Rapid automated modeling methods, systems, and media applicable to research reactors

Abstract

The present invention discloses a rapid automated modeling method, system, and medium applicable to research reactors, and belongs to the field of thermal hydraulic technology of research reactors. The method includes: establishing position numbers for different positions of the reactor core; establishing coordinates under the position numbers; collecting layout information of components in the reactor core, establishing coordinate information of components in the reactor core; establishing component structured data corresponding to the positions; sequentially reading information of each position of the reactor core, establishing a component model of the entire reactor core, and completing rapid automated modeling of the entire core. The rapid automated modeling method applicable to research reactors provided by the present invention models and analyzes each type of component in the core (including beryllium components, fuel components, aluminum components, control rod components, and irradiation channels) separately, and finally establishes a one-to-one corresponding position assembly relationship for the core layout in a programming manner, thereby realizing three-dimensional automatic modeling.

Description

Technical Field

[0001] This invention relates to the field of thermal-hydraulic technology for research reactors, and more specifically to rapid automated modeling methods, systems, and media applicable to research reactors. Background Technology

[0002] Compared to commercial pressurized water reactors, research reactors have a much more complex core layout and the ability to simultaneously conduct irradiation of multiple fuels, isotopes, and materials. Especially in research reactors like the High Flux Engineering Test Reactor (HFETR), the core layout is highly flexible. Each fuel assembly, isotope target, beryllium assembly, aluminum assembly, etc., occupies a cell and can be interchanged as needed. Placing different components in each cell creates a new core, and the core layout varies greatly depending on the mission requirements. Therefore, research reactors are characterized by a very complex core layout, which significantly impacts thermal-hydraulic calculations and core flow distribution. Research reactors typically operate for a fixed duration per run, such as one month. This means that the types of components arranged in various locations within the reactor core may change every month. If traditional manual 3D modeling methods are used, the significant monthly changes to the core would necessitate remodeling each time, requiring the model to be drawn manually at each location—a highly inefficient and costly process. Summary of the Invention

[0003] This invention provides a rapid automated modeling method, system, and medium for research reactors. Targeting the characteristics of research reactor cores—flexible layout, numerous and varied irradiation tasks—it establishes a rapid and automated 3D modeling method suitable for the complex and flexible nature of research reactor cores, solving the problem that each heat loading of a research reactor is complex and that manual 3D modeling is time-consuming.

[0004] The above technical objectives of the present invention are achieved through the following technical solutions:

[0005] This invention provides a rapid and automated modeling method suitable for research reactors, the method comprising:

[0006] Establish position numbers for different locations in the reactor core. The first position in the first row is numbered A1, the second position in the first row is numbered A2, the first position in the second row is numbered B1, and so on.

[0007] Establish coordinates under location number;

[0008] Collect the layout information of the components in the reactor core and establish the coordinate information of the components in the reactor core;

[0009] Establish structured data for components corresponding to their locations, and obtain the coordinates, component type, material type, and hydrodynamic data under the location number;

[0010] Read the information about the reactor core location, determine the component type of the reactor core at that location, and build a component model;

[0011] Information from each location in the reactor core is read sequentially to build a component model of the entire reactor core, thus completing rapid and automated modeling of the entire reactor core.

[0012] Furthermore, in the aforementioned rapid automated modeling method applicable to research reactors, the reactor core components include: aluminum assembly Al, beryllium assembly Be, control rod assembly CR, and representative fuel assembly FA.

[0013] Furthermore, in the aforementioned rapid automated modeling method applicable to research reactors, the reactor core is a fuel assembly FA, ​​and a three-dimensional model of the corresponding fuel assembly FA is established at that location based on the fuel assembly FA.

[0014] Furthermore, in the aforementioned rapid automated modeling method applicable to research reactors, the reactor core is a beryllium assembly Be, and a three-dimensional model of the corresponding beryllium assembly Be is established at that location based on the beryllium assembly Be.

[0015] Furthermore, in the aforementioned rapid automated modeling method applicable to research reactors, the reactor core is an aluminum assembly A1, and a three-dimensional model of the corresponding aluminum assembly A1 is established at that location based on the aluminum assembly A1.

[0016] Furthermore, in the aforementioned rapid automated modeling method applicable to research reactors, the reactor core is a control rod assembly (CR), and a three-dimensional model of the corresponding control rod assembly (CR) is established at that location based on the control rod assembly (CR).

[0017] Furthermore, in the aforementioned rapid automated modeling method applicable to research reactors, the component type also includes irradiation channels, where the corresponding 3D model of the irradiation channel does not contain any fuel assemblies.

[0018] Furthermore, in the aforementioned rapid automated modeling method applicable to research heaps, the coordinates under the location number are established, and the specific process is as follows:

[0019] Set the coordinates of A1 to (0, 0), A2 to (0, X), and B1 to (-X*√3 / 2, -X / 2). Based on the fact that three adjacent components form an equilateral triangle, and so on; where X is the distance between adjacent components.

[0020] The present invention also provides a system based on the above-described rapid automated modeling method suitable for research reactors, the system comprising:

[0021] The location coordinate processing module establishes location numbers for different locations in the reactor core and creates coordinates for each location number.

[0022] The data acquisition module collects the layout information of the components in the reactor core, establishes the coordinate information of the components in the reactor core, and establishes the structured data of the components corresponding to their positions.

[0023] The model building module reads information from each location in the reactor core in sequence, determines the component type of the reactor core at that location, and builds a component model to create a component model of the entire reactor core.

[0024] The present invention also provides a computer-readable storage medium, characterized in that the computer-readable storage medium stores a computer program, wherein when the computer program is executed by a processor, it implements the steps of the rapid automated modeling method applicable to research reactors as described above.

[0025] Compared with the prior art, the present invention has the following beneficial effects:

[0026] The present invention provides a rapid automated modeling method for research reactors, which models and analyzes each type of component in the reactor core (including beryllium components, fuel components, aluminum components, control rod components, and irradiation channels) separately, and finally establishes a one-to-one positional assembly relationship for the reactor core arrangement through programming, thereby realizing three-dimensional automatic modeling.

[0027] The present invention provides a rapid automated modeling method for research reactors, which realizes three-dimensional automatic modeling. The modeling efficiency and accuracy are far higher than manual modeling, and the modeling time is greatly reduced from the original 3 days to 10 minutes. It can adapt well to the situation that the reactor core changes in each batch, avoiding repeated modeling.

[0028] The rapid automated modeling method for research reactors provided by this invention can be applied to the rapid modeling of research reactors with complex and flexible layouts, laying the foundation for thermal-hydraulic analysis. Attached Figure Description

[0029] The accompanying drawings, which are included to provide a further understanding of embodiments of the invention and constitute a part of this invention, are not intended to limit the scope of the invention. In the drawings:

[0030] Figure 1 This is a schematic diagram of the actual core layout of a typical research reactor provided in the embodiments of the present invention;

[0031] Figure 2 A flowchart illustrating a rapid automated modeling method for research reactors provided in an embodiment of the present invention;

[0032] Figure 3 This is a schematic diagram of the full core layout of a research reactor provided in an embodiment of the present invention;

[0033] Figure 4A schematic diagram of the cross-sectional structure of some components in the rapid automated modeling method for research heaps provided in this embodiment of the invention;

[0034] Figure 5 A schematic diagram of a three-dimensional model of a combustion component in a rapid automated modeling method for research reactors provided in an embodiment of the present invention;

[0035] Figure 6 A model established based on the rapid automated modeling method for research reactors provided in the embodiments of the present invention;

[0036] Figure 7 This is a flowchart illustrating a rapid automated modeling system for research reactors, provided as an embodiment of the present invention. Detailed Implementation

[0037] 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 examples and drawings. The exemplary embodiments of the present invention and their descriptions are only used to explain the present invention and are not intended to limit the present invention.

[0038] A research reactor is a type of nuclear reactor used for irradiation experiments. A typical core arrangement is a regular hexagon (three adjacent positions form an equilateral triangle with sides of 63 mm). The core arrangement of a research reactor is very complex; please refer to [reference needed]. Figure 1 , Figure 1 This is a schematic diagram of the actual core layout of a typical research reactor. A typical research reactor used for irradiation testing has 320 core locations, with each location having options such as (aluminum assembly Al, beryllium assembly Be, control rod assembly CR, representative fuel assembly FA, ​​irradiation channel assembly, etc.). Such a research reactor core layout requires at least 5... 320 One possibility is that relying solely on manual modeling is labor-intensive and inefficient. Research reactors used for irradiation experiments are frequently adjusted according to the needs of the research. Unlike other reactors where modeling is done once, research reactors typically operate for a fixed period each time, requiring adjustments to the reactor core. For example, if each batch operates for one month, this means that the types of components arranged in various locations within the reactor core may change each month. If traditional manual 3D modeling methods are used, the significant monthly changes to the core would necessitate remodeling each time, requiring the model to be drawn one by one at each location—a highly inefficient and costly process.

[0039] Therefore, in view of the deficiencies described in the background art above, the rapid automated modeling method for research reactors in this embodiment of the invention models and analyzes each type of component in the reactor core (including beryllium components, fuel components, aluminum components, control rod components, irradiation channels, etc.) separately, and finally establishes a one-to-one corresponding positional assembly relationship for the reactor core arrangement through programming, thereby realizing three-dimensional automatic modeling.

[0040] The method provided in this embodiment will be described in detail below with reference to specific implementation methods. Please refer to [link / reference]. Figure 2 , Figure 2 This is a flowchart illustrating a rapid automated modeling method for research reactors provided in an embodiment of the present invention. The method includes:

[0041] S1. Establish position numbers for different locations in the reactor core. The first position in the first row is numbered A1, the second position in the first row is numbered A2, the first position in the second row is numbered B1, and so on.

[0042] S2, establish coordinates under the position number, set the coordinates of A1 as (0, 0), the coordinates of A2 as (0, X), and the coordinates of B1 as (-X*√3 / 2, -X / 2). Based on the fact that three adjacent components form an equilateral triangle, and so on; where X is the distance between adjacent components;

[0043] In this embodiment, the distance between different components is a fixed distance. In the case of a typical core, this distance X is 64mm. Then the coordinates of A1 are (0mm, 0mm), the coordinates of A2 are (0mm, 64mm), and the coordinates of B1 are (-64*√3 / 2mm, -64 / 2mm). Based on the fact that three adjacent components form an equilateral triangle, the same principle applies.

[0044] S3, collect the layout information of the components in the reactor core and establish the coordinate information of the components in the reactor core; that is, determine which type of component should be placed at each location.

[0045] In this embodiment, the reactor core components include: an aluminum assembly (Al), a beryllium assembly (Be), a control rod assembly (CR), and a fuel-representing assembly (FA). The assembly also includes an irradiation channel assembly that does not contain any fuel. Figure 3 The diagram shown is a schematic of the core layout of a research reactor, where Al represents aluminum assemblies, Be represents beryllium assemblies, CR represents control rod assemblies, and FA represents fuel assemblies.

[0046] S4. Establish structured data of components corresponding to the location, and obtain the coordinates, component type, material type and hydrodynamic data under the location number;

[0047] In this embodiment, the location number is matched with its corresponding coordinates, component type, material type, and hydrodynamic data.

[0048] S5, Read the information on the location of the reactor core, determine the component type of the reactor core at that location, and build a component model;

[0049] In this embodiment, the reactor core is fuel assembly FA. A three-dimensional model of the corresponding fuel assembly FA is created at this location. The cross-sectional structure of the fuel assembly FA is as follows: Figure 4 As shown, the three-dimensional model structure of the fuel assembly established at this location is as follows: Figure 5 As shown.

[0050] The reactor core is a beryllium assembly (Be). Based on the beryllium assembly (Be), a 3D model of the corresponding beryllium assembly (Be) is created at this location. The cross-sectional structure of the beryllium assembly (Be) is as follows. Figure 4 As shown.

[0051] The reactor core is aluminum assembly A1. Based on aluminum assembly A1, a three-dimensional model of the corresponding aluminum assembly A1 is built at this location. The cross-sectional structure of aluminum assembly A1 is a hexagonal solid.

[0052] The reactor core is a control rod assembly (CR). Based on the CR, a 3D model of the corresponding CR is created at this location. The cross-sectional structure of the control rod assembly CR is as follows. Figure 4 As shown.

[0053] The component type also includes irradiation channels, where no fuel assemblies are placed in the corresponding 3D model of the irradiation channel; no modeling process is performed at this location, which represents the 3D model of the irradiation channel.

[0054] S6 sequentially reads information from each location in the reactor core, establishes a component model of the entire reactor core, and completes rapid automated modeling of the entire reactor core.

[0055] In this embodiment, step (5) is performed sequentially at each location in the reactor, and the final rapid automated modeling result of the entire reactor core is as follows: Figure 6 As shown.

[0056] Corresponding to the embodiments of the rapid automated modeling method applicable to research reactors described above, this invention also provides a rapid automated modeling system applicable to research reactors, such as... Figure 7 As shown, the system includes:

[0057] The position coordinate processing module 10 uses programming to establish position numbers for different locations in the reactor core and establish coordinates for the corresponding position numbers.

[0058] The data acquisition module 20 uses programming to acquire the layout information of the components in the reactor core, establish the coordinate information of the components in the reactor core, and establish the structured data of the components corresponding to their positions.

[0059] The model building module 30 uses a programming approach to sequentially read information from each location in the reactor core, determine the component type at that location, and build a component model to create a component model for the entire reactor core.

[0060] In this embodiment, the system uses Python programming to achieve rapid automated modeling suitable for research reactors.

[0061] In summary, the rapid automated modeling system for research reactors provided in this embodiment of the invention utilizes a data acquisition-modeling processing method to individually model and analyze each type of component in the reactor core (including beryllium assemblies, fuel assemblies, aluminum assemblies, control rod assemblies, and irradiation channels). Finally, it uses Python programming to establish a one-to-one positional assembly relationship for the reactor core layout, thereby achieving three-dimensional automatic modeling.

[0062] In another embodiment of the present invention, a readable storage medium is provided, specifically a computer-readable storage medium (Memory), which is a memory device in a computer device used to store programs and data. It is understood that the computer-readable storage medium here can include both built-in storage media in the computer device and extended storage media supported by the computer device. The computer-readable storage medium provides storage space that stores the operating system of a terminal. Furthermore, the storage space also stores one or more instructions suitable for loading and execution by a processor, which can be one or more computer programs (including program code). It should be noted that the computer-readable storage medium here can be high-speed RAM or non-volatile memory, such as at least one disk storage device. One or more instructions stored in the computer-readable storage medium can be loaded and executed by a processor to implement the corresponding steps in the above embodiments related to the rapid automated modeling system applicable to research heaps. Those skilled in the art will understand that embodiments of the present invention can be provided as methods, systems, or computer program products. Therefore, the present invention can take the form of a completely hardware embodiment, a completely software embodiment, or an embodiment combining software and hardware aspects. Furthermore, the present invention can take the form of a computer program product implemented on one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) containing computer-usable program code.

[0063] The specific implementation methods described above further illustrate the objectives, technical solutions and beneficial effects of the present invention in detail. It should be understood that the above description is only a specific implementation method of the present invention and is 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 and automated modeling method suitable for research reactors, characterized in that, The method includes: Step 1: Establish position numbers for different locations in the reactor core. The first position in the first row is numbered A1, the second position in the first row is numbered A2, the first position in the second row is numbered B1, and so on. Step 2: Establish coordinates under the location number; Step 3: Collect the layout information of the components in the reactor core and establish the coordinate information of each component in the reactor core. The components in the reactor core include: aluminum assembly Al, beryllium assembly Be, control rod assembly CR, fuel assembly FA, ​​and irradiation channel assembly. Step 4: Establish structured data for components corresponding to their locations, and obtain the coordinates, component type, material type, and hydrodynamic data under the location number; Step 5: Use Python programming to read the reactor core location information, determine the component type of the reactor core at that location, and build a component model based on the determined component type: If the component type at this location in the reactor core is fuel assembly FA, ​​then a three-dimensional model of the corresponding fuel assembly FA is created at this location based on the fuel assembly FA. If the component type at this location in the reactor core is a beryllium component Be, then build a three-dimensional model of the corresponding beryllium component Be at this location; If the reactor core component type at this location is aluminum component A1, then a three-dimensional model of the corresponding aluminum component A1 is created at this location based on aluminum component A1. If the component type at this location in the reactor core is a control rod assembly (CR), then a three-dimensional model of the corresponding control rod assembly (CR) is created at this location. If the reactor core at this location is an irradiation channel, no fuel assembly will be placed in the corresponding 3D model of the irradiation channel at this location. Step 6: Read the information of each location of the remaining reactor core in sequence, and perform Step 5 at each location until a component model of the entire reactor core is established, thus completing the rapid and automated modeling of the entire reactor core.

2. The rapid automated modeling method for research reactors according to claim 1, characterized in that, The specific process for establishing coordinates under a location number is as follows: Let the coordinates of A1 be (0, 0), the coordinates of A2 be (0, X), and the coordinates of B1 be (_X*√3 / 2, _X / 2). The coordinates of A1 and B1 are determined by the fact that three adjacent components form an equilateral triangle, and so on. Here, X is the distance between adjacent components.

3. A system based on the rapid automated modeling method for research reactors according to any one of claims 1 to 2, characterized in that, The system includes: The location coordinate processing module establishes location numbers for different locations in the reactor core and creates coordinates for each location number. The data acquisition module collects the layout information of the components in the reactor core, establishes the coordinate information of the components in the reactor core, and establishes the structured data of the components corresponding to their positions. The model building module reads information from each location in the reactor core in sequence, determines the component type of the reactor core at that location, and builds a component model based on the component type, thus building a component model of the entire reactor core. The reactor core components include: aluminum assembly Al, beryllium assembly Be, control rod assembly CR, fuel assembly FA, ​​and irradiation channel assembly; When the model building module creates a component model based on the component type: If the component type at this location in the reactor core is fuel assembly FA, ​​then a three-dimensional model of the corresponding fuel assembly FA is created at this location based on the fuel assembly FA. If the component type at this location in the reactor core is a beryllium component Be, then build a three-dimensional model of the corresponding beryllium component Be at this location; If the reactor core component type at this location is aluminum component A1, then a three-dimensional model of the corresponding aluminum component A1 is created at this location based on aluminum component A1. If the component type at this location in the reactor core is a control rod assembly (CR), then a three-dimensional model of the corresponding control rod assembly (CR) is created at this location. If the reactor core at this location is an irradiated duct, the corresponding 3D model of the irradiated duct at this location will not contain any fuel assemblies.

4. A computer-readable storage medium, characterized in that, The computer-readable storage medium stores a computer program, wherein when the computer program is executed by a processor, it implements the steps of the rapid automated modeling method applicable to research reactors as described in any one of claims 1 to 2.

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