An X-ray shielding design method, system, device and storage medium
By using a radiation particle transport model based on the Monte Carlo method and iterative optimization techniques, the problem of radiation shielding design in complex multi-source environments was solved. This enabled accurate simulation of radiation fields and optimization of shielding schemes in complex environments, reducing material usage and costs, and ensuring radiation safety.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- XI AN JIAOTONG UNIV
- Filing Date
- 2026-03-19
- Publication Date
- 2026-06-02
AI Technical Summary
Existing radiation shielding design methods are not adaptable enough to complex environments such as multi-source coexistence and space constraints, making it difficult to achieve accurate radiation field simulation and effective shielding design, resulting in redundant material usage and increased costs.
A radiation particle transport model based on the Monte Carlo method was adopted. The actual positions and geometries of multiple X-ray sources were combined, and the model was built using radiation particle transport software. The variance reduction method was used to reduce statistical errors, and iterative optimization was carried out under the constraint of set dose limits to design the geometry and materials of the shield.
It enables accurate simulation of radiation fields in complex environments, optimizes shielding schemes, reduces material usage, lowers weight and cost, while meeting radiation safety requirements, and is suitable for shielding designs in compact spaces.
Smart Images
Figure CN122133416A_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of radiation protection technology, and in particular to an X-ray shielding design method, system, device and storage medium. Background Technology
[0002] With the widespread application of X-ray technology in non-destructive testing, high-energy physics experiments, advanced manufacturing, and biomedical imaging, while improving system performance and detection efficiency, it also generates a certain dose of ionizing radiation, which may pose potential hazards to operators, the surrounding environment, and the equipment itself. Therefore, developing scientific, reliable, and engineering-feasible radiation shielding designs for different application scenarios is a necessary prerequisite for ensuring the safe and controlled operation of X-ray sources.
[0003] Currently, commonly used radiation shielding design methods mainly include empirical formulas, lookup tables, and numerical simulation. While empirical formulas and lookup tables offer advantages such as ease of calculation and rapid implementation, their theoretical foundations are largely based on idealized geometric structures and single-source radiation assumptions. When faced with complex engineering conditions such as multi-source superposition, irregularly shaped shielding paths, and locally confined spaces, they often fail to accurately describe the radiation field distribution, leading to significant deviations in results. To ensure safety margins, their outputs typically require large safety factors, resulting in redundant shielding materials, increased structural mass, and higher manufacturing costs, which is detrimental to the development of modern equipment towards lightweight and refined designs. In contrast, particle transport simulation based on the Monte Carlo method can accurately reproduce the interaction process between photons and matter through stochastic processes. It exhibits high modeling accuracy and applicability under complex geometric structures, multi-material combinations, and wide-spectrum radiation field conditions, and has therefore become the mainstream shielding design method.
[0004] Several mature Monte Carlo simulation software programs are currently available for radiation shielding analysis, such as MCNP developed by Oak Ridge National Laboratory in the United States and the Geant4 toolkit developed by CERN. These software programs have significant advantages in simulating particle-matter interactions and have yielded substantial research results in the simulation and optimization of shielding for accelerator sources. For example, Wang Sheng et al. disclosed a radiation shielding design method based on radiation particle transport simulation. This method combines a genetic algorithm with the Monte Carlo-based radiation particle transport software MCNP to achieve multi-objective optimization of radiation shielding design. Sun Jianfeng et al. disclosed a transient gamma radiation shielding method, which is suitable for radiation shielding safety protection of transient high-current electron accelerators. Chen Lu et al. disclosed a radiation shielding mechanism and method for electron irradiation accelerators, which performs local shielding design for the working area of the electron accelerator beam under-beam device in the irradiation chamber, improving the safety of the working environment.
[0005] Although existing Monte Carlo simulation methods can simulate radiation fields relatively accurately, most existing shielding design methods focus on a single radiation source and are usually applicable to relatively broad or idealized laboratory and application scenarios. They are not adaptable to complex environments such as multi-source coexistence and space constraints. Summary of the Invention
[0006] In view of the defects of the existing technology, the present invention provides an X-ray shielding design method, system, device and storage medium, which solves the existing problems.
[0007] The present invention adopts the following technical solution: In a first aspect, the present invention provides an X-ray shielding design method, comprising the following steps: A computational model is obtained by modeling the actual location and geometry of multiple X-ray sources on radiation particle transport software; the target area is then subjected to radiation simulation using the computational model to obtain the simulated dose value of the target area when it is not shielded. The geometric structure of the shield to be designed is determined based on a computational model. The shield to be designed includes a target area shield and an X-ray source shield. The material and dimensions of the shield to be designed are obtained based on the comparison between the simulated dose value of the target area when it is not shielded and the set dose limit. The geometric structure, material and dimensions of the shield to be designed are combined to obtain the shield model. The shielding model is integrated into the calculation model to obtain the shielding calculation model; under the constraint of the set dose limit in the target area, the shielding model is iteratively optimized through the shielding calculation model.
[0008] Preferably, a computational model is obtained by modeling the actual positions and geometries of multiple X-ray sources using radiation particle transport software, specifically including the following steps: A corresponding geometric model is established based on the geometric structure of multiple X-ray sources, and material is filled into the geometric model; The particle type and source term parameters involved in the simulated transport process are determined by the geometric model to obtain the computational model; the particle type is photon, and the source term parameters include energy spectrum and angular distribution.
[0009] Preferably, the target area is a location where people reside. Radiation simulation of the target area is performed using a computational model to obtain the simulated dose value when the target area is not shielded. Specifically, this includes the following steps: The physical quantities of the target region are statistically analyzed using an F-type counter; these physical quantities are particle flux or energy deposition. The physical quantity is converted into the corresponding simulated dose value by combining dose conversion.
[0010] Preferably, during radiation simulation, the variance reduction method is used to control the particle transport process.
[0011] Preferably, the material includes lead, copper-tungsten alloy, tungsten-nickel-iron, or Q235 steel.
[0012] Secondly, the present invention provides an X-ray shielding design system, comprising: The simulation module is used to model the actual positions and geometries of multiple X-ray sources in radiation particle transport software to obtain a computational model; the computational model is used to perform radiation simulation on the target area to obtain the simulated dose value of the target area when it is not shielded. The module is used to determine the geometry of the shield to be designed based on the calculation model. The shield to be designed includes a target area shield and an X-ray source shield. The material and dimensions of the shield to be designed are obtained based on the comparison between the simulated dose value of the target area when it is not shielded and the set dose limit. The geometry, material and dimensions of the shield to be designed are combined to obtain the shield model. The optimization module is used to connect the shielding body model to the calculation model to obtain the shielding calculation model; under the constraint of the set dose limit in the target area, the shielding body model is iteratively optimized through the shielding calculation model.
[0013] Thirdly, the present invention provides a computer device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the program to implement the above-described X-ray shielding design method.
[0014] Fourthly, the present invention provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the above-described X-ray shielding design method.
[0015] Compared with the prior art, the above-mentioned at least one technical solution adopted by the present invention can achieve the following beneficial effects: This invention establishes a radiation particle transport model based on the Monte Carlo method, which can accurately simulate the superimposed radiation field of multiple X-ray sources in complex environments such as space constraints. It solves the shortcomings of traditional methods in dealing with the synergistic effects of multiple sources and spatial limitations. Furthermore, by optimizing the shielding model under the constraint of set dose limits in the target area, it fully considers the selection of materials and size while ensuring radiation safety, so that the final shielding scheme meets the dose constraints and effectively ensures the safety and compliance of the working environment. Attached Figure Description
[0016] To more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.
[0017] Figure 1 This is a flowchart of an X-ray shielding design method according to the present invention; Figure 2 This is a top view schematic diagram of an X-ray source device according to an embodiment of the present invention; Figure 3 The X-ray energy spectrum of an embodiment of the present invention; Figure 4 The X-ray angular distribution is shown in this embodiment of the invention. Figure 5 The sleeve shielding body is an embodiment of the present invention; Figure 6 This is a permanent shielding body according to an embodiment of the present invention; Figure 7 This is a sleeve shield body with optimized structure according to an embodiment of the present invention; In the diagram: 1-First personnel's permanent position, 2-Second personnel's permanent position, 3-Third personnel's permanent position, 4-X-X-ray source, 5-Front end cover, 6-Front end sleeve, 7-Short sleeve, 8-Middle sleeve, 9-Rear sleeve, 10-Rear end cover, 11-Shielding behind the driver's seat, 12-Shielding on the side of the driver's seat, 13-Plug-type shielding, 14-First sleeve-type shielding, 15-Second sleeve-type shielding, 16-Disc-type shielding. Detailed Implementation
[0018] 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.
[0019] While existing Monte Carlo simulation methods can accurately simulate radiation fields, most current shielding design methods focus primarily on single radiation sources and are generally applicable to relatively broad or idealized laboratory and application scenarios. Existing solutions lack adaptability to complex environments such as multi-source coexistence, compact structures, and space constraints, particularly in balancing radiation shielding effectiveness with structural optimization. Therefore, the purpose of this invention is to propose an X-ray shielding design method to address the shortcomings of existing technologies, including insufficient adaptability to multi-source conditions, limited structural optimization capabilities, and low shielding design accuracy.
[0020] like Figure 1 As shown, this invention provides a method for designing X-ray shielding for multi-source complex structures, addressing the lack of suitable design methods for multi-source complex structure X-ray shielding in compact spaces. The method includes the following steps: S1: Obtain the annual radiation dose constraint value for staff.
[0021] The annual radiation dose limit for workers is determined according to relevant national standards. The method for obtaining the annual radiation dose limit for workers is as follows: the radiation dose limit for workers is determined to be 20 mSv / year according to GB18871-2002 "Basic Standards for Ionizing Radiation Protection and Radiation Source Safety".
[0022] S2: Model the shielding design object on the radiation particle transport software, obtain the calculation model, and provide the simulation calculation results of the personnel's permanent location.
[0023] S21: Measure dimensions and establish a geometric model.
[0024] S22: Fill the geometric block with material according to the actual situation.
[0025] S23: Determine the types of particles involved in the simulated transport process. This invention studies X-ray shielding design; therefore, the particles involved in the simulated transport process are photons.
[0026] S24: Determine the radiation source term parameters.
[0027] Source parameters include the energy spectrum and angular distribution of the X-ray source, providing accurate physical basis for subsequent shielding simulations.
[0028] S25: Determine the statistical method. The statistical method of this invention combines tally statistics from Monte Carlo radiation transport calculations with dose conversion: First, physical quantities such as particle fluence or energy deposition at the personnel's usual location are statistically analyzed using a Class F counter; then, the statistical quantities are converted into corresponding dosimetric quantities using dose conversion, thereby obtaining the dose calculation result at the target location. This method enables quantitative comparison of doses for different shielding schemes, providing a basis for shielding structure optimization.
[0029] S26: Utilizing variance reduction methods to lower statistical errors. In Monte Carlo radiation transport simulations, due to the non-uniform distribution of radiation in space, some regions (especially low-flux regions after shielding) have a low probability of particle arrival, easily leading to undercounting and large statistical variance, thus affecting the reliability of the calculation results. To improve the credibility of the calculation results, this invention introduces variance reduction methods in the simulation process to regulate the particle transport process. For example, commonly used variance reduction techniques such as weighted windows are employed to improve the effective statistical efficiency in key areas, achieving improved statistical accuracy without altering the physical transport laws.
[0030] The innovations in this process are mainly reflected in the following aspects: (1) In the radiation field modeling stage, multiple radiation sources are introduced for unified modeling and calculation to more realistically represent the radiation field distribution characteristics under the condition of multiple source coexistence; (2) In the dose assessment process, the variance reduction method is flexibly applied in combination with the statistical error situation to improve the statistical accuracy of the low injection volume area, thereby enhancing the credibility of the simulated dose results and providing a reliable basis for the determination and optimization of the shielding scheme.
[0031] S3: Compare the simulated dose value in S2 with the annual radiation dose limit in S1 to provide a preliminary shielding scheme.
[0032] The method for determining the preliminary shielding scheme is as follows: Based on the geometric model of the X-ray source, determine the geometry of the shield to be designed, and according to the calculation methods provided in NCRP-151 (Structural Shielding Design And Evaluation For Megavoltage X-And Gamma-Ray Radiotherapy Facilities), specify the material and dimensions of the shield. The shield to be designed includes a shield for the target area and a shield for the X-ray source.
[0033] The geometry, material, and dimensions of the shield to be designed are combined to obtain the shield model.
[0034] S4: Connect the shielding model in S3 to the calculation model to obtain the shielding calculation model.
[0035] S5: Based on the shielding calculation model in S3, perform engineering optimization on the shielding scheme given in S3.
[0036] The engineering optimization of shielding solutions refers to ensuring the engineering feasibility of the solution in manufacturing, assembly, and integration while meeting the core constraint of radiation dose limits. Specifically, it requires comprehensive consideration of multiple factors such as material availability, processability, structural space constraints, and ease of equipment maintenance to guarantee the final feasibility of the solution.
[0037] S6: Determine whether the annual radiation dose constraint value is met after adopting the shielding scheme. If it is met, jump to S7. If it is not met, return to S3 until a shielding design scheme that meets the requirements is obtained.
[0038] S7: Obtain the final shielding design scheme.
[0039] Example Taking a certain X-ray source device as an example, its top view is as follows: Figure 2 As shown in the figure. In the figure, 1, 2, and 3 represent the first, second, and third personnel's permanent positions, respectively, and 4 is the X-ray source (the relative positions of the X-ray sources in the figure are schematic and used to illustrate the spatial distribution of the multi-source radiation field). Horizontally, the distance from permanent positions 1 and 2 to 4 is 74 cm, and the distance from permanent positions 3 to 4 is 267.2 cm. To ensure radiation safety in the personnel's permanent residence area, X-ray shielding design is required.
[0040] The specific design will be implemented according to the following steps: S1: According to GB18871-2002 "Basic Standards for Ionizing Radiation Protection and Radiation Source Safety", the radiation dose limit for workers is determined to be 20 mSv / year.
[0041] S2: Model the shielding design object on the radiation particle transport software, obtain the calculation model, and provide the simulation calculation results of the personnel's permanent location.
[0042] S21: Measure dimensions and establish a geometric model; S22: Fill the geometric blocks with material according to the actual situation; S23: Determine the types of particles involved in the simulated transport process; This invention studies the shielding design of X-rays, therefore the particles involved in the simulated transport process are photons.
[0043] S24: Determine the radiation source term parameters; Source parameters include the energy spectrum and angular distribution of the X-ray source, as shown in [reference 1]. Figure 3 , Figure 4 .
[0044] S25: Determine the statistical methods; S26: Use variance reduction methods flexibly to reduce statistical errors.
[0045] S3: The simulated dose values for personnel's permanent residence locations 1, 2, and 3 in S2 are 33.61 mSv, 29.32 mSv, and 10.32 mSv, respectively. These simulated dose values for personnel's permanent residence locations are compared with the annual radiation dose limit of 20 mSv. Following the calculation method provided in Report 151 of the U.S. National Commission on Radiation Protection and Measurement, the material and dimensions of the shielding are preliminarily determined, and the geometry of the shielding is determined based on the three-dimensional model (see...). Figure 5 , Figure 6 The orange area in the diagram represents the X-ray source piping, while the red and yellow areas represent the shielding structure. The orange area and the X-ray source constitute the X-ray source device. From a theoretical perspective of radiation protection, the shielding structure can achieve more continuous geometric coverage by further filling in the blank areas; however, at this stage, the preliminary design of the shielding structure is mainly based on engineering practice. While ensuring that reducing radiation dose is the primary objective, the actual situation of the X-ray source device having a linear scale on the order of centimeters, as well as engineering factors such as the processing complexity of the shielding structure and the ease of assembly and disassembly, were comprehensively considered, resulting in the preliminary shielding structure scheme shown in the diagram. Based on this, the shielding structure was further optimized using Monte Carlo radiation transport simulations, resulting in… Figure 7 The shielding scheme shown is an optimized design that effectively reduces radiation dose at personnel's usual locations while also considering engineering feasibility and practicality, making it more suitable for real-world applications.
[0046] In the diagram, 5 is the front cover, made of copper-tungsten alloy, with a diameter of 5.1cm and a dimension of 4cm; 6 is the front sleeve, made of lead, with an inner diameter of 5.1cm, an outer diameter of 15cm, and a length of 6.3cm; 7 is the short sleeve, made of lead, with an inner diameter of 5.6cm, an outer diameter of 15cm, and a length of 2.4cm; 8 is the middle sleeve, made of lead, with an inner diameter of 7.2cm, an outer diameter of 15cm, and a length of 12.98cm; 9 is the rear sleeve, made of lead, with an inner diameter of 5.7cm, an outer diameter of 15cm, and a length of 6.2cm; 10 is the rear cover, made of copper-tungsten alloy, with an inner diameter of 9.5cm, an outer diameter of 40cm, and a length of 2.29cm; 11 is the rear shield of the driver's seat, and 12 is the side shield of the driver's seat, made of tungsten-nickel-iron, with a dimension of 0.3cm.
[0047] S4: The shielding structures from S3 were incorporated into the computational model for simulation. The dose values at personnel's usual positions 1, 2, and 3 were 0.432 mSv, 0.394 mSv, and 0.356 mSv, respectively. Two shielding structures (11) were installed behind the driver's seat and two on the sides (12). Four shielding structures were also installed: a front cover (5), a front sleeve (6), a short sleeve (7), a middle sleeve (8), a rear sleeve (9), and a rear cover (10). The total weight of the shielding structure was 319.66 kg. Simulation results showed that although the dose levels at each location met safety limits, the shielding structure was too heavy, indicating significant room for optimization.
[0048] S5: Based on the shielding calculation model in S4, the shielding scheme given in S3 is optimized for engineering purposes. While meeting the core constraint of a radiation dose limit of 20 mSv, the engineering feasibility of the scheme in terms of manufacturing, assembly, and integration is ensured. Specifically, it requires comprehensive consideration of multiple factors such as material availability, processability, structural space constraints, and ease of equipment maintenance to guarantee the final feasibility of the scheme. Considering the space constraints and processing technology outside the short tube, the optimization mainly focuses on the shielding body outside the short tube. The optimized shielding scheme is shown below. Figure 7 .
[0049] 13 is a plug-type shield, optimized from the front end cover 5 and the front end sleeve 6, made of lead, with a diameter of 13cm and a length of 4cm. 14 and 15 are the first sleeve-type shield and the first sleeve-type shield, respectively. 14 is optimized from the short sleeve 7 and the middle sleeve 8, still made of lead, with an inner diameter of 11.5cm, an outer diameter of 15cm, and a length of 14.38cm. 15 is a slight modification of the rear sleeve 9, made of copper-tungsten alloy, with an inner diameter of 9.6cm, an outer diameter of 15cm, and a length of 1.86cm. 16 is a disc-type shield, slightly modified from the rear end cover 10, still made of copper-tungsten alloy, with an inner diameter of 5.6cm, an outer diameter of 40cm, and a length of 1.38cm. In addition, the material for the shields behind the driver's seat and the side shields is changed to Q235 steel, which is cheaper and has a lower density, while the shape and size remain unchanged. The total weight of the shields is 214.52kg.
[0050] S6: After adopting this shielding scheme, the dose values at personnel's permanent residence locations 1, 2, and 3 are 1.496 mSv, 1.474 mSv, and 0.679 mSv, respectively, all of which are less than the annual radiation dose constraint value. This scheme is a shielding design scheme that meets the requirements.
[0051] S7: The final shielding design consists of 20 shielding elements, which can be divided into two categories according to their relative spatial positions: the shielding area at the stationary location and the shielding area at the short pipe. The shielding area at the stationary location consists of 4 shielding elements, made of Q235 steel: 2 shielding elements behind the driver's seat, 76.5cm long and 30cm wide, with a dimension of 0.3cm; and 2 shielding elements on the side of the driver's seat, 94cm long and 41cm wide, with a dimension of 0.3cm. The shielding area at the short tube consists of 16 shielding elements: 4 end-type shielding elements, made of lead, 13cm in diameter and 4cm in length; 8 sleeve-type shielding elements, including 4 long sleeves made of lead (11.5cm inner diameter, 15cm outer diameter, 14.38cm length) and 4 short sleeves made of copper-tungsten alloy (9.6cm inner diameter, 15cm outer diameter, 1.86cm length); and 4 disc-type shielding elements, made of copper-tungsten alloy, 5.6cm inner diameter, 40cm outer diameter, and 1.38cm length. The total weight of the shielding element is 214.52kg.
[0052] This invention proposes an X-ray shielding design method applicable to complex multi-source structures, which can accurately simulate the superimposed radiation field of multiple radiation sources in complex geometries, and solves the adaptability problem of existing technologies in multi-source synergy and space-constrained environments.
[0053] This invention employs particle transport simulation technology based on the Monte Carlo method, which can simulate radiation physics processes in complex geometries with high fidelity, thereby improving the accuracy and precision of radiation field calculations.
[0054] This invention combines practical engineering needs with comprehensive consideration of materials, processing technology, space constraints, and equipment maintenance to optimize the shielding scheme, ensuring good engineering feasibility while guaranteeing radiation safety, reducing redundant materials, and lowering weight and cost.
[0055] This invention proposes a multi-source complex structure X-ray shielding design method. By establishing a radiation particle transport model based on the Monte Carlo method, it can accurately simulate the superimposed radiation field of multiple X-ray sources in complex geometries, overcoming the shortcomings of traditional methods in handling the synergistic effects of multiple sources and spatial constraints. It is particularly suitable for shielding design in compact spaces. By flexibly applying various variance reduction techniques, the computational efficiency of particle transport simulation is significantly improved. Under the premise of controlling the statistical error to less than 10%, the accuracy and reliability of the simulation results are ensured, providing data support for the refined design of shielding schemes. After multiple rounds of iterative optimization, while ensuring radiation safety, the method fully considers material selection, structural layout, and construction feasibility, so that the final shielding scheme not only meets dose constraints but also has good engineering applicability. The radiation dose in the personnel's permanent residence area is far below the national annual dose limit, effectively ensuring the safety and compliance of the working environment.
[0056] Based on the same concept, the present invention also provides an X-ray shielding design system, including a simulation module, a construction module and an optimization module.
[0057] The simulation module is used to model the actual location and geometry of multiple X-ray sources in radiation particle transport software to obtain a calculation model; the calculation model is used to perform radiation simulation on the target area to obtain the simulated dose value of the target area when it is not shielded.
[0058] The construction module is used to determine the geometry of the shield to be designed based on the calculation model. The shield to be designed includes a target area shield and an X-ray source shield. The material and dimensions of the shield to be designed are obtained based on the comparison between the simulated dose value of the target area when it is not shielded and the set dose limit. The geometry, material and dimensions of the shield to be designed are combined to obtain the shield model.
[0059] The optimization module is used to connect the shielding body model to the calculation model to obtain the shielding calculation model; under the constraint of the set dose limit in the target area, the shielding body model is iteratively optimized through the shielding calculation model.
[0060] The present invention also provides a computer device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the program to implement the above-described X-ray shielding design method.
[0061] The present invention also provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the above-described X-ray shielding design method.
[0062] Although preferred embodiments of the invention have been described, those skilled in the art, upon learning the basic inventive concept, can make other changes and modifications to these embodiments. Therefore, the appended claims are intended to be interpreted as including both the preferred embodiments and all changes and modifications falling within the scope of the invention.
[0063] Obviously, those skilled in the art can make various modifications and variations to this invention without departing from its spirit and scope. Therefore, if these modifications and variations fall within the scope of the claims of this invention and their equivalents, this invention also intends to include these modifications and variations.
Claims
1. An X-ray shielding design method, characterized in that, Includes the following steps: A computational model is obtained by modeling the actual positions and geometries of multiple X-ray sources using radiation particle transport software. The radiation simulation of the target area is performed by a computational model to obtain the simulated dose value of the target area when it is not shielded. The geometric structure of the shield to be designed is determined based on a computational model. The shield to be designed includes a target area shield and an X-ray source shield. The material and dimensions of the shield to be designed are obtained based on the comparison between the simulated dose value of the target area when it is not shielded and the set dose limit. The geometric structure, material and dimensions of the shield to be designed are combined to obtain the shield model. The shielding model is integrated into the calculation model to obtain the shielding calculation model; under the constraint of the set dose limit in the target area, the shielding model is iteratively optimized through the shielding calculation model.
2. The X-ray shielding design method as described in claim 1, characterized in that, Based on the actual locations and geometries of multiple X-ray sources, a computational model is obtained by modeling in radiation particle transport software. The specific steps include: A corresponding geometric model is established based on the geometric structure of multiple X-ray sources, and material is filled into the geometric model; The particle type and source term parameters involved in the simulated transport process are determined by the geometric model to obtain the computational model; the particle type is photon, and the source term parameters include energy spectrum and angular distribution.
3. The X-ray shielding design method as described in claim 1, characterized in that, The target area is a location where people reside. Radiation simulation of the target area is performed using a computational model to obtain the simulated dose value when the target area is not shielded. The specific steps include: The physical quantities of the target region are statistically analyzed using an F-type counter; these physical quantities are particle flux or energy deposition. The physical quantity is converted into the corresponding simulated dose value by combining dose conversion.
4. The X-ray shielding design method as described in claim 1, characterized in that, In the radiation simulation, the variance reduction method is used to control the particle transport process.
5. The X-ray shielding design method as described in claim 1, characterized in that, The materials include lead, copper-tungsten alloy, tungsten-nickel-iron, or Q235 steel.
6. An X-ray shielding design system, characterized in that, include: The simulation module is used to model the actual positions and geometries of multiple X-ray sources in radiation particle transport software to obtain a computational model. The radiation simulation of the target area is performed by a computational model to obtain the simulated dose value of the target area when it is not shielded. The module is used to determine the geometry of the shield to be designed based on the calculation model. The shield to be designed includes a target area shield and an X-ray source shield. The material and dimensions of the shield to be designed are obtained based on the comparison between the simulated dose value of the target area when it is not shielded and the set dose limit. The geometry, material and dimensions of the shield to be designed are combined to obtain the shield model. The optimization module is used to connect the shielding body model to the calculation model to obtain the shielding calculation model; under the constraint of the set dose limit in the target area, the shielding body model is iteratively optimized through the shielding calculation model.
7. A computer device, characterized in that, It includes a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the program to implement the X-ray shielding design method according to any one of claims 1-5.
8. A computer-readable storage medium, characterized in that, The storage medium stores a computer program, which, when executed by a processor, implements the X-ray shielding design method according to any one of claims 1-5.