes in each finite element model are determined by a relative node coordinate positioning method; geometric parameters and / or material parameters in the finite element model are automatically numbered by a dynamic numbering function; and the numbered finite element models are merged to obtain a mechanical analysis model of the reactor coolant system. When the reactor coolant system is complexly arranged and involves numerous components, the present invention reduces the risk of conflict between the real constant numbering and the material constant numbering of the mechanical model of each component and the reactor coolant main loop pipeline through a modular and parameterized modeling method, and improves the model accuracy and modeling efficiency.

Description

Technical Field

[0001] The present invention relates to the field of reactor structural mechanics, and more specifically, to a rapid modeling method, system and terminal for mechanical analysis of a reactor coolant system. Background Art

[0002] The reactor coolant system is composed of seismic Class I equipment such as the reactor coolant main loop pipeline, reactor pressure vessel, main cooler, main pump and volume compensator, and is the reactor coolant pressure boundary. Under design basis accidents and extreme accident conditions, the reactor coolant system needs to provide sufficient structural integrity to ensure the shutdown system, emergency core cooling system and the barrier to prevent radioactive leakage are intact. Therefore, the establishment of the mechanical analysis model and mechanical response calculation of the reactor coolant system are important technical means to evaluate the safety of nuclear power plants.

[0003] Mechanical analysis of the reactor coolant system is an indispensable part of the safety assessment of nuclear power plants, and the analysis model is the basis for mechanical analysis. Numerical simulation is usually used to analyze the stress of the reactor coolant system under the action of deadweight, thermal expansion, earthquake and LOCA. At present, ANSYS is one of the more commonly used finite element analysis software. However, due to the large number of components involved in the reactor coolant system, the installation position elevations of different components vary greatly, and the layout of the reactor coolant main loop pipeline is complex. To establish the model, a large number of nodes and units need to be set to ensure the accuracy of the model. When the structural design needs to be adjusted or optimized, the analyst needs to re-model and adjust the material parameters, structural parameters and node coordinates of the model, which generates a lot of repetitive work, resulting in a long modeling time, low modeling efficiency, time-consuming and cumbersome, and unable to quickly and effectively evaluate the design, affecting the design efficiency.

[0004] Therefore, how to study and design a rapid modeling method, system and terminal for mechanical analysis of reactor coolant systems that can overcome the above-mentioned defects is a problem that we urgently need to solve. Summary of the invention

[0005] To address the deficiencies in the prior art, the purpose of the present invention is to provide a rapid modeling method, system and terminal for mechanical analysis of a reactor coolant system. When the reactor coolant system has a complex layout and involves many components, a modular and parameterized modeling approach is used to reduce the risk of conflict between the real constant numbering and the material constant numbering of the mechanical model of each component and the reactor coolant main loop pipeline, which is beneficial to improving model accuracy and modeling efficiency.

[0006] The above technical objectives of the present invention are achieved through the following technical solutions:

[0007] In a first aspect, a rapid modeling method for mechanical analysis of a reactor coolant system is provided, comprising the following steps:

[0008] The reactor coolant system is divided into a plurality of submodules according to basic components and / or functions, and a corresponding finite element model is obtained after parameterized modeling of each submodule;

[0009] The relative node coordinate positioning method is used to determine the coordinates of the nodes in each finite element model;

[0010] Automatically number the geometric parameters and / or material parameters in the finite element model through dynamic numbering functions;

[0011] The finite element models that have been numbered are merged to obtain the mechanical analysis model of the reactor coolant system.

[0012] Furthermore, the submodules of the reactor coolant system include a reactor pressure vessel module, a main cooler module, a main pump module, a volume compensator module and a reactor coolant main loop pipeline module.

[0013] Further, the geometric parameters of the reactor pressure vessel module include the outer diameter and wall thickness of the reactor pressure vessel cylinder;

[0014] The geometric parameters of the main cooler module include the outer diameter and wall thickness of the main cooler cylinder;

[0015] The geometric parameters of the main pump module include the cross-sectional shape, outer diameter and wall thickness of the main pump structure;

[0016] The geometric parameters of the volume compensator module include the outer diameter and wall thickness of the volume compensator cylinder;

[0017] And, the geometric parameters of the reactor coolant main loop pipeline module include the outer diameter and wall thickness of the reactor coolant main loop pipeline.

[0018] Further, the material parameters of the reactor pressure vessel module include density, Young's modulus and Poisson's ratio of the reactor pressure vessel cylinder;

[0019] The material parameters of the main cooler module include the density, Young's modulus and Poisson's ratio of the main cooler cylinder;

[0020] The material parameters of the main pump module include the density, Young's modulus and Poisson's ratio of the main pump structure;

[0021] The material parameters of the volume compensator module include the density, Young's modulus and Poisson's ratio of the volume compensator cylinder;

[0022] And, the material parameters of the reactor coolant main loop pipeline module include the density, Young's modulus and Poisson's ratio of the reactor coolant main loop pipeline.

[0023] Furthermore, the automatic numbering process of the geometric parameters and / or material parameters is specifically as follows:

[0024] Determine the number designation and total number of geometric parameters and / or material parameters;

[0025] The numbers of the geometric parameters and / or material parameters are sequentially superimposed and numbered by a dynamic numbering function until all the numbers are completed;

[0026] The overall translation of geometric parameters and / or material parameters in a single finite element model is achieved by adjusting the value of the total number.

[0027] Furthermore, the process of determining the coordinates of the nodes in the finite element model is specifically as follows:

[0028] Selecting coordinates of at least one node in the finite element model as calibration coordinates;

[0029] The coordinates of the remaining nodes in the finite element model are determined relative to the calibration coordinates;

[0030] Among them, when adding and / or reducing nodes in the finite element model corresponding to the reactor coolant main loop pipeline:

[0031] The nodes in the mechanical analysis model are divided into fixed nodes and adjustable nodes based on the changing nodes.

[0032] The change amount between the changed node and the adjacent fixed node is taken as the adjustment amount;

[0033] After superimposing the adjustment amount with the coordinates of each adjustment node, an updated mechanical analysis model is obtained.

[0034] Furthermore, the fusion process of the finite element model is specifically as follows:

[0035] The finite element model corresponding to the reactor coolant main loop pipeline is used as the basic model;

[0036] The finite element models corresponding to the reactor pressure vessel cylinder, the main cooler cylinder, the main pump structure and the volume compensator cylinder are imported into the basic model to obtain the mechanical analysis model of the reactor coolant system.

[0037] Furthermore, the method is applicable to mechanical analysis modeling of reactor coolant systems with multiple supports and / or large spans.

[0038] Secondly, a rapid modeling system for mechanical analysis of reactor coolant systems is provided, including:

[0039] A model division module is used to divide the reactor coolant system into multiple submodules according to basic components and / or functions, and obtain a corresponding finite element model after parameterizing each submodule;

[0040] A coordinate determination module, used to determine the coordinates of nodes in each finite element model using a relative node coordinate positioning method;

[0041] A numbering processing module, used for automatically numbering geometric parameters and / or material parameters in a finite element model through a dynamic numbering function;

[0042] The model fusion module is used to fuse the various numbered finite element models to obtain a mechanical analysis model of the reactor coolant system.

[0043] In a third aspect, a computer terminal is provided, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein when the processor executes the program, a rapid modeling method for mechanical analysis of a reactor coolant system as described in any one of the first aspects is implemented.

[0044] Compared with the prior art, the present invention has the following beneficial effects:

[0045] 1. The rapid modeling method for mechanical analysis of a reactor coolant system provided by the present invention reduces the risk of conflict between the real constant numbering and the material constant numbering of the mechanical model of each component and the reactor coolant main loop pipeline through modular and parameterized modeling when the reactor coolant system has a complex layout and involves many components, which is beneficial to improving the model accuracy and modeling efficiency;

[0046] 2. The present invention combines parameterization and relative node coordinate positioning methods. When the reactor coolant main loop pipeline changes, only the model nodes need to be partially adjusted, and the relevant nodes can be automatically adjusted and positioned. This makes it unnecessary for analysts to repeat the entire finite element model establishment process in the design process to modify a size parameter, which greatly reduces the workload and greatly improves the design optimization efficiency of the reactor coolant system.

[0047] 3. All processes of the present invention are realized by computer programs, and the calculation results are reliable. It can be used to conduct self-weight, thermal expansion and seismic analysis of multi-support and large-span reactor coolant systems, providing solid technical support for the safe and stable operation of reactor coolant systems. BRIEF DESCRIPTION OF THE DRAWINGS

[0048] The drawings described herein are used to provide a further understanding of the embodiments of the present invention, constitute a part of this application, and do not constitute a limitation of the embodiments of the present invention. In the drawings:

[0049] Figure 1is a flow chart in an embodiment of the present invention;

[0050] Figure 2 is a schematic diagram of a model of a reactor pressure vessel in an embodiment of the present invention;

[0051] Figure 3 is a schematic diagram of a model of a main cooler in an embodiment of the present invention;

[0052] Figure 4 is a schematic diagram of a model of a main pump structure in an embodiment of the present invention;

[0053] Figure 5 is a schematic diagram of a model of a volume compensator in an embodiment of the present invention;

[0054] Figure 6 is a schematic diagram of a model of a reactor coolant main loop pipeline in an embodiment of the present invention;

[0055] Figure 7 is a schematic diagram of a mechanical analysis model in an embodiment of the present invention;

[0056] Figure 8 It is a system block diagram in an embodiment of the present invention. DETAILED DESCRIPTION

[0057] In order to make the objectives, technical solutions and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with embodiments and drawings. The exemplary embodiments of the present invention and their description are only used to explain the present invention and are not intended to limit the present invention.

[0058] Example 1: Rapid modeling method for mechanical analysis of reactor coolant system, such as Figure 1 As shown, the following steps are included:

[0059] Step S1: dividing the reactor coolant system into multiple submodules according to basic components and / or functions, and performing parameterized modeling on each submodule to obtain a corresponding finite element model;

[0060] Step S2: using the relative node coordinate positioning method to determine the coordinates of the nodes in each finite element model;

[0061] Step S3: automatically numbering the geometric parameters and / or material parameters in the finite element model by a dynamic numbering function;

[0062] Step S4: merging the numbered finite element models to obtain a mechanical analysis model of the reactor coolant system.

[0063] Specifically, the composition relationship of the reactor coolant system is analyzed, and according to its basic components and functions, it is divided into reactor pressure vessel module, main cooler module, main pump module, volume compensator module and reactor coolant main loop pipeline module, and parametric modeling is performed for each module.

[0064] (1) Figure 2 As shown, according to the changes in the outer diameter and wall thickness of the reactor pressure vessel cylinder, the coordinates of the model nodes are determined and the nodes are defined; the geometric parameters of the pressure vessel cylinder, including the outer diameter and wall thickness, are determined, and the geometric parameters are defined by dynamic numbering. Before defining the geometric parameters, the number is named realnum, and realnum=N, where N is any integer greater than 0. Before defining subsequent geometric parameters, realnum=realnum+1 is used to achieve automatic superposition and dynamic numbering of geometric parameters until the definition of all geometric parameters is completed. By adjusting N, the overall translation of all geometric parameter numbers can be achieved, which can easily solve and avoid the problem of geometric parameter number conflicts in the subsequent overall assembly process.

[0065] Determine the material parameters of the pressure vessel cylinder, including density, Young's modulus, and Poisson's ratio, and use dynamic numbering to define the material parameters. Before defining the material parameters, name the number matnum, and let matnum=N, where N is any integer greater than 0. Before defining subsequent material parameters, use matnum=matnum+1 to achieve automatic superposition and dynamic numbering of material parameters until all material parameters are defined. By adjusting N, the overall translation of all material parameter numbers can be achieved, which can easily solve and avoid the problem of material parameter number conflicts in the subsequent overall assembly process; define the real constants of the spring unit simulating the pressure vessel support, including the stiffness in all directions; establish the unit to obtain the finite element model of the reactor pressure vessel; save it as a pressure vessel model macro file.

[0066] (2) Figure 3 As shown, according to the changes in the outer diameter and wall thickness of the main cooler cylinder, the coordinates of the model nodes are determined and the nodes are defined; the geometric parameters of the main cooler cylinder, including the outer diameter and wall thickness, are determined, and the geometric parameters are defined by dynamic numbering. Before defining the geometric parameters, the number is named realnum, and realnum=N, where N is any integer greater than 0. Before defining subsequent geometric parameters, realnum=realnum+1 is used to achieve automatic superposition and dynamic numbering of geometric parameters until the definition of all geometric parameters is completed. By adjusting N, the overall translation of all geometric parameter numbers can be achieved, which can easily solve and avoid the problem of geometric parameter number conflicts in the subsequent overall assembly process.

[0067] Determine the material parameters of the main cooler cylinder, including density, Young's modulus, and Poisson's ratio, and use dynamic numbering to define the material parameters. Before defining the material parameters, name the number matnum, and let matnum=N, where N is any integer greater than 0. Before defining subsequent material parameters, use matnum=matnum+1 to achieve automatic superposition and dynamic numbering of material parameters until all material parameters are defined. By adjusting N, the overall translation of all material parameter numbers can be achieved, which can easily solve and avoid the problem of material parameter number conflicts in the subsequent overall assembly process; define the real constants of the spring unit simulating the main cooler support, including the stiffness in all directions; establish the unit to obtain the finite element model of the main cooler; save it as the main cooler model macro file.

[0068] (3) Figure 4 As shown, according to the structural characteristics of the main pump, the coordinates of the model nodes are determined and the nodes are defined; the geometric parameters of the main pump structure, including the cross-sectional shape, outer diameter and wall thickness, are determined, and the geometric parameters are defined by dynamic numbering. Before defining the geometric parameters, the number is named realnum, and realnum=N, where N is any integer greater than 0. Before defining subsequent geometric parameters, realnum=realnum+1 is used to realize automatic superposition and dynamic numbering of geometric parameters until the definition of all geometric parameters is completed. By adjusting N, the overall translation of all geometric parameter numbers can be realized, which can easily solve and avoid the problem of geometric parameter number conflicts in the subsequent overall assembly process.

[0069] Determine the material parameters of the main pump, including density, Young's modulus, and Poisson's ratio. Use dynamic numbering to define the material parameters. Before defining the material parameters, name the number matnum, and let matnum=N, where N is any integer greater than 0. Before defining subsequent material parameters, use matnum=matnum+1 to achieve automatic superposition and dynamic numbering of material parameters until all material parameters are defined. By adjusting N, the overall translation of all material parameter numbers can be achieved, which can easily solve and avoid the problem of material parameter number conflicts in the subsequent overall assembly process; define the real constants of the shell unit simulating the support of the main pump, including the thickness of the shell; establish the unit to obtain the finite element model of the main pump; save it as the main pump model macro file.

[0070] (4) Figure 5As shown, according to the changes in the outer diameter and wall thickness of the volume compensator cylinder, the coordinates of the model nodes are determined and the nodes are defined; the geometric parameters of the volume compensator cylinder, including the outer diameter and wall thickness, are determined, and the geometric parameters are defined by dynamic numbering. Before defining the geometric parameters, the number is named realnum, and realnum=N, where N is any integer greater than 0. Before defining subsequent geometric parameters, realnum=realnum+1 is used to achieve automatic superposition and dynamic numbering of geometric parameters until the definition of all geometric parameters is completed. By adjusting N, the overall translation of all geometric parameter numbers can be achieved, which can easily solve and avoid the problem of geometric parameter number conflicts in the subsequent overall assembly process.

[0071] Determine the material parameters of the volume compensator cylinder, including density, Young's modulus, and Poisson's ratio. Use dynamic numbering to define the material parameters. Before defining the material parameters, name the number matnum, and let matnum=N, where N is any integer greater than 0. Before defining subsequent material parameters, use matnum=matnum+1 to achieve automatic superposition and dynamic numbering of material parameters until all material parameters are defined. By adjusting N, the overall translation of all material parameter numbers can be achieved, which can easily solve and avoid the problem of material parameter number conflicts in the subsequent overall assembly process; define the real constants of the spring unit simulating the volume compensator, including the stiffness in all directions; establish the unit to obtain the finite element model of the volume compensator; save it as a volume compensator model macro file.

[0072] (5) Figure 6 As shown, according to the reactor coolant main loop pipeline structure, the node coordinates of the pipeline model are determined by the relative node coordinate positioning method. The newly defined node coordinates are represented by parameters xx, yy and zz, and the calculation formula is: xx=xx0+Δxx, yy=yy0+Δyy, zz=zz0+Δzz. Among them, Δxx is the change of the newly defined node in the X direction of the model coordinate system relative to the previous adjacent node, xx0, yy0 and zz0 represent the coordinates of the previous adjacent node; Δyy is the change of the newly defined node in the Y direction of the model coordinate system relative to the previous adjacent node; Δzz is the change of the newly defined node in the Z direction of the model coordinate system relative to the previous adjacent node. Based on the relative node coordinate positioning method, when the reactor coolant main loop pipeline changes, only the model nodes need to be locally adjusted, and the relevant nodes can be automatically adjusted and positioned, which solves the problem of the traditional absolute node coordinate positioning method that requires adjustment of a large number of node coordinates. Determine the geometric parameters of the reactor coolant main loop pipeline, including the outer diameter and wall thickness; determine the material parameters of the reactor coolant main loop pipeline, including density, Young's modulus, and Poisson's ratio; establish units to obtain a finite element model of the reactor coolant main loop pipeline.

[0073] (6) Figure 7 As shown, based on the finite element model of the reactor coolant main loop piping, the reactor pressure vessel model, the main cooler model, the main pump model and the volume compensator model are imported into the finite element model of the reactor coolant main loop piping by using the *USE command to form a mechanical analysis model of the reactor coolant system.

[0074] Embodiment 2: A rapid modeling system for mechanical analysis of a reactor coolant system, the system is used to implement the rapid modeling method for mechanical analysis of a reactor coolant system described in Embodiment 1, such as Figure 8 As shown, it includes a model division module, a coordinate determination module, a number processing module and a model fusion module.

[0075] Among them, the model division module is used to divide the reactor coolant system into multiple sub-modules according to basic components and / or functions, and obtain the corresponding finite element model after parametric modeling of each sub-module; the coordinate determination module is used to determine the coordinates of the nodes in each finite element model by using the relative node coordinate positioning method; the numbering processing module is used to automatically number the geometric parameters and / or material parameters in the finite element model through the dynamic numbering function; the model fusion module is used to fuse the finite element models after numbering to obtain the mechanical analysis model of the reactor coolant system.

[0076] Working principle: When the reactor coolant system is complex in layout and involves many components, the present invention reduces the risk of conflict between the real constant numbering and the material constant numbering of the mechanical model of each component and the reactor coolant main loop pipeline through modular and parameterized modeling methods, which is beneficial to improving model accuracy and modeling efficiency; in addition, the present invention combines parameterization and relative node coordinate positioning methods. When the reactor coolant main loop pipeline changes, only local adjustments to the model nodes are required, and the relevant nodes can be automatically adjusted and positioned, so that analysts no longer need to repeat the entire finite element model establishment process due to modifying a dimensional parameter during the design process, which greatly reduces the workload and greatly improves the design optimization efficiency of the reactor coolant system.

[0077] Those skilled in the art will appreciate that the embodiments of the present application may be provided as methods, systems, or computer program products. Therefore, the present application may adopt the form of a complete hardware embodiment, a complete software embodiment, or an embodiment in combination with software and hardware. Moreover, the present application may adopt the form of a computer program product implemented in one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) that include computer-usable program code.

[0078] The present application is described with reference to the flowcharts and / or block diagrams of the methods, devices (systems), and computer program products according to the embodiments of the present application. It should be understood that each process and / or box in the flowchart and / or block diagram, as well as the combination of the processes and / or boxes in the flowchart and / or block diagram, can be implemented by computer program instructions. These computer program instructions can be provided to a processor of a general-purpose computer, a special-purpose computer, an embedded processor, or other programmable data processing device to generate a machine, so that the instructions executed by the processor of the computer or other programmable data processing device generate instructions for implementing the processes in the flowchart and / or block diagram. Figure 1 A process or multiple processes and / or boxes Figure 1 A device that provides the functions specified in a block or multiple blocks.

[0079] These computer program instructions may also be stored in a computer-readable memory capable of directing a computer or other programmable data processing device to operate in a specific manner, so that the instructions stored in the computer-readable memory produce an article of manufacture comprising an instruction device, which implements the process Figure 1 A process or multiple processes and / or boxes Figure 1 A function specified in one or more boxes.

[0080] These computer program instructions can also be loaded onto a computer or other programmable data processing device so that a series of operating steps are executed on the computer or other programmable device to produce a computer-implemented process, thereby providing instructions for implementing the process. Figure 1 A process or multiple processes and / or boxes Figure 1 A step that specifies a function in one or more boxes.

[0081] The above specific implementation methods further illustrate the objectives, technical solutions and beneficial effects of the present invention in detail. It should be understood that the above are only specific implementation methods of the present invention and are not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present invention should be included in the scope of protection of the present invention.

Claims

1. A rapid modeling method for mechanical analysis of reactor coolant systems, characterized by: The following steps are involved: The reactor coolant system is divided into a plurality of submodules according to basic components and / or functions, and a corresponding finite element model is obtained after parameterized modeling of each submodule; The relative node coordinate positioning method is used to determine the coordinates of the nodes in each finite element model; Automatically number the geometric parameters and / or material parameters in the finite element model through dynamic numbering functions; The finite element models after numbering are merged to obtain the mechanical analysis model of the reactor coolant system; The process of determining the coordinates of the nodes in the finite element model is specifically as follows: Selecting coordinates of at least one node in the finite element model as calibration coordinates; The coordinates of the remaining nodes in the finite element model are determined relative to the calibration coordinates; Among them, when adding and / or reducing nodes in the finite element model corresponding to the reactor coolant main loop pipeline: The nodes in the mechanical analysis model are divided into fixed nodes and adjustable nodes based on the changing nodes. The change amount between the changed node and the adjacent fixed node is taken as the adjustment amount; After superimposing the adjustment amount and the coordinates of each adjustment node, an updated mechanical analysis model is obtained; The fusion process of the finite element model is specifically as follows: The finite element model corresponding to the reactor coolant main loop pipeline is used as the basic model; The finite element models corresponding to the reactor pressure vessel cylinder, the main cooler cylinder, the main pump structure and the volume compensator cylinder are imported into the basic model to obtain the mechanical analysis model of the reactor coolant system.

2. The rapid modeling method for mechanical analysis of a reactor coolant system according to claim 1, characterized in that: The submodules of the reactor coolant system include a reactor pressure vessel module, a main cooler module, a main pump module, a volume compensator module and a reactor coolant main loop pipeline module.

3. The rapid modeling method for mechanical analysis of a reactor coolant system according to claim 2, characterized in that: The geometric parameters of the reactor pressure vessel module include the outer diameter and wall thickness of the reactor pressure vessel cylinder; The geometric parameters of the main cooler module include the outer diameter and wall thickness of the main cooler cylinder; The geometric parameters of the main pump module include the cross-sectional shape, outer diameter and wall thickness of the main pump structure; The geometric parameters of the volume compensator module include the outer diameter and wall thickness of the volume compensator cylinder; And, the geometric parameters of the reactor coolant main loop pipeline module include the outer diameter and wall thickness of the reactor coolant main loop pipeline.

4. The rapid modeling method for mechanical analysis of a reactor coolant system according to claim 2, characterized in that: The material parameters of the reactor pressure vessel module include density, Young's modulus and Poisson's ratio of the reactor pressure vessel cylinder; The material parameters of the main cooler module include the density, Young's modulus and Poisson's ratio of the main cooler cylinder; The material parameters of the main pump module include the density, Young's modulus and Poisson's ratio of the main pump structure; The material parameters of the volume compensator module include the density, Young's modulus and Poisson's ratio of the volume compensator cylinder; And, the material parameters of the reactor coolant main loop pipeline module include the density, Young's modulus and Poisson's ratio of the reactor coolant main loop pipeline.

5. The rapid modeling method for mechanical analysis of a reactor coolant system according to claim 1, characterized in that: The automatic numbering process of the geometric parameters and / or material parameters is specifically as follows: Determine the number designation and total number of geometric parameters and / or material parameters; The numbers of the geometric parameters and / or material parameters are sequentially superimposed and numbered by a dynamic numbering function until all the numbers are completed; The overall translation of geometric parameters and / or material parameters in a single finite element model is achieved by adjusting the value of the total number.

6. The rapid modeling method for mechanical analysis of a reactor coolant system according to any one of claims 1 to 5, characterized in that: The method is suitable for mechanical analysis modeling of reactor coolant systems with multiple supports and / or large spans.

7. Rapid modeling system for mechanical analysis of reactor coolant system, characterized by: The system is used to implement the rapid modeling method for mechanical analysis of a reactor coolant system as claimed in any one of claims 1 to 6, comprising: A model division module is used to divide the reactor coolant system into multiple submodules according to basic components and / or functions, and obtain a corresponding finite element model after parameterizing each submodule; A coordinate determination module, used to determine the coordinates of nodes in each finite element model using a relative node coordinate positioning method; A numbering processing module, used for automatically numbering geometric parameters and / or material parameters in a finite element model through a dynamic numbering function; The model fusion module is used to fuse the various numbered finite element models to obtain a mechanical analysis model of the reactor coolant system.

8. A computer terminal comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein: When the processor executes the program, the rapid modeling method for mechanical analysis of a reactor coolant system as described in any one of claims 1 to 5 is implemented.

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