A point kernel integration calculation model based on scene three-dimensional model efficient modeling method
By aligning standard geometric primitives in the 3D modeling program and introducing dose rate and color mapping to assist in locating source terms, the problems of low modeling efficiency and poor accuracy in the existing technology are solved, and an efficient and accurate gamma radiation field calculation model is established.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- CHINA INST FOR RADIATION PROTECTION
- Filing Date
- 2026-01-30
- Publication Date
- 2026-06-05
AI Technical Summary
Existing technologies suffer from low modeling efficiency and are susceptible to measurement errors and differences in experience when establishing calculation models for gamma radiation fields. In particular, they are difficult to guarantee the accuracy of models in complex scenes and under severe occlusion conditions.
A scene-based 3D model approach is adopted, in which objects are disassembled by a 3D modeling program, standard geometric primitives are created and aligned with the 3D model, and dose rate and color mapping are combined to assist in locating source terms. Parameters are extracted using a secondary development script to generate a point kernel integral calculation model.
It significantly reduces the workload of manual measurement and parameter entry in complex scenarios, improves the accuracy and efficiency of modeling, and ensures the reliability and interpretability of calculation results.
Smart Images
Figure CN122154166A_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of gamma radiation field calculation, and specifically to an efficient modeling method for point kernel integral calculation model based on a scene 3D model. Background Technology
[0002] The point kernel integration method is a commonly used method in gamma radiation field calculations. It simplifies the consideration of gamma ray scattering in matter by introducing a accumulation factor, thus effectively improving the computational efficiency of gamma radiation fields. Gamma rays exhibit different physical properties in different materials. Before using the point kernel integration method for gamma radiation field calculations, a corresponding computational model must be established to fully describe the geometric and material properties of the target scene space. To facilitate description and improve computational speed, simple standard geometric primitives are generally used to build the computational model. In the past, the coordinates and dimensions of these primitives were usually obtained from field measurements or data from design drawings. This not only resulted in low modeling efficiency but also compromised the accuracy of the computational model when the accuracy of measurements was poor or when there were significant deviations between the actual field conditions and the design drawings.
[0003] With the continuous advancement of digital transformation in the nuclear industry, more and more nuclear facilities have completed 3D modeling and formed corresponding digital 3D models. Against this backdrop, it has become possible to establish corresponding point kernel integral calculation models based on the 3D models of nuclear facility scenes.
[0004] In current engineering practice, the establishment of point-core integral calculation models largely relies on design drawings and on-site measurement results. Modelers abstract entities such as pipes, equipment, and walls into standard geometric basics such as cuboids, cylinders, and spheres, and then input material and source term parameters one by one. When the scene structure is complex, there is severe spatial occlusion, or the on-site conditions deviate significantly from the drawings, this method often requires a large amount of manual disassembly, positioning, and repeated verification, resulting in low modeling efficiency and susceptibility to measurement errors and differences in experience. Summary of the Invention
[0005] To achieve the above and other related objectives, this invention discloses an efficient modeling method for point kernel integral calculation models based on scene 3D models, comprising: Import the 3D model of the nuclear facility scene into the 3D modeling program and break down the objects to be modeled to form individual isolated 3D models; For shielding type objects, a standard geometric primitive is created in the 3D modeling program and aligned with the 3D model corresponding to the shielding type object. The size parameters and rotation angle are adjusted to obtain the shielding calculation model based on the 3D model. Material information is written according to the preset naming rules, and the shielding calculation model is named until all shielding type objects are processed. The location of the radioactive source term is determined, and when measured radiation field data is available, a quantitative mapping between dose rate and color is established, converting the measured data into colored spherical measuring points corresponding to the spatial location to assist in positioning. At the location of the source term, a source term calculation model is established by imitation, and material, nuclide and activity information are written in; The parameters of the shielded calculation model and the source item calculation model are extracted using a secondary development script and a basic body information extraction algorithm; The parameters are stored in the input card format according to the point kernel integral calculation program to obtain the point kernel integral calculation model for γ radiation field calculation.
[0006] Preferably, the process of splitting the object to be modeled includes: Using the separation function of the 3D modeling program, the object to be modeled is split into individual 3D models that can be selected and edited independently.
[0007] Preferably, the naming rules for the shielding calculation model include at least three types of fields: model name, material identifier, and shielding identifier; The material identifier is used to indicate at least one of the following materials: iron, water, air, concrete, polyethylene, or lead; the shielding identifier is used to indicate that the basic body is a shielded calculation model.
[0008] Preferably, the dose rate and color quantization mapping is used to map the dose rate value of each measurement point to an RGB color value, and to make the color of the colored spherical measurement point gradually change from cool to warm as the dose rate increases.
[0009] Preferably, the assisted positioning includes: Based on the spatial distribution of the colored spherical measuring points and the dose rate represented by the color, high dose rate regions are identified, and the spatial locations corresponding to these high dose rate regions are used as candidate locations for the radioactive source term.
[0010] Preferably, the naming rules for the source term calculation model include at least four types of fields: model name, material identifier, nuclide type, and activity, wherein the activity is recorded in Bq.
[0011] Preferably, the basic body information extraction algorithm includes: The primitive category is determined by a type determination function; Read the geometric, position, and orientation parameters according to the basic body category, where the orientation parameters are rotation quaternion information; Convert the rotation quaternion into a rotation matrix and calculate the Euler angles; Check for abnormal cases such as incorrect model naming and negative dimensional parameters; Iterate through all primitives in the scene and output the geometry and orientation parameters of the primitives.
[0012] Secondly, this invention discloses an efficient modeling system for point kernel integral calculation models based on scene 3D models, comprising: The model import and split module is used to import 3D models of nuclear facility scenes and split the objects to be modeled. The shielding model imitation module is used to create standard geometric primitives, align the primitives with the corresponding 3D models, and adjust their size and rotation to generate a shielding calculation model and write material information. The source term localization and visualization module is used to determine the location of radioactive source terms and, when there is actual radiation field measurement data, convert the measured data into colored spherical measurement points to assist in localization. The source term model imitation module is used to imitate and establish a source term calculation model at the source term location and write material, nuclide and activity information; The parameter extraction module is used to call the secondary development script and the basic information extraction algorithm to extract the parameters of the shielded calculation model and the source item calculation model; The input card generation module is used to store the parameters in the input card format of the point-core integral calculation program and generate the point-core integral calculation model.
[0013] Preferably, the parameter extraction module is configured to: select the corresponding attribute reading instruction according to the basic body category, extract geometric, position and rotation quaternion information, and verify naming errors and negative dimension anomalies before outputting.
[0014] Thirdly, the present invention discloses a computer-readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, implements the method described thereon.
[0015] By adopting the above technical solution, the structure of the real scene is aligned and imitated using standard geometric primitives in the 3D modeling program. Key attributes such as materials, nuclides, and activity are solidified according to a unified naming rule. Then, the input card parameters required for the point kernel integral calculation program are automatically exported by combining secondary development scripts and primitive information extraction algorithms. This significantly reduces the workload of manual measurement and parameter entry in complex scenes and reduces modeling inconsistencies caused by on-site deviations and measurement errors. At the same time, when radiation field measurement data is available, the visualization of dose rate and color mapping measurement points is introduced to assist in source term positioning and improve the accuracy and interpretability of source term modeling. Moreover, compared with directly performing ray intersection calculations on the 3D model of triangular facets, this invention achieves controllable calculation scale through primitive modeling, taking into account modeling efficiency, calculation efficiency, and the reliability of dose assessment results. Attached Figure Description
[0016] The above and other features, advantages, and aspects of the embodiments of this disclosure will become more apparent from the accompanying drawings and the following detailed description. The drawings are provided for a better understanding of the invention and are not intended to limit the scope of this disclosure. In the drawings, the same or similar reference numerals denote the same or similar elements, wherein: Figure 1 This is a flowchart of a method according to an embodiment of the present invention; Figure 2 This is a schematic diagram of the calculation model in an embodiment of the present invention; Figure 3 This is a schematic diagram of the converted colored spherical measuring points according to an embodiment of the present invention; Figure 4 The diagram illustrates the effect of implementing an embodiment of the present invention. Detailed Implementation
[0017] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.
[0018] Reference Figure 1 This invention provides an efficient modeling method for point kernel integral calculation models based on scene 3D models, including: Import the 3D model of the nuclear facility scene into the 3D modeling program and break down the objects to be modeled to form individual isolated 3D models; Reference Figure 2 For shielding objects, a standard geometric primitive is created in the 3D modeling program and aligned with the 3D model corresponding to the shielding object. The size parameters and rotation angle are adjusted to obtain a shielding calculation model based on the 3D model. Material information is written according to the preset naming rules, and the shielding calculation model is named until all shielding objects are processed. The location of the radioactive source term is determined, and when measured radiation field data is available, a quantitative mapping between dose rate and color is established, converting the measured data into colored spherical measuring points corresponding to the spatial location to assist in positioning. At the location of the source term, a source term calculation model is established by imitation, and material, nuclide and activity information are written in; The parameters of the shielded calculation model and the source item calculation model are extracted using a secondary development script and a basic body information extraction algorithm; The parameters are stored in the input card format according to the point kernel integral calculation program to obtain the point kernel integral calculation model for γ radiation field calculation.
[0019] Reference Figure 4The image shows the effect of using the point kernel integral calculation model to calculate the radiation field.
[0020] Preferably, the process of splitting the object to be modeled includes: Using the separation function of the 3D modeling program, the object to be modeled is split into individual 3D models that can be selected and edited independently.
[0021] Preferably, the naming rules for the shielding calculation model include at least three types of fields: model name, material identifier, and shielding identifier; The material identifier is used to indicate at least one of the following materials: iron, water, air, concrete, polyethylene, or lead; the shielding identifier is used to indicate that the basic body is a shielded calculation model.
[0022] In this embodiment of the invention, the naming rules for the shielding calculation model are as follows: for example, "Tube1 i sh", the first parameter is the model name, which can be named arbitrarily; the second parameter is the material of the model, "i" represents iron, "w" represents water, "a" represents air, "c" represents concrete, "p" represents polyethylene, and "l" represents lead; the third parameter "sh" identifies the calculation model as a shielding calculation model.
[0023] Preferably, the dose rate and color quantization mapping is used to map the dose rate value of each measurement point to an RGB color value, and to make the color of the colored spherical measurement point gradually change from cool to warm as the dose rate increases.
[0024] Preferably, the assisted positioning includes: Based on the spatial distribution of the colored spherical measuring points and the dose rate represented by the color, high dose rate regions are identified, and the spatial locations corresponding to these high dose rate regions are used as candidate locations for the radioactive source term.
[0025] Reference Figure 3 In this embodiment of the invention, a quantitative mapping relationship between dose rate values and color RGB values is established through a secondary development script. The radiation field measurement data is automatically converted into colored spherical measurement points at corresponding spatial locations in the three-dimensional modeling program (different colors correspond to different dose rate values) so as to more accurately locate the location of the radioactive source term.
[0026] The RGB value calculation algorithm is as follows: the color of the measuring point from blue to red represents the dose rate from low to high. Points with high dose rates are often near radioactive source terms.
[0027] Where dose is the dose rate value, min is the minimum dose rate, max is the maximum dose rate, and mean is the average dose rate.
[0028] Preferably, when creating the source term calculation model, based on the determined location of the radioactive source term, a corresponding source term calculation model is created inside the pipe, equipment, or other models in the same way. The naming rules of the source term calculation model include at least four fields: model name, material identifier, nuclide type, and activity, where the activity is recorded in Bq.
[0029] In this embodiment of the invention, the naming rule for the source term calculation model is as follows: "Cube1 a Co-60 1.2E+09", where the first parameter is the model name, which can be named arbitrarily; the second parameter is the material of the model, where "i" represents iron, "w" represents water, "a" represents air, "c" represents concrete, "p" represents polyethylene, and "l" represents lead; the third parameter is the nuclide type of the source term; and the fourth parameter is the activity of the source term, in Bq.
[0030] Preferably, the basic body information extraction algorithm includes: The primitive category is determined by a type determination function; Read the geometric, position, and orientation parameters according to the basic body category, where the orientation parameters are rotation quaternion information; Convert the rotation quaternion into a rotation matrix and calculate the Euler angles; Check for abnormal cases such as incorrect model naming and negative dimensional parameters; Iterate through all primitives in the scene and output the geometry and orientation parameters of the primitives.
[0031] In this embodiment of the invention, the basic body information extraction algorithm includes: S1. Use the classOf function to determine the category of the basic cube model, such as cuboid, cylinder, sphere, tubular, etc. S2. According to the category to which the basic model belongs, find its corresponding attributes using different commands. For example, use commands such as selection.height, selection.position, and selection.transform.rotationPart to obtain information such as geometry, position, and rotation quaternion of the basic model. S3. Convert the rotation quaternion of the model into a rotation matrix using the following formula: Where R is the rotation matrix of the model, Let be the rotation quaternion of the model; S4. Convert the rotation matrix to the corresponding Euler angles using the atan2 function: Where R is the rotation matrix of the model, , , These are the rotation angles of the model on the x, y, and z axes, respectively, with the rotation order being yxz; S5. Check for any abnormalities such as incorrect model naming or negative dimensional parameters; S6. Traverse all basic models and extract relevant data.
[0032] Preferably, storing the parameters in a point kernel integral calculation program input card format to obtain a point kernel integral calculation model for γ-radiation field calculation includes: The extracted computational model parameters are stored in the format of the CIRPDose input card to obtain the computational model used for point kernel integration. After importing it into the CIRPDose point kernel integration program, the γ radiation field can be calculated.
[0033] Secondly, this invention discloses an efficient modeling system for point kernel integral calculation models based on scene 3D models, comprising: The model import and split module is used to import 3D models of nuclear facility scenes and split the objects to be modeled. The shielding model imitation module is used to create standard geometric primitives, align the primitives with the corresponding 3D models, and adjust their size and rotation to generate a shielding calculation model and write material information. The source term localization and visualization module is used to determine the location of radioactive source terms and, when there is actual radiation field measurement data, convert the measured data into colored spherical measurement points to assist in localization. The source term model imitation module is used to imitate and establish a source term calculation model at the source term location and write material, nuclide and activity information; The parameter extraction module is used to call the secondary development script and the basic information extraction algorithm to extract the parameters of the shielded calculation model and the source item calculation model; The input card generation module is used to store the parameters in the input card format of the point-core integral calculation program and generate the point-core integral calculation model.
[0034] Preferably, the parameter extraction module is configured to: select the corresponding attribute reading instruction according to the basic body category, extract geometric, position and rotation quaternion information, and verify naming errors and negative dimension anomalies before outputting.
[0035] Thirdly, the present invention discloses a computer-readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, implements the method described thereon.
[0036] It will be understood by those skilled in the art that, unless otherwise defined, all terms used herein (including technical and scientific terms) have the same meaning as commonly understood by one of ordinary skill in the art to which this invention pertains. It should also be understood that terms such as those defined in general dictionaries should be understood to have the meaning consistent with their meaning in the context of the prior art, and should not be interpreted in an idealized or overly formal sense unless specifically defined.
[0037] For the sake of simplicity, the method embodiments are described as a series of actions. However, those skilled in the art should understand that the embodiments of the present invention are not limited to the described order of actions, because according to the embodiments of the present invention, some steps can be performed in other orders or simultaneously. Furthermore, those skilled in the art should also understand that the embodiments described in the specification are preferred embodiments, and the actions involved are not necessarily essential to the embodiments of the present invention.
[0038] As can be seen from the above description of the embodiments, those skilled in the art can clearly understand that this application can be implemented by means of software plus necessary general-purpose hardware platforms. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, can be embodied in the form of a software product. This computer software product can be stored in a storage medium, such as ROM / RAM, magnetic disk, optical disk, etc., and includes several instructions to cause a computer device (which may be a personal computer, server, or network device, etc.) to execute the methods described in various embodiments or some parts of the embodiments of this application.
[0039] Finally, it should be noted that the above embodiments are only used to illustrate the technical solutions of the present invention, and not to limit them; although the present invention has been described in detail with reference to the foregoing embodiments, those skilled in the art should understand that modifications can still be made to the technical solutions described in the foregoing embodiments, or equivalent substitutions can be made to some or all of the technical features; and these modifications or substitutions do not cause the essence of the corresponding technical solutions to deviate from the scope of the technical solutions of the embodiments of the present invention.
Claims
1. An efficient modeling method for point kernel integral calculation model based on scene 3D model, characterized in that, include: Import the 3D model of the nuclear facility scene into the 3D modeling program and break down the objects to be modeled to form individual isolated 3D models; For shielding type objects, a standard geometric primitive is created in the 3D modeling program and aligned with the 3D model corresponding to the shielding type object. The size parameters and rotation angle are adjusted to obtain the shielding calculation model based on the 3D model. Material information is written according to the preset naming rules, and the shielding calculation model is named until all shielding type objects are processed. The location of the radioactive source term is determined, and when measured radiation field data is available, a quantitative mapping between dose rate and color is established, converting the measured data into colored spherical measuring points corresponding to the spatial location to assist in positioning. At the location of the source term, a source term calculation model is established by imitation, and material, nuclide and activity information are written in; The parameters of the shielded calculation model and the source item calculation model are extracted using a secondary development script and a basic body information extraction algorithm; The parameters are stored in the input card format according to the point kernel integral calculation program to obtain the point kernel integral calculation model for γ radiation field calculation.
2. The method according to claim 1, characterized in that, The process of splitting the object to be modeled includes: Using the separation function of the 3D modeling program, the object to be modeled is split into individual 3D models that can be selected and edited independently.
3. The method according to claim 1, characterized in that, The naming rules for the shielding calculation model include at least three types of fields: model name, material identifier, and shielding identifier; The material identifier is used to indicate at least one of the following materials: iron, water, air, concrete, polyethylene, or lead; the shielding identifier is used to indicate that the basic body is a shielded calculation model.
4. The method according to claim 1, characterized in that, The dose rate and color quantization mapping is used to map the dose rate value of each measurement point to an RGB color value, and to make the color of the colored spherical measurement point gradually change from cool to warm as the dose rate increases.
5. The method according to claim 4, characterized in that, The assisted positioning includes: Based on the spatial distribution of the colored spherical measuring points and the dose rate represented by the color, high dose rate regions are identified, and the spatial locations corresponding to these high dose rate regions are used as candidate locations for the radioactive source term.
6. The method according to claim 1, characterized in that, The naming rules for the source term calculation model include at least four fields: model name, material identifier, nuclide type, and activity, with activity recorded in Bq.
7. The method according to claim 1, characterized in that, The basic body information extraction algorithm includes: The primitive category is determined by a type determination function; Read the geometric, position, and orientation parameters according to the basic body category, where the orientation parameters are rotation quaternion information; Convert the rotation quaternion into a rotation matrix and calculate the Euler angles; Check for abnormal cases such as incorrect model naming and negative dimensional parameters; Iterate through all primitives in the scene and output the geometry and orientation parameters of the primitives.
8. A high-efficiency modeling system for point kernel integral calculation model based on scene 3D model, characterized in that, include: The model import and split module is used to import 3D models of nuclear facility scenes and split the objects to be modeled. The shielding model imitation module is used to create standard geometric primitives, align the primitives with the corresponding 3D models, and adjust their size and rotation to generate a shielding calculation model and write material information. The source term localization and visualization module is used to determine the location of radioactive source terms and, when there is actual radiation field measurement data, convert the measured data into colored spherical measurement points to assist in localization. The source term model imitation module is used to imitate and establish a source term calculation model at the source term location and write material, nuclide and activity information; The parameter extraction module is used to call the secondary development script and the basic information extraction algorithm to extract the parameters of the shielded calculation model and the source item calculation model; The input card generation module is used to store the parameters in the input card format of the point-core integral calculation program and generate the point-core integral calculation model.
9. The system according to claim 8, characterized in that, The parameter extraction module is configured to: select the corresponding attribute reading instruction according to the basic body category, extract geometric, position and rotation quaternion information, and verify naming errors and negative dimension anomalies before outputting.
10. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by a processor, it implements the method according to any one of claims 1 to 7.