Intelligent monitoring and evaluation method and equipment for radiation protection performance of hospital proton region

Abstract

A hospital proton zone radiation protection performance intelligent monitoring and evaluation method and device relate to the radiation monitoring field, and the method comprises the following steps: carrying out three-dimensional scanning on an actual building structure and an actual device layout of a target proton treatment center to obtain three-dimensional scanning data, and correcting a preset BIM model by using the three-dimensional scanning data to obtain a three-dimensional building model; after the detection equipment is started, obtaining a measured dose rate level of the target proton treatment center at a preset target measurement point; and performing curve fitting on the measured dose rate level to obtain a measured dose rate curve, fusing the simulated dose rate level and the measured dose rate curve to obtain an actual dose rate level of each building structure position, and mapping the actual dose rate level into a three-dimensional building model to obtain a three-dimensional dose distribution diagram. By implementing the method, the radiation protection level of the proton treatment area of the hospital can be displayed more visually.

Description

Technical Field

[0001] The present application relates to the field of radiation monitoring, and in particular to a method and device for intelligently monitoring and evaluating the radiation protection performance of a hospital proton area. Background Art

[0002] At present, the radiation protection performance evaluation of hospitals with proton therapy areas is divided into two stages: the initial planning stage and the operation stage. Hospitals with proton therapy areas will conduct environmental evaluations in the initial planning stage, especially the evaluation of the radiation protection performance of the proton area. Generally, the 3D BIM software Fluka based on the Monte Carlo method will be used to evaluate the radiation protection performance of the proton area. In the operation stage, the 3D BIM model established by the construction unit's 3D BIM software Revit will be used for construction. After the construction is completed, the radiation performance of the workplace will be evaluated in combination with the detection instruments and requirements. The evaluation method is a combination of instrument measurement and manual recording.

[0003] However, the data from these two periods are relatively independent, and the data measured by instruments during the operation period cannot intuitively display the radiation protection level of the hospital's proton therapy area. Summary of the invention

[0004] The present application provides a method and device for intelligently monitoring and evaluating the radiation protection performance of a hospital's proton treatment area, which is used to more intuitively display the radiation protection level of a hospital's proton treatment area.

[0005] In a first aspect, the present application provides an intelligent monitoring and evaluation method for the radiation protection performance of a hospital proton area, which is applied to intelligent monitoring and evaluation equipment. The method includes: obtaining the actual building structure and actual equipment layout of a target proton therapy center, performing a three-dimensional scan of the actual building structure and the actual equipment layout to obtain three-dimensional scanning data, and correcting a preset BIM model based on the three-dimensional scanning data to obtain a three-dimensional building model; after the detection equipment is turned on, obtaining a measured dose rate level of the target proton therapy center at a preset target measurement point; performing curve fitting on the measured dose rate level to obtain a measured dose rate curve, merging the simulated dose rate level and the measured dose rate curve to obtain the actual dose rate level of each building structure position, and the simulated dose rate level is simulated in a Monte Carlo program; mapping the actual dose rate level to the three-dimensional building model to obtain a three-dimensional dose distribution map, which includes a dose isosurface, a dose value at each building structure position, and a dose distribution slice map of any plane.

[0006] By adopting the above technical solution, the three-dimensional scanning data of the actual building structure and equipment layout of the target proton therapy center is obtained, and the preset BIM model is corrected according to the three-dimensional scanning data to obtain a three-dimensional building model. After the detection equipment is turned on, the measured dose rate level is obtained, and a curve fitting is performed on it to obtain a measured dose rate curve. The simulated dose rate level and the measured dose rate curve are then merged to obtain the actual dose rate level of each building structure position. Finally, the actual dose rate level is mapped to the three-dimensional building model to obtain a three-dimensional dose distribution map, including dose isosurfaces, dose values ​​at each building structure position, and dose distribution slices on any plane. This can intuitively and comprehensively display the radiation distribution of the proton therapy center, and help to accurately evaluate the radiation protection performance in the entire proton zone space.

[0007] In combination with some embodiments of the first aspect, in some embodiments, before the step of obtaining the actual building structure and actual equipment layout of the target proton therapy center and performing three-dimensional scanning on the actual building structure and the actual equipment layout to obtain three-dimensional scanning data, the method also includes: modeling the target proton therapy center in a Monte Carlo program based on a preset building structure and a preset equipment layout to obtain a three-dimensional grid model of the target proton therapy center; performing dose rate level simulation in the Monte Carlo program based on building material data of each building structure part in the three-dimensional grid model and treatment parameters of the proton therapy equipment in the target proton therapy center to obtain a simulated dose rate level at each building structure position in the building structure part, the building material data including density, elemental composition and mass content, and the treatment parameters including target material and beam intensity.

[0008] By adopting the above technical scheme, the target proton therapy center is modeled in the Monte Carlo program based on the preset building structure and equipment layout to obtain a three-dimensional grid model. In the Monte Carlo program, the dose rate level is simulated based on the building material data (including density, element composition, mass content, etc.) of each building structure part in the three-dimensional grid model and the treatment parameters of the proton therapy equipment in the target proton therapy center (including target material and beam intensity), and the simulated dose rate level of each building structure position in the building structure part is obtained, which can accurately reflect the actual situation of the proton therapy center and make the simulation results more reliable.

[0009] In combination with some embodiments of the first aspect, in some embodiments, the step of fusing the simulated dose rate level and the measured dose rate curve to obtain the actual dose rate level of each building structure position specifically includes: inputting each building structure position in the three-dimensional grid model into a preset credibility assessment model to obtain the simulation credibility corresponding to all building structure positions in the three-dimensional grid model, and normalizing the simulation credibility to obtain an initial fusion weight; calculating the distance attenuation coefficient of each building structure position according to the initial fusion weight and the distance from the building structure position to the nearest preset target measurement point; multiplying the initial fusion weight by the distance attenuation coefficient to obtain the final fusion weight of each building structure position; and based on the final fusion weight, weighted averaging the simulated dose rate level and the corresponding position dose rate obtained by interpolation according to the measured dose rate curve to obtain the actual dose rate level of each building structure part.

[0010] By adopting the above technical solution, each building structure position in the three-dimensional grid model is input into the preset credibility assessment model to obtain the simulation credibility corresponding to all building structure positions, and normalization is performed to obtain the initial fusion weight. The distance attenuation coefficient is calculated according to the initial fusion weight and the distance from the building structure position to the nearest preset target measurement point. The initial fusion weight is multiplied by the distance attenuation coefficient to obtain the final fusion weight of each building structure position. Based on the final fusion weight, the simulated dose rate level and the dose rate at the corresponding position obtained by interpolation according to the measured dose rate curve are weighted averaged to obtain the actual dose rate level of each building structure part, so that the calculation of the actual dose rate level is more accurate, thereby more accurately evaluating the radiation protection performance of concrete.

[0011] In combination with some embodiments of the first aspect, in some embodiments, the step of mapping the actual dose rate level to the three-dimensional building model to obtain a three-dimensional dose distribution map specifically includes: comparing the three-dimensional grid model with the three-dimensional building model, identifying the newly added structural part in the three-dimensional building model, and creating a new data point in the newly added structural part; assigning an initial dose value to the newly added data point based on the actual dose rate level; obtaining building material data of the newly added structural part in the three-dimensional building model, and calculating the attenuation coefficient corresponding to the initial dose value based on the building material data, the building material data including material parameters and geometric characteristics; multiplying the attenuation coefficient by the initial dose value to obtain a simulated dose level corresponding to the newly added data point; mapping the numerical value corresponding to the actual dose rate level to the three-dimensional building model, and mapping the numerical value corresponding to the simulated dose level to the newly added structural part to obtain a three-dimensional dose distribution map.

[0012] By adopting the above technical solution, the three-dimensional grid model is compared with the three-dimensional building model, and the newly added structural part in the three-dimensional building model can be accurately identified. After creating new data points in the newly added structural part, the initial dose value is assigned to the new data point based on the actual dose rate level, the building material data of the newly added structural part in the three-dimensional building model is obtained, and the attenuation coefficient corresponding to the initial dose value is calculated based on the data. The attenuation coefficient is multiplied by the initial dose value to obtain the simulated dose level corresponding to the newly added data point, the numerical value corresponding to the actual dose rate level is mapped to the three-dimensional building model, and the numerical value corresponding to the simulated dose level is mapped to the newly added structural part to obtain a complete three-dimensional dose distribution map, which can accurately reflect the radiation dose distribution of the entire building, and provide more accurate data support for the intelligent monitoring and evaluation of the radiation protection performance of concrete.

[0013] In combination with some embodiments of the first aspect, in some embodiments, the step of simulating the dose rate level in a Monte Carlo program based on the building material data of each building structure part in the three-dimensional grid model and the treatment parameters of the proton therapy equipment in the target proton therapy center to obtain the simulated dose rate level of each building structure position in the building structure part specifically includes: obtaining the display accuracy requirement of each building structure part, dividing the three-dimensional grid model into spatial units based on the display accuracy requirement to obtain grid units; matching the corresponding simulation parameters of the Monte Carlo program for each grid unit, and the simulation parameters include spatial resolution, statistical error threshold and number of iterations; inputting the building material data and the treatment parameters into the Monte Carlo program, performing dose rate level simulation calculation for each grid unit, and obtaining the simulated dose rate level of each grid unit; mapping the simulated dose rate level to the corresponding building structure position in the three-dimensional grid model to obtain the simulated dose rate level of each building structure position in the building structure part.

[0014] By adopting the above technical solution, the display accuracy requirements of each building structure part are obtained, and the three-dimensional grid model is divided into spatial units based on the requirements to obtain suitable grid units, so that the model can meet the accuracy requirements of different structural parts. The simulation parameters of the corresponding Monte Carlo program are matched for each grid unit, including spatial resolution, statistical error threshold and number of iterations, etc., to ensure the accuracy and efficiency of the simulation calculation. The building material data and treatment parameters are input into the Monte Carlo program, and the dose rate level simulation calculation is performed for each grid unit to obtain the simulated dose rate level of each grid unit. The simulated dose rate level is mapped to the corresponding building structure position in the three-dimensional grid model to obtain the simulated dose rate level of each building structure position in the building structure part, thereby realizing the accurate simulation of the radiation dose level of the entire building structure.

[0015] In combination with some embodiments of the first aspect, in some embodiments, after the step of simulating the dose rate level in the Monte Carlo program based on the building material data of each building structure part in the three-dimensional grid model and the treatment parameters of the proton therapy equipment in the target proton therapy center to obtain the simulated dose rate level of each building structure position in the building structure part, the method also includes: if the simulated dose rate level of the target building position exceeds the preset simulation threshold, performing a local correction on the target building position, and the local correction includes increasing the wall thickness and increasing the wall material density; based on the locally corrected building material data, re-simulating the dose rate level in the Monte Carlo program to obtain a corrected dose rate level; repeating the local correction and the dose rate level simulation until the simulated dose rate level at the target building position does not exceed the preset simulation threshold.

[0016] By adopting the above technical solution, if the simulated dose rate level at the target building location exceeds the preset simulation threshold, the target building location is locally corrected, such as increasing the wall thickness and increasing the wall material density, which can effectively reduce the radiation dose level. Based on the locally corrected building material data, the dose rate level simulation is re-performed in the Monte Carlo program to obtain the corrected dose rate level to verify the effectiveness of the correction measures. Repeat the process of local correction and dose rate level simulation until the simulated dose rate level at the target building location does not exceed the preset simulation threshold, ensuring that the radiation protection performance of the building meets safety standards. In this way, the problem of excessive radiation dose can be discovered and resolved in a timely manner, thereby improving the safety and reliability of the proton therapy center.

[0017] In combination with some embodiments of the first aspect, in some embodiments, after the step of mapping the actual dose rate level to the three-dimensional building model to obtain a three-dimensional dose distribution map, the method also includes: detecting whether there is a building location in the three-dimensional dose distribution map that exceeds a preset dose rate level threshold; if so, sending a prompt message to the target client, the prompt message including location information and dose rate level data of the building location.

[0018] By adopting the above technical solution, after obtaining the three-dimensional dose distribution map, it is detected whether there is a building location in the map that exceeds the preset dose rate level threshold. If there is a building location that exceeds the threshold, a prompt message is sent to the target client. The prompt message contains the location information and dose rate level data of the building location, so that relevant personnel can obtain key information in a timely and accurate manner to take corresponding measures.

[0019] In a second aspect, an embodiment of the present application provides an intelligent monitoring and evaluation device, which includes: one or more processors and a memory; the memory is coupled to the one or more processors, the memory is used to store computer program code, the computer program code includes computer instructions, and the one or more processors call the computer instructions to enable the intelligent monitoring and evaluation device to perform the method described in the first aspect and any possible implementation method of the first aspect.

[0020] In a third aspect, an embodiment of the present application provides a computer program product comprising instructions, which, when the computer program product is run on an intelligent monitoring and evaluation device, enables the intelligent monitoring and evaluation device to perform the method described in the first aspect and any possible implementation method of the first aspect.

[0021] In a fourth aspect, an embodiment of the present application provides a computer-readable storage medium, comprising instructions. When the instructions are executed on an intelligent monitoring and evaluation device, the intelligent monitoring and evaluation device executes the method described in the first aspect and any possible implementation method of the first aspect.

[0022] It is understandable that the intelligent monitoring and evaluation device provided in the second aspect, the computer program product provided in the third aspect, and the computer storage medium provided in the fourth aspect are all used to execute the method provided in the embodiment of the present application. Therefore, the beneficial effects that can be achieved can refer to the beneficial effects in the corresponding method, which will not be repeated here.

[0023] One or more technical solutions provided in the embodiments of the present application have at least the following technical effects or advantages: 1. This application obtains three-dimensional scanning data of the actual building structure and equipment layout of the target proton therapy center, and modifies the preset BIM model according to the three-dimensional scanning data to obtain a three-dimensional building model. After the detection equipment is turned on, the measured dose rate level is obtained, and a curve fitting is performed to obtain a measured dose rate curve. The simulated dose rate level and the measured dose rate curve are then merged to obtain the actual dose rate level of each building structure position. Finally, the actual dose rate level is mapped to the three-dimensional building model to obtain a three-dimensional dose distribution diagram, including dose isosurfaces, dose values ​​at each building structure position, and dose distribution slices on any plane. This can intuitively and comprehensively display the radiation distribution of the proton therapy center, and help to accurately evaluate the radiation protection performance in the entire proton zone space.

[0024] 2. This application models the target proton therapy center in a Monte Carlo program based on a preset building structure and equipment layout to obtain a three-dimensional grid model. In the Monte Carlo program, the dose rate level is simulated based on the building material data (including density, element composition, mass content, etc.) of each building structure part in the three-dimensional grid model and the treatment parameters (including target material and beam intensity) of the proton therapy equipment in the target proton therapy center, and the simulated dose rate level of each building structure position in the building structure part is obtained, which can accurately reflect the actual situation of the proton therapy center and make the simulation results more reliable.

[0025] 3. The present application obtains the simulation credibility corresponding to all building structure positions by inputting each building structure position in the three-dimensional grid model into a preset credibility assessment model, and performs normalization processing to obtain the initial fusion weight. The distance attenuation coefficient is calculated according to the initial fusion weight and the distance from the building structure position to the nearest preset target measurement point. The initial fusion weight is multiplied by the distance attenuation coefficient to obtain the final fusion weight of each building structure position. Based on the final fusion weight, the simulated dose rate level and the dose rate at the corresponding position obtained by interpolation according to the measured dose rate curve are weighted averaged to obtain the actual dose rate level of each building structure part, so that the calculation of the actual dose rate level is more accurate and reasonable, thereby more accurately evaluating the radiation protection performance of concrete. BRIEF DESCRIPTION OF THE DRAWINGS

[0026] Figure 1 It is a flow chart of a method for intelligently monitoring and evaluating the radiation protection performance of a hospital proton zone in an embodiment of the present application; Figure 2 This is another flow chart of the method for intelligently monitoring and evaluating the radiation protection performance of the proton area in a hospital in an embodiment of the present application; Figure 3 It is a schematic diagram of the structure of a physical device of the intelligent monitoring and evaluation equipment in the embodiment of the present application. DETAILED DESCRIPTION

[0027] The terms used in the following embodiments of the present application are only for the purpose of describing specific embodiments, and are not intended to be used as limitations to the present application. As used in the specification of the present application, the singular expressions "one", "a kind of", "above", "the" and "this" are intended to also include plural expressions, unless there is a clear indication to the contrary in the context. It should also be understood that the term "and / or" used in the present application refers to any or all possible combinations comprising one or more of the listed items.

[0028] In the following, the terms "first" and "second" are used for descriptive purposes only and are not to be understood as suggesting or implying relative importance or implicitly indicating the number of the indicated technical features. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of the features, and in the description of the embodiments of the present application, unless otherwise specified, "plurality" means two or more.

[0029] For ease of understanding, the application scenarios of the embodiments of the present application are introduced below.

[0030] At present, hospitals with proton therapy areas will conduct environmental assessments in the early stages of planning, especially assessments of the radiation protection performance of the proton area. The assessments generally use the three-dimensional BIM software Fluka based on the Monte Carlo method. When the proton therapy area is built, due to the radiation protection requirements of the hospital's proton area, the equipment pipelines need to be accurately pre-buried, and because the volume of radiation-proof concrete is large, it needs to be constructed in sections. At this time, the construction unit will use Revit to establish a three-dimensional BIM model to guide the entire construction process. During the hospital operation stage, the radiation performance of the workplace needs to be evaluated according to requirements, and the evaluation method is a combination of instrument measurement and manual recording.

[0031] In this way, it is difficult to accurately assess the impact of these changes on the overall radiation protection effectiveness. The lack of intuitive visualization tools makes it difficult for management to quickly understand and make decisions on potential radiation risk areas.

[0032] By adopting the intelligent monitoring and evaluation method proposed in this application, the treatment center is scanned using 3D scanning technology in the early stage of planning to generate a 3D building model. The scanned model in the early stage of planning is matched with the initial BIM design model to identify structural changes during the construction process. Radiation detectors are installed at key locations, and data is transmitted to the monitoring system in real time. The theoretical radiation distribution data of Monte Carlo simulation and real-time measurement data are combined for data fusion to generate a 3D radiation distribution map of the treatment center, including dose isosurfaces and dose distribution slices of any plane, and the radiation level data of each location can be displayed through the interface.

[0033] For ease of understanding, the following describes the process of the method provided by this implementation in combination with the above scenario. Figure 1 , which is a flow chart of the intelligent monitoring and evaluation method of the radiation protection performance of the proton area of ​​a hospital in an embodiment of the present application.

[0034] S101. Acquire the actual building structure and actual equipment layout of the target proton therapy center, perform three-dimensional scanning on the actual building structure and the actual equipment layout to obtain three-dimensional scanning data, and modify the preset BIM model based on the three-dimensional scanning data to obtain a three-dimensional building model.

[0035] Among them, the target proton therapy center refers to a specific proton therapy center that requires intelligent monitoring and evaluation of concrete radiation protection performance. The actual building structure refers to the proton therapy center during the operation period, that is, the completed building structure, including walls, floors, ceilings, etc. The actual equipment layout is used to indicate the placement of proton therapy equipment in the treatment center during the operation period. The preset BIM model refers to the BIM model for construction established using Revit software. The three-dimensional building model refers to the final three-dimensional digital model containing the actual building structure and equipment layout information. The three-dimensional building model can accurately restore the physical project.

[0036] Specifically, before starting to monitor the radiation protection performance of a proton therapy center, it is necessary to first obtain the actual situation of the treatment center, obtain the actual building structure and equipment layout information of the target proton therapy center through on-site surveys or the use of measuring equipment, and then use a 3D laser scanner or other 3D scanning equipment to comprehensively scan the entire treatment center to generate 3D point cloud data containing the building structure and equipment layout. Next, the obtained 3D scanning data is compared with the pre-prepared BIM model. After finding any differences, the preset BIM model is corrected and adjusted based on the 3D scanning data. Through this data fusion and calibration process, a 3D building model is finally generated.

[0037] For example, during on-site scanning, the scanning can be divided into large-area overall scanning and special node precise scanning. The appropriate scanning radius is selected according to the actual situation of the scanning area. The large-area overall scanning is to scan the completion status of the steel bars, pipelines, embedded parts and the surrounding conditions of the entire node. The precise scanning of special nodes includes a certain treatment chamber, accelerator room or complex wall columns and pipelines. Three-dimensional scanning can generate three-dimensional coordinate information (XYZ), color value RGB, laser reflection intensity information and other data, compare the exported scanning data with the relevant data of the BIM model, and modify the BIM model based on the scanning data until the data in the BIM model conforms to the three-dimensional scanning data. After correction, the three-dimensional building model is obtained.

[0038] The specific method of modifying the preset BIM model based on the 3D scanning data is: use a 3D laser scanner or other 3D scanning equipment to scan the target proton therapy center. The scanning is divided into large-area overall scanning and special node precision scanning. The large-area overall scanning covers the completion of the steel bars, pipelines, embedded parts and surrounding conditions of the entire node. The special node precision scanning targets a certain key part such as a treatment chamber, accelerator room or complex wall column pipelines. The appropriate scanning radius is selected according to the actual situation of the scanning area. The scanning can generate 3D coordinate information (XYZ), color value RGB, laser reflection intensity information and other data; The 3D point cloud data obtained by scanning is preprocessed, and the processed 3D scan data is compared with the preset BIM model established in advance using Revit software. During the comparison process, the key features of the building structure are used as the benchmark, such as the location, thickness, material type of the wall, the structure of the floor and ceiling, etc. For each key feature, the difference value between the 3D scan data and the BIM model data is calculated. For example, for the wall position, if the scan data shows that the deviation between the actual position of the wall and the position in the BIM model exceeds a certain threshold (such as 5 cm), the difference is recorded, and the preset BIM model is structurally adjusted according to the comparison results. If a wall position deviation is found, the position of the wall is moved in the BIM model to match the scan data. For structural parts that actually exist but are missing in the BIM model, such as newly added small equipment support structures, add corresponding structural elements in the BIM model. For structural dimensions that are different from those in the BIM model, such as the actual wall thickness is thicker or thinner than that recorded in the BIM model, modify the wall thickness parameters in the BIM model to make it consistent with the actual scan data. When the scan finds that the actual building material is different from the preset material in the BIM model, update the material property information in the BIM model. For example, if the actual wall material is detected as a new type of radiation-proof concrete, but it is recorded as ordinary concrete in the BIM model, modify the relevant parameters of the wall material in the BIM model, such as density, element composition, etc.

[0039] It should be noted that the 3D building model is obtained by 3D scanning the actual building structure and actual equipment layout of the target proton therapy center to obtain 3D scanning data, and then modifying the preset BIM model (such as the model established using Revit software) based on the 3D scanning data. It takes the geometric structure of the actual building as the basic framework and contains accurate information on the layout of building components such as walls, floors, ceilings, and actual equipment such as proton therapy equipment. The specific parameters of the 3D building model include geometric parameters and material parameters. The geometric parameters include: wall thickness, accurate to the millimeter level. The wall thickness in different areas may vary due to different radiation protection requirements. For example, the wall thickness in the critical protection area may be between 800-1200mm, while that in the non-critical area may be between 200-600mm. Room size. The length, width and height of the room shall be based on actual measurements and shall be accurate to the centimeter level. For example, the length of the proton accelerator room may be between 10-15 meters, the width between 8-12 meters, and the height between 4-6 meters. Equipment size and position. The size of the proton therapy equipment is determined according to the equipment model, and the position is based on the actual installation location, accurate to the centimeter level. For example, a certain type of proton accelerator may be between 5-8 meters long and 3-5 meters wide. Its installation position in the treatment room may be within 3-5 meters of a corner. The material parameters include: wall material. For radiation-proof walls, the material properties include density, element composition, and mass content. For example, the density of the radiation-proof concrete material used may be between 2.2-2.8g / cm³, and the element composition may include elements such as lead and boron. The mass content varies according to different formulas. The material properties of floor and ceiling materials also include relevant parameters such as density, element composition, and mass content, which are determined according to radiation protection and structural requirements. For example, the floor uses a composite material containing a certain proportion of heavy metals, and its density is between 1.8-2.5g / cm³.

[0040] The geometric shape and position of the building components and equipment in the model must be completely consistent with the actual building and equipment layout, and the error must be within an acceptable range. For example, the wall position deviation must not exceed ±5 cm, and the equipment position deviation must not exceed ±3 cm. The material properties recorded in the model must be consistent with the actual material properties used, and the error must be within an acceptable range. For example, the material density error must not exceed ±0.2g / cm³. The element composition and mass content errors are determined based on the actual situation and detection accuracy, but should ensure that they do not affect the evaluation of radiation protection performance.

[0041] S102: After the detection device is turned on, a measured dose rate level of a target proton therapy center at a preset target measurement point is obtained.

[0042] Among them, the detection equipment refers to an instrument used to measure the radiation dose rate, such as a portable radiation detector; the preset target measurement point refers to a predetermined specific location where the radiation dose rate measurement is required; the measured dose rate level refers to the radiation dose rate value measured at the specific location, usually in units of μSv / h (microsievert / hour).

[0043] Specifically, the preset target measurement points are usually selected in areas that are most affected by radiation, or in locations that must be monitored according to relevant standards and specifications. For example, measurement points are set in the proton accelerator room, main control room, rotation therapy room, etc. The detection equipment will obtain the dose rate level data of these measurement points in real time and record these data.

[0044] S103, curve fitting is performed on the measured dose rate level to obtain a measured dose rate curve, and the simulated dose rate level and the measured dose rate curve are merged to obtain the actual dose rate level at each building structure position, where the simulated dose rate level is simulated in a Monte Carlo program.

[0045] Among them, the measured dose rate level represents the radiation dose rate value actually measured at the preset target measurement point, curve fitting refers to fitting discrete measurement data points into a continuous function curve through mathematical methods, and the measured dose rate curve is used to represent the continuous dose rate distribution function obtained after fitting. The simulated dose rate level refers to the theoretical dose rate distribution obtained by Monte Carlo simulation calculation, and the Monte Carlo program refers to professional software used for Monte Carlo simulation calculations, such as MCNP or Geant4. The actual dose rate level refers to the more accurate dose rate distribution obtained by fusing the measured data and simulated data.

[0046] Specifically, first, the measured dose rate level is curve-fitted using the least squares method or spline interpolation to obtain a continuous measured dose rate curve, which is used to describe the trend of dose rate changes in space. The Monte Carlo simulation program is used to calculate the theoretical simulated dose rate level based on the building structure, material properties and radiation source parameters of the treatment center. The measured dose rate curve and the simulated dose rate level are then data-fused, taking measurement errors and simulation accuracy into comprehensive consideration.

[0047] In some embodiments, the acquisition of the measured dose rate curve and the determination of the actual dose rate level can be achieved in a variety of ways: Optionally, the measured dose rate level is first fitted using a polynomial regression method to obtain a measured dose rate curve represented by a polynomial function; then the geometric model and material composition of the proton therapy center are established using MCNP software, and a Monte Carlo simulation is performed to obtain a simulated dose rate level; then the Bayesian inference method is used, the measured dose rate curve is used as a prior distribution, and the simulated dose rate level is used as a likelihood function, and the posterior distribution is calculated to obtain the actual dose rate level. Optionally, the measured dose rate level is first spatially interpolated using a radial basis function interpolation method to obtain a continuous measured dose rate distribution field; then the Geant4 toolkit is used to construct a physical model of the proton therapy center, and the particle transport process is simulated to obtain a simulated dose rate field; then data assimilation technology, such as ensemble Kalman filtering, is used to dynamically fuse the measured dose rate field and the simulated dose rate field to obtain the actual dose rate level at each building structure location. It is understandable that other methods can also be used, which are not limited here.

[0048] S104, mapping the actual dose rate level to the three-dimensional building model to obtain a three-dimensional dose distribution map, which includes a dose isosurface, a dose value at each building structure position, and a dose distribution slice map of any plane.

[0049] Among them, the actual dose rate level represents the accurate dose rate distribution obtained after fusing the measured data and the simulated data. The three-dimensional building model refers to the digital model obtained in the previous step that contains the actual building structure and equipment layout information. The three-dimensional dose distribution map is used to represent the distribution of dose rate in three-dimensional space. The dose isosurface refers to the three-dimensional surface formed by spatial points with the same dose rate. The dose distribution slice map represents the two-dimensional dose rate distribution on any plane.

[0050] In some embodiments, the mapping of the actual dose rate level to the three-dimensional dose distribution map can be achieved in a variety of ways: optionally, first use a three-dimensional interpolation algorithm to expand the discrete actual dose rate level data to the entire three-dimensional space; then use volume rendering technology, such as ray projection method, to render the interpolated continuous dose rate field into the three-dimensional building model; then generate multiple dose isosurfaces and distinguish them with different colors, and finally use the interactive slicing function to allow the user to obtain a two-dimensional dose distribution slice map at any position and direction. Optionally, first convert the actual dose rate level data into a voxel data structure, each voxel corresponds to a dose rate value; then calculate the dose rate distribution of the entire three-dimensional space, and use the isosurface extraction algorithm to generate multiple dose isosurfaces, and finally implement a real-time volume data cutting function to support users to obtain dose distribution slice maps at any position by dragging and dropping. It is understandable that other methods can also be used to achieve the mapping of the actual dose rate level to the three-dimensional dose distribution map, which is not limited here.

[0051] The following is a more detailed description of the process of the method provided by this implementation. Figure 2 , is another flow chart of the method for intelligently monitoring and evaluating the radiation protection performance of the proton area in a hospital in an embodiment of the present application.

[0052] S201. Modeling the target proton therapy center in a Monte Carlo program based on a preset building structure and a preset equipment layout to obtain a three-dimensional grid model of the target proton therapy center.

[0053] The preset building structure refers to the building structure specified in the design drawings of the proton therapy center in the initial planning stage, including the size, material and location information of components such as walls, floors and ceilings. The preset equipment layout represents the planned placement and configuration of the proton therapy equipment in the treatment center in the initial planning stage. The Monte Carlo program refers to professional software used for Monte Carlo simulation calculations, such as MCNP (Monte Carlo N-Particle) or Geant4. The target proton therapy center refers to a specific proton therapy center that needs to be monitored and evaluated for radiation protection performance. The three-dimensional mesh model refers to a BIM model composed of multiple small geometric units.

[0054] First, the CAD format data file of the preset building structure and preset equipment layout is read, including the building plan, elevation and equipment layout. Then, the two-dimensional drawing information is converted into a three-dimensional geometric model. The conversion process includes the physical property data of the building materials, such as density and element composition. Then, the converted three-dimensional geometric model is imported into the Monte Carlo program through the application program interface of the Monte Carlo program. Inside the Monte Carlo program, the imported model is meshed to divide the entire space into a large number of small grid units, and each grid unit is assigned corresponding material properties and geometric information. Finally, the generated grid model is quality checked to eliminate any grid overlap or gaps. For a standard proton therapy room, the wall is usually divided into cubic grid units with a side length of 1 mm to 10 mm.

[0055] It should be noted that the three-dimensional grid model is constructed in the Monte Carlo program based on the preset building structure and preset equipment layout. It is composed of multiple small geometric units (grid units). These grid units are arranged according to certain rules to form a digital representation of the building structure and equipment layout of the target proton therapy center in the early planning stage. Each grid unit in the model is assigned corresponding material properties and geometric information.

[0056] The specific parameters of the three-dimensional grid model include grid unit parameters and material property parameters. The grid unit parameters include the size and number of grids, and the material property parameters include density, element composition and mass content. For example, for key protective structures such as walls, the grid unit can be set to a cubic grid unit with a side length of 1mm-10mm; for non-critical areas, the grid unit size may be increased to 10cm×10cm×10cm. For ordinary concrete materials, the density may be between 2.0-2.4g / cm³; for radiation-proof concrete, the density may be between 2.2-2.8g / cm³. The element composition and mass content are determined according to the actual composition of the building materials.

[0057] The arrangement and combination of grid cells should be able to accurately represent the geometric shape of the building structure and equipment layout, with an acceptable error. For example, for the representation of wall positions, the error should not exceed ±1cm; for the representation of equipment positions, the error should not exceed ±5cm. The material properties assigned to each grid cell should be consistent with the actual building materials, with an acceptable error. For example, the material density error should not exceed ±0.2g / cm³, and the element composition and mass content errors should be determined based on the actual situation and detection accuracy.

[0058] S202. Performing a dose rate level simulation in a Monte Carlo program based on the building material data of each building structure part in the three-dimensional grid model and the treatment parameters of the proton therapy equipment in the target proton therapy center to obtain a simulated dose rate level at each building structure position in the building structure part, wherein the building material data includes density, element composition and mass content, and the treatment parameters include target material and beam intensity.

[0059] In some embodiments, the step specifically includes: The display accuracy requirement of each building structure part is obtained, and the three-dimensional grid model is divided into spatial units based on the display accuracy requirement to obtain grid units.

[0060] The simulation parameters of the corresponding Monte Carlo procedure are matched for each grid unit, and the simulation parameters include spatial resolution, statistical error threshold and number of iterations.

[0061] The building material data and the treatment parameters are input into the Monte Carlo program, and a dose rate level simulation calculation is performed on each grid unit to obtain a simulated dose rate level of each grid unit.

[0062] The simulated dose rate level is mapped to the corresponding building structure position in the three-dimensional grid model to obtain the simulated dose rate level of each building structure position in the building structure part.

[0063] Specifically, the display accuracy requirement indicates the degree of detail required for each part of the building structure when it is displayed in a three-dimensional model. The three-dimensional grid model refers to a digital three-dimensional representation composed of multiple geometric units. The spatial unit division refers to the process of dividing the three-dimensional space into smaller, regular geometric units. The grid unit refers to the smallest geometric unit obtained after the spatial unit division. The simulation parameters of the Monte Carlo program include key parameters that control the simulation accuracy and efficiency. The spatial resolution indicates the minimum spatial scale of the simulation calculation. The statistical error threshold specifies the acceptable error range of the simulation results. The number of iterations determines the number of repetitions of the simulation calculation. The building material data includes the physical and chemical properties of each part of the building structure. The treatment parameters include the energy, intensity and other related parameters of the proton beam.

[0064] Specifically, the display accuracy requirements of each building structure are obtained, and the three-dimensional grid model is divided into spatial units based on these requirements. The specific implementation method can be to use an adaptive grid division algorithm to dynamically adjust the grid density according to the importance and complexity of different areas. For example, for key protective structures such as walls, a higher grid density can be used, and the grid size can be set to 1cm×1cm×1cm; while for non-critical areas, a larger grid size can be used, such as 10cm×10cm×10cm.

[0065] Match the corresponding Monte Carlo simulation parameters for each grid cell. Parameter settings can be implemented based on predefined rules or lookup tables. For example, for areas with high precision requirements, the spatial resolution can be set to 0.1mm, the statistical error threshold can be set to 1%, and the number of iterations can be set to 10^6 times; for areas with low precision requirements, the spatial resolution can be set to 1mm, the statistical error threshold can be set to 5%, and the number of iterations can be set to 10^4 times.

[0066] Input building material data and treatment parameters into the Monte Carlo program. Building material data includes density, element composition, atomic number, etc., which can be obtained through database query. Treatment parameters such as proton beam energy can be set to 60-250MeV and beam intensity to 1-5nA. Dose rate level simulation calculation is performed for each grid cell, and parallel computing technology is used to improve calculation efficiency.

[0067] The simulated dose rate level is mapped to the corresponding building structure position in the three-dimensional grid model. The mapping process can use spatial indexing technology to locate the spatial position corresponding to each dose rate value, obtain the simulated dose rate level of each building structure position in the building structure part, and form a complete three-dimensional dose distribution data set.

[0068] Among them, steps S201 to S202 are completed before the construction of the target proton therapy center, and professional software for Monte Carlo simulation calculations is used to perform numerical simulation of radiation levels on the preset modeling of the target proton therapy center.

[0069] S203, obtaining the actual building structure and actual equipment layout of the target proton therapy center, performing a three-dimensional scan on the actual building structure and the actual equipment layout to obtain three-dimensional scanning data, and modifying the preset BIM model based on the three-dimensional scanning data to obtain a three-dimensional building model.

[0070] It can be understood that this step is similar to step S101 and will not be described in detail here.

[0071] In step S203, the target proton therapy center has completed construction based on the three-dimensional building model, so the fineness of the three-dimensional building model is greater than the three-dimensional grid model performed before construction.

[0072] S204. After the detection device is turned on, a measured dose rate level of the target proton therapy center at a preset target measurement point is obtained.

[0073] It can be understood that this step is similar to step S102 and will not be described in detail here.

[0074] S205: input each building structure position in the three-dimensional grid model into a preset credibility evaluation model to obtain simulation credibility corresponding to all building structure positions in the three-dimensional grid model, and normalize the simulation credibility to obtain an initial fusion weight.

[0075] The preset credibility assessment model is an algorithm or mathematical model used to evaluate the reliability of simulation results. Simulation credibility is an indicator to measure the accuracy of simulation results, usually expressed as a value between 0 and 1. Normalization is a mathematical operation that scales data to a specific interval (such as 0 to 1). The initial fusion weight is the initial weight coefficient when the simulation results are fused with the measured data.

[0076] In this step, the device first inputs the coordinates of each building structure position in the 3D grid model into a pre-trained credibility assessment model. The model evaluates the reliability of the simulation results of each position based on multiple factors (such as simulation parameters, grid accuracy, material properties, etc.) and outputs a credibility value between 0 and 1. For example, positions close to the proton beam source have higher credibility, while positions far from the source or in complex structures have lower credibility. Subsequently, the device normalizes the credibility values ​​of all positions, linearly maps them to the range of 0 to 1, and obtains the initial fusion weights.

[0077] It should be noted that the training process and parameter determination process of the preset credibility assessment model are as follows: in the data collection stage, a large amount of known building structure data of different types and sizes is collected, including information related to its three-dimensional grid model and the corresponding actual measurement data. For each building structure, the feature information corresponding to the simulation data and the actual measurement data is extracted. The simulation data features include simulation parameters such as spatial resolution, statistical error threshold, number of iterations, as well as the grid division size (grid accuracy) of different regions and material properties such as density, element composition, and mass content of building materials. The actual measurement data is data such as radiation dose rate measured at various key locations of the building structure.

[0078] The feature information corresponding to the simulated data and the actual measured data is combined as the input of the training sample. For example, a training sample may contain the simulation parameters of a specific location of a building structure (such as a spatial resolution of 0.5 mm, a statistical error threshold of 3%, and 50,000 iterations), grid accuracy (such as the grid size of the area where the location is located is 5 cm × 5 cm × 5 cm), and material properties (such as the building material density is 2.5 g / cm³, the element composition is [specific element composition], and the mass content is [specific mass content]).

[0079] The degree of difference between the actual measurement results and the simulation results is used as the output label of the training sample (i.e., the simulation credibility). The degree of difference can be calculated in a variety of ways, such as calculating the relative error between the actual measured dose rate and the simulated dose rate, and mapping the relative error to the interval of 0-1 as the simulation credibility. If the actual measured dose rate is exactly the same as the simulated dose rate, the simulation credibility is 1; if the difference is large, the simulation credibility is close to 0.

[0080] Use the back propagation algorithm to train the preset credibility assessment model. Input the constructed training samples into the model in sequence. The model predicts based on the input feature information to obtain the predicted simulation credibility. The predicted simulation credibility is compared with the actual simulation credibility (output label) in the training sample to calculate the loss function. The loss function can be the mean square error (MSE) function, which can measure the average square error between the predicted value and the true value. According to the value of the loss function, the weight and bias of the model are adjusted through the back propagation algorithm. Starting from the output layer, the error is back propagated layer by layer, and the weights and biases of each layer of neurons are updated to make the prediction results of the model closer to the actual simulation credibility. Repeat the above training process and perform multiple iterations on a large number of training samples until the loss function value of the model converges to a smaller value.

[0081] Determine the number of neurons through experiments and verification. Start with a smaller number of neurons, such as 10, and gradually increase the number of neurons to observe the performance of the model on the verification data set. The verification data set is a part of the data reserved from the collected building structure data. It is not used to train the model, but is used to evaluate the generalization ability of the model. When the performance of the model on the verification data set (such as the average error between the predicted simulation credibility and the actual simulation credibility) begins to decline, it means that there are too many neurons, which may lead to overfitting. Select the number of neurons before the performance begins to decline as the appropriate number of neurons. For example, when the number of neurons increases to 50, the performance of the model on the verification data set begins to decline. Then, 30-40 neurons can be selected as the appropriate range of the number of neurons, and the specific value can be determined through further experiments. The ReLU function is selected as the activation function. The appropriate value of the learning rate can be determined through multiple experimental verifications. Start with a smaller learning rate, such as 0.001, and gradually increase the learning rate to observe the performance of the model on the training data set and the verification data set.

[0082] S206: Calculate the distance attenuation coefficient of each building structure position according to the initial fusion weight and the distance from the building structure position to the nearest preset target measurement point.

[0083] The initial fusion weight is the normalized value obtained in the previous step, which reflects the credibility of the simulation results. The building structure position refers to the specific spatial point in the 3D grid model. The preset target measurement point is the fixed position point where the radiation dose is actually measured. The distance refers to the spatial straight-line distance from the building structure position to the nearest measurement point. The distance attenuation coefficient is a coefficient that decreases with increasing distance and is used to adjust the fusion weight.

[0084] In this step, the device first calculates the spatial distance from each building structure position to the nearest preset target measurement point by calculating the Euclidean distance between the two points. Then, the distance decay function is set to the inverse function (1 / d), and the distance decay coefficient is calculated using the inverse function, where d is the distance from the building structure position to the nearest preset target measurement point, and the unit of distance d is meter. When d is 0, the distance decay coefficient is defined as 1.

[0085] S207: multiply the initial fusion weight by the distance attenuation coefficient to obtain the final fusion weight of each building structure position.

[0086] The final fusion weight is the weight value after comprehensively considering the simulation credibility and distance factors.

[0087] In this step, the device performs the following operations for each building structure position: first, the initial fusion weight and distance decay coefficient corresponding to the position are taken out. Then, these two values ​​are multiplied to obtain the final fusion weight of the position. This multiplication operation realizes the comprehensive consideration of two factors: the initial fusion weight reflects the credibility of the simulation result itself, while the distance decay coefficient reflects the impact of the spatial relationship between the position and the actual measurement point on the credibility. For example, if the initial fusion weight of a position is 0.8 and the distance decay coefficient is 0.6, the final fusion weight is 0.48. The result of this step is the final fusion weight of each building structure position.

[0088] S208. Perform curve fitting on the measured dose rate level to obtain a measured dose rate curve. Based on the final fusion weight, perform weighted averaging on the simulated dose rate level and the dose rate at the corresponding position obtained by interpolation according to the measured dose rate curve to obtain the actual dose rate level of each building structure part. The simulated dose rate level is simulated in a Monte Carlo program.

[0089] The measured dose rate curve is a function obtained after fitting that describes the spatial variation of dose rate, and the simulated dose rate level is the predicted dose rate value obtained by simulation and calculation using a Monte Carlo program.

[0090] In this step, the device first performs curve fitting on the acquired measured dose rate level data to obtain a continuous measured dose rate curve. This fitting can be done using methods such as polynomial fitting, exponential fitting or spline interpolation, and the specific choice depends on the characteristics of the data. Then, the device uses the final fusion weight calculated previously to weighted average the simulated dose rate level simulated by the Monte Carlo procedure and the dose rate at the corresponding position obtained by interpolation based on the measured dose rate curve. The interpolation process can use linear interpolation or higher-order interpolation methods to obtain estimated dose rate values ​​at locations outside the measurement point. The calculation formula for weighted average can be expressed as: actual dose rate = final fusion weight * simulated dose rate + (1-final fusion weight) * interpolated dose rate.

[0091] S209: Compare the three-dimensional grid model with the three-dimensional building model, identify a newly added structural part in the three-dimensional building model, and create a new data point in the newly added structural part.

[0092] The newly added structure refers to the building structure that is added or changed during the actual construction process relative to the original design. The newly added data points refer to the spatial sampling points created to describe the radiation dose distribution of the newly added structure.

[0093] In this step, the device first compares the 3D mesh model with the 3D building model. This comparison process can be achieved through a spatial registration algorithm, such as the iterative closest point (ICP) algorithm or the feature matching algorithm. The recognition process can be based on voxel comparison or grid difference analysis. After the newly added structural parts are identified, new data points will be created in these parts. The distribution of the new data points can be divided into uniform grids. For example, a data point can be created at a certain interval (such as every 10 cm) on the surface and inside of the newly added wall, or a denser sampling strategy can be used at the curved surface structure.

[0094] S210: assigning an initial dose value to the newly added data point based on the actual dose rate level.

[0095] Specifically, in this step, the device uses the previously obtained actual dose rate level data to assign initial dose values ​​to the newly created data points, and uses the Kriging interpolation method to estimate the initial dose values ​​for the newly added data points taking into account spatial correlation and anisotropy.

[0096] For example, suppose a 30-cm-thick concrete shield is added to one wall of a proton therapy room. The device first creates a series of data points in this new structure, such as setting a point every 5 cm in the thickness direction. Then, the device uses the kriging interpolation method to estimate the initial dose value for each new data point based on the known dose rate levels in the surrounding area. For the first data point near the inside of the treatment room, the device estimates a relatively high initial value based on the higher dose rate levels nearby, while for the last data point near the outside, it estimates a significantly lower initial value based on the attenuation characteristics of radiation in concrete. At the same time, the device adjusts the anisotropy of the dose distribution based on the relative position and angle of this wall to the proton beam source. For possible scattered radiation hotspots, multi-scale analysis is used to capture these local features and reflect them in the initial dose value. Finally, an uncertainty assessment is set to be attached to each initial dose value. For example, new data points close to known measurement points are assigned lower uncertainties, while data points farther away or in complex geometric structures have higher uncertainties.

[0097] S211. Acquire building material data of the newly added structural part in the three-dimensional building model, and calculate the attenuation coefficient corresponding to the initial dose value based on the building material data, wherein the building material data includes material parameters and geometric features.

[0098] Building material data is a collection of information that describes the physical properties of building materials, including material parameters (such as density, atomic number, electron density, etc.) and geometric characteristics (such as thickness, shape, size, etc.). The attenuation coefficient is a physical quantity that represents the degree to which the intensity of radiation is weakened when passing through a material, and is related to the composition and thickness of the material.

[0099] Specifically, first extract detailed information about the newly added structural parts from the three-dimensional building model, including their spatial position, shape, and size. Then, the device accesses the preset building material database and obtains the corresponding material parameters according to the type of the newly added structure (such as walls, shielding doors, etc.). For composite materials or special structures, the device may need to perform material composition analysis, such as using an X-ray fluorescence spectrometer to perform field measurements of the material. After obtaining the material data, the device calculates the attenuation coefficient using a radiation physics model. This process can use simplified analytical methods (such as exponential decay models) or more complex Monte Carlo simulations. For radiation with strong energy dependence (such as proton beams), the device will consider the attenuation characteristics of different energy ranges. The calculation of the attenuation coefficient will also calculate the geometric characteristics of the material. For example, for curved structures, the device will calculate the effective thickness through which the radiation passes.

[0100] S212: Multiply the attenuation coefficient by the initial dose value to obtain a simulated dose level corresponding to the newly added data point.

[0101] The attenuation coefficient is a physical quantity that represents the degree to which radiation intensity is reduced when passing through a material. The initial dose value is a preliminary radiation dose estimate assigned to the newly added data points. The newly added data points are spatial sampling points created in the newly added structure. The simulated dose level is the theoretical radiation dose rate at each spatial point obtained through calculation.

[0102] In this step, the device performs a dose attenuation calculation for each newly added data point. The device first reads the attenuation coefficient calculated in step S211 and the initial dose value assigned in step S210. The device then multiplies these two values ​​to obtain a simulated dose level that takes into account the material attenuation effect. This calculation process can be expressed as: simulated dose level = initial dose value × attenuation coefficient. For complex geometric structures or inhomogeneous materials, the device uses a ray tracing algorithm to simulate the transmission path of radiation in the material, or uses the Monte Carlo method for a more accurate dose deposition simulation. In addition, the device also considers the effects of scattered radiation and secondary particle generation. In particular, for high-energy proton beams, it may be necessary to simulate the contribution of secondary particles such as neutrons produced by nuclear reactions.

[0103] S213. Map the numerical value corresponding to the actual dose rate level to the three-dimensional building model, and map the numerical value corresponding to the simulated dose level to the newly added structural part to obtain a three-dimensional dose distribution map, which includes a dose isosurface, a dose value at each building structure position, and a dose distribution slice map of any plane.

[0104] First, a high-density dot matrix corresponding to the geometric structure of the building model is created in three-dimensional space. For the original structure, the actual dose rate level data obtained by fusion is assigned to the corresponding dot matrix position. For the newly added structure part, the simulated dose level data calculated in step S212 is assigned to the corresponding dot matrix position. During the data allocation process, the dose values ​​between adjacent points are linearly interpolated to ensure the continuity of the dose distribution.

[0105] The process of generating a three-dimensional dose distribution map is as follows: First, traverse all points in the three-dimensional space and identify point sets with equal dose values. By connecting these point sets, a dose isosurface is constructed. In order to improve efficiency, a step-by-step refinement method is adopted, first determining the general outline on a coarser grid, and then performing refinement in the high-dose gradient area. Then, the entire three-dimensional space is divided into multiple nested small cubes, each of which contains a certain number of dose data points. The maximum and minimum dose values ​​contained in each cube are recorded for each cube to form a hierarchical data structure.

[0106] Next, the function of generating a slice of dose distribution on any plane is realized. The specific process is: first determine the position and direction of the slice plane in three-dimensional space, and then calculate the intersection of the plane and the dose data point. For each pixel on the plane, trace a ray passing through the pixel, collect the information of all dose data points on the ray path, and calculate the dose value of the pixel by weighted average. Finally, convert the calculated dose value into color information to generate a two-dimensional dose distribution image.

[0107] In some embodiments, after step S206, the following steps may also be included: If the simulated dose rate level at a target building location exceeds a preset simulation threshold, a local correction is performed on the target building location, wherein the local correction includes increasing the wall thickness and the wall material density; Based on the partially corrected building material data, the dose rate level simulation is re-performed in the Monte Carlo program to obtain the corrected dose rate level; The local correction and the dose rate level simulation are repeated until the simulated dose rate level at the target building location does not exceed the preset simulation threshold.

[0108] Specifically, the preset simulation threshold is a pre-set acceptable maximum dose rate level used to determine whether a protection correction is needed. Local correction is a structural or material adjustment made to a specific building location to reduce the radiation dose rate. Increasing the wall thickness means increasing the thickness of the shielding material to improve the radiation attenuation effect. Increasing the density of the wall material means using a higher density material to enhance the radiation shielding capability.

[0109] First, check the simulated dose rate level of each target building location in the three-dimensional building model. When it is found that the simulated dose rate level of a certain location exceeds the preset simulation threshold, the target building location is locally corrected, and the thickness that needs to be increased is calculated to achieve sufficient radiation attenuation effect or a suitable alternative material is selected from the preset high-density material database. After that, the equipment inputs the corrected building material data into the Monte Carlo program and re-simulates the dose rate level. If the dose rate level still exceeds the threshold, the equipment repeats the process of local correction and dose rate level simulation. In each iteration, the equipment fine-tunes the correction plan based on the previous simulation results, further increasing the wall thickness or selecting a higher density material until the simulated dose rate levels of all target building locations do not exceed the preset simulation threshold.

[0110] In some embodiments, after step S206, the following steps may also be included: Detecting whether there is a building position in the three-dimensional dose distribution map that exceeds a preset dose rate level threshold; If it exists, a prompt message is sent to the target client, and the prompt message includes the location information and dose rate level data of the building location.

[0111] Specifically, the dose rate level of each point in the three-dimensional dose distribution map is compared with the preset dose rate level threshold. When the dose rate level exceeds the preset threshold, a prompt message is generated. First, the data of all points exceeding the threshold are sorted out, and the spatial coordinates are converted into a more understandable location description, such as "northwest corner of the first floor" or "door of the treatment room on the second floor". Then, the device generates a detailed prompt message for each point exceeding the threshold, including a location description and an accurate dose rate value, packages these prompt messages into a structured data packet, and sends the prompt information data packet to the target client.

[0112] The following describes the intelligent monitoring and evaluation device in the embodiment of the present invention from the perspective of hardware processing. Figure 3 , which is a schematic diagram of the structure of a physical device of the intelligent monitoring and evaluation equipment in the embodiment of the present application.

[0113] It should be noted that Figure 3 The structure of the intelligent monitoring and evaluation device shown is only an example and should not bring any limitation to the functions and scope of use of the embodiments of the present invention.

[0114] like Figure 3 As shown, the intelligent monitoring and evaluation device includes a central processing unit (CPU) 301, which can perform various appropriate actions and processes according to the program stored in the read-only memory (ROM) 302 or the program loaded from the storage part 308 to the random access memory (RAM) 303, such as executing the method described in the above embodiment. In RAM 303, various programs and data required for system operation are also stored. CPU 301, ROM 302 and RAM 303 are connected to each other through bus 304. Input / output (I / O) interface 305 is also connected to bus 304.

[0115] The following components are connected to the I / O interface 305: an input section 306 including an audio input device, a button switch, etc.; an output section 307 including a liquid crystal display (LCD) and an audio output device, an indicator light, etc.; a storage section 308 including a hard disk, etc.; and a communication section 309 including a network interface card such as a LAN (Local Area Network) card, a modem, etc. The communication section 309 performs communication processing via a network such as the Internet. A drive 310 is also connected to the I / O interface 305 as needed. A removable medium 311, such as a magnetic disk, an optical disk, a magneto-optical disk, a semiconductor memory, etc., is installed on the drive 310 as needed so that a computer program read therefrom is installed into the storage section 308 as needed.

[0116] In particular, according to an embodiment of the present invention, the process described above with reference to the flowchart can be implemented as a computer software program. For example, an embodiment of the present invention includes a computer program product, which includes a computer program carried on a computer-readable medium, and the computer program includes a computer program for executing the method shown in the flowchart. In such an embodiment, the computer program can be downloaded and installed from a network through the communication part 309, and / or installed from a removable medium 311. When the computer program is executed by the central processing unit (CPU) 301, various functions defined in the present invention are performed.

[0117] It should be noted that specific examples of computer-readable storage media may include, but are not limited to: an electrical connection with one or more wires, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM), a flash memory, an optical fiber, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination thereof. In the present invention, a computer-readable storage medium may be any tangible medium containing or storing a program that may be used by or in combination with an instruction execution system, apparatus, or device.

[0118] The flowcharts and block diagrams in the accompanying drawings illustrate the possible architecture, functions and operations of the systems, methods and computer program products according to various embodiments of the present invention. Each box in the flowchart or block diagram may represent a module, a program segment, or a part of a code, and the above-mentioned module, program segment, or a part of a code contains one or more executable instructions for implementing the specified logical functions. It should also be noted that in some alternative implementations, the functions marked in the box may also occur in an order different from that marked in the accompanying drawings.

[0119] Specifically, the intelligent monitoring and evaluation device of this embodiment includes a processor and a memory. The memory stores a computer program. When the computer program is executed by the processor, the intelligent monitoring and evaluation method for the radiation protection performance of the proton area of ​​the hospital provided in the above embodiment is implemented.

[0120] As another aspect, the present invention further provides a computer-readable storage medium, which may be included in the intelligent monitoring and evaluation device described in the above embodiment; or may exist independently without being assembled into the intelligent monitoring and evaluation device. The above storage medium carries one or more computer programs, and when the above one or more computer programs are executed by a processor of the intelligent monitoring and evaluation device, the intelligent monitoring and evaluation device implements the intelligent monitoring and evaluation method for the radiation protection performance of the proton area of ​​the hospital provided in the above embodiment.

[0121] As described above, the above embodiments are only used to illustrate the technical solutions of the present application, rather than to limit them. Although the present application has been described in detail with reference to the aforementioned embodiments, those skilled in the art should understand that they can still modify the technical solutions described in the aforementioned embodiments, or make equivalent replacements for some of the technical features therein. However, these modifications or replacements 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 application.

[0122] As used in the above embodiments, the term "when..." may be interpreted to mean "if..." or "after..." or "in response to determining..." or "in response to detecting...", depending on the context. Similarly, the phrases "upon determining..." or "if (the stated condition or event) is detected" may be interpreted to mean "if determining..." or "in response to determining..." or "upon detecting (the stated condition or event)" or "in response to detecting (the stated condition or event)", depending on the context.

[0123] Those skilled in the art can understand that to implement all or part of the processes in the above-mentioned embodiments, the processes can be completed by computer programs to instruct related hardware, and the programs can be stored in computer-readable storage media. When the programs are executed, they can include the processes of the above-mentioned method embodiments. The aforementioned storage media include: ROM or random access memory RAM, magnetic disk or optical disk and other media that can store program codes.

Claims

1. A method for intelligent monitoring and evaluation of radiation protection performance of proton areas in hospitals, characterized in that: Applied to intelligent monitoring and evaluation equipment, the method comprises: Acquire the actual building structure and actual equipment layout of the target proton therapy center, perform three-dimensional scanning on the actual building structure and the actual equipment layout to obtain three-dimensional scanning data, and modify the preset BIM model based on the three-dimensional scanning data to obtain a three-dimensional building model; After the detection device is turned on, the measured dose rate level of the target proton therapy center at the preset target measurement point is obtained; Performing curve fitting on the measured dose rate level to obtain a measured dose rate curve, fusing the simulated dose rate level and the measured dose rate curve to obtain the actual dose rate level at each building structure position, wherein the simulated dose rate level is obtained by simulation in a Monte Carlo program; The actual dose rate level is mapped to the three-dimensional building model to obtain a three-dimensional dose distribution map, which includes a dose isosurface, a dose value at each building structure position, and a dose distribution slice map of any plane.

2. The method according to claim 1, characterized in that Before the step of obtaining the actual building structure and actual equipment layout of the target proton therapy center and performing three-dimensional scanning on the actual building structure and the actual equipment layout to obtain three-dimensional scanning data, the method further includes: Modeling the target proton therapy center in a Monte Carlo program based on a preset building structure and a preset equipment layout to obtain a three-dimensional grid model of the target proton therapy center; In the Monte Carlo program, a dose rate level simulation is performed based on the building material data of each building structure part in the three-dimensional grid model and the treatment parameters of the proton therapy equipment in the target proton therapy center to obtain a simulated dose rate level at each building structure position in the building structure part, the building material data including density, element composition and mass content, and the treatment parameters including target material and beam intensity.

3. The method according to claim 2, characterized in that The step of fusing the simulated dose rate level with the measured dose rate curve to obtain the actual dose rate level at each building structure position specifically includes: Inputting each building structure position in the three-dimensional grid model into a preset credibility evaluation model to obtain simulation credibility corresponding to all building structure positions in the three-dimensional grid model, and normalizing the simulation credibility to obtain an initial fusion weight; Calculating a distance attenuation coefficient for each of the building structure positions according to the initial fusion weight and the distance from the building structure position to the nearest preset target measurement point; Multiplying the initial fusion weight by the distance attenuation coefficient to obtain the final fusion weight of each building structure position; Based on the final fusion weight, the simulated dose rate level and the dose rate at the corresponding position obtained by interpolation according to the measured dose rate curve are weighted averaged to obtain the actual dose rate level of each building structure part.

4. The method according to claim 2, characterized in that: The step of mapping the actual dose rate level to the three-dimensional building model to obtain a three-dimensional dose distribution map specifically includes: Comparing the three-dimensional grid model with the three-dimensional building model, identifying a newly added structural part in the three-dimensional building model, and creating a new data point in the newly added structural part; assigning an initial dose value to the newly added data point based on the actual dose rate level; Acquiring building material data of the newly added structural part in the three-dimensional building model, and calculating the attenuation coefficient corresponding to the initial dose value based on the building material data, wherein the building material data includes material parameters and geometric characteristics; Multiplying the attenuation coefficient by the initial dose value to obtain a simulated dose level corresponding to the newly added data point; The numerical value corresponding to the actual dose rate level is mapped to the three-dimensional building model, and the numerical value corresponding to the simulated dose level is mapped to the newly added structural part to obtain a three-dimensional dose distribution map.

5. The method according to claim 2, characterized in that: The step of simulating the dose rate level in the Monte Carlo program based on the building material data of each building structure part in the three-dimensional grid model and the treatment parameters of the proton therapy equipment in the target proton therapy center to obtain the simulated dose rate level of each building structure position in the building structure part specifically includes: Obtaining display accuracy requirements for each building structure part, and dividing the three-dimensional grid model into spatial units based on the display accuracy requirements to obtain grid units; Matching the simulation parameters of the corresponding Monte Carlo procedure to each of the grid cells, wherein the simulation parameters include spatial resolution, statistical error threshold and number of iterations; Inputting the building material data and the treatment parameters into the Monte Carlo program, performing a dose rate level simulation calculation on each of the grid cells, and obtaining a simulated dose rate level for each of the grid cells; The simulated dose rate level is mapped to the corresponding building structure position in the three-dimensional grid model to obtain the simulated dose rate level of each building structure position in the building structure part.

6. The method according to claim 2, characterized in that After the step of simulating the dose rate level based on the building material data of each building structure part in the three-dimensional grid model and the treatment parameters of the proton therapy equipment in the target proton therapy center in the Monte Carlo program to obtain the simulated dose rate level of each building structure position in the building structure part, the method further includes: If the simulated dose rate level at the target building location exceeds a preset simulation threshold, a local correction is performed on the target building location, wherein the local correction includes increasing the wall thickness and the wall material density; Based on the partially corrected building material data, re-simulating the dose rate level in the Monte Carlo program to obtain a corrected dose rate level; The local correction and the dose rate level simulation are repeated until the simulated dose rate level at the target building location does not exceed the preset simulation threshold.

7. The method according to claim 1, characterized in that After the step of mapping the actual dose rate level into the three-dimensional building model to obtain a three-dimensional dose distribution map, the method further comprises: Detecting whether there is a building location in the three-dimensional dose distribution map that exceeds a preset dose rate level threshold; If so, a prompt message is sent to the target client, wherein the prompt message includes the location information of the building location and the dose rate level data.

8. An intelligent monitoring and evaluation device, characterized in that: The intelligent monitoring and evaluation device includes: one or more processors and a memory; the memory is coupled to the one or more processors, the memory is used to store computer program code, the computer program code includes computer instructions, and the one or more processors call the computer instructions to enable the intelligent monitoring and evaluation device to execute the method described in any one of claims 1-7.

9. A computer-readable storage medium comprising instructions, characterized in that: When the instruction is executed on the intelligent monitoring and evaluation device, the intelligent monitoring and evaluation device executes the method as described in any one of claims 1-7.

10. A computer program product, characterized in that When the computer program product runs on an intelligent monitoring and evaluation device, the intelligent monitoring and evaluation device is enabled to perform the method according to any one of claims 1 to 7.

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