A proton radiotherapy environment multi-point radiation dose real-time monitoring system and method
By using multi-level radiation monitoring modules and dynamic modeling with three-dimensional spatial division, the problems of real-time radiation monitoring and insufficient spatial coverage in proton radiotherapy environments have been solved, enabling all-weather, blind-spot-free radiation monitoring and individual risk warning, thus improving the safety and monitoring accuracy of proton radiotherapy sites.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- 中南兰信(南京)辐射技术研究院有限公司
- Filing Date
- 2025-09-01
- Publication Date
- 2026-07-21
AI Technical Summary
Existing radiation dose monitoring in proton therapy environments suffers from poor real-time performance, incomplete spatial coverage, and a lack of individual risk warnings. In particular, real-time monitoring cannot be achieved in non-fixed areas and areas with high human activity, and there is a lack of comprehensive assessment of multiple types of radiation.
A multi-level collaborative monitoring system is adopted, consisting of fixed, patrol-type, and personal radiation dose monitoring modules. Combining three-dimensional spatial geometric division and dynamic expansion modeling, a three-dimensional radiation coefficient map of the control area is constructed to monitor and assess risk areas and safe areas in real time, and to provide real-time alerts through personal radiation dose monitoring modules.
It enables all-weather, all-around monitoring of radiation dose in proton radiotherapy sites, improving monitoring accuracy and reliability, possessing adaptive update capabilities, providing highly reliable safety assurance, and achieving multi-dimensional safety protection for personnel and the environment.
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Figure CN120871213B_ABST
Abstract
Description
Technical Field
[0001] This invention belongs to the field of radiation monitoring technology, specifically relating to a multi-point real-time radiation dose monitoring system and method for proton radiotherapy environments. Background Technology
[0002] With rapid economic development and continuous advancements in medical technology, proton therapy, as an advanced cancer treatment method, has gradually gained widespread application in major medical institutions due to its precise dose distribution and effective protection of surrounding healthy tissues.
[0003] Current technologies for monitoring radiation dose in proton therapy environments typically rely on fixed-point monitoring or periodic manual inspections, which suffer from limited monitoring range, insufficient real-time performance, incomplete spatial coverage, and coarse-grained risk assessment. Specifically, traditional methods often employ a small number of fixed detectors deployed at preset locations, making it difficult to comprehensively reflect the spatial distribution characteristics of the radiation field in complex treatment environments. In particular, radiation changes in non-fixed areas and areas with personnel activity cannot be captured in real time. At the same time, existing methods often rely on periodic manual inspections, resulting in significant data update delays and an inability to achieve continuous dynamic monitoring, leading to delayed risk warnings. Furthermore, existing systems typically lack comprehensive assessments of multiple types of radiation (such as neutrons and X-rays) and fail to perform three-dimensional fusion analysis of personnel location information and real-time radiation fields, thus failing to provide accurate risk warnings for individual personnel.
[0004] To address the aforementioned problems, this invention proposes a real-time multi-point radiation dose monitoring system and method for proton radiotherapy environments. Summary of the Invention
[0005] To address the shortcomings of existing technologies, this invention provides a multi-point real-time radiation dose monitoring system and method for proton radiotherapy environments, solving the problems of poor real-time radiation monitoring, incomplete spatial coverage, and lack of individual risk warnings in existing technologies.
[0006] The objective of this invention can be achieved through the following technical solutions: A method for real-time monitoring of multi-point radiation dose in a proton radiotherapy environment, the method comprising: Step 1: Use fixed radiation dose monitoring modules deployed at fixed points within the control area to collect the first neutron dose signal and the first X-ray dose signal of each fixed sub-region within the control area. The inspection personnel carry the inspection-type radiation dose monitoring module to collect the second neutron dose signal and the second X-γ ray dose signal in the non-covered area within the control zone at predefined inspection cycles. The third neutron dose signal and the third X-γ ray dose signal at the control area where the staff are located are collected using personal radiation dose monitoring modules worn by the staff. Step 2: Calculate the radiation coefficient of the corresponding fixed sub-region based on the first neutron dose signal and the first X-γ ray dose signal collected by the fixed radiation dose monitoring module associated with each fixed sub-region within the control area. Map the radiation coefficients of all fixed sub-regions associated with the control area to the three-dimensional control area map associated with the control area to construct the three-dimensional control area radiation coefficient map; Step 3: Based on the determined three-dimensional control area radiation coefficient map, as well as the second neutron dose signal and the second X-γ ray dose signal of the non-covered area within the control area, calculate the radiation coefficient of the non-covered area associated with the non-covered area within the control area, and map it to the three-dimensional control area radiation coefficient map associated with the control area to improve the three-dimensional control area radiation coefficient map. Based on the three-dimensional radiation coefficient map of the control area, the risk areas and safe areas within the control area are comprehensively assessed and marked. Step 4: Obtain the personal radiation dose monitoring module worn by any staff member, locate the staff member in real time, and determine the first and second danger signals associated with the staff member in real time by combining the determined three-dimensional control area radiation coefficient map, and give the staff member a real-time reminder.
[0007] As a further embodiment of the present invention, in step one, the fixed radiation dose monitoring module includes a fixed neutron dosimeter, a fixed X-γ dosimeter, and a radiation management system, wherein the radiation management system is pre-constructed by the operator and the radiation management system is determined and unique. The inspection-type radiation dose monitoring module includes one inspection-type neutron dosimeter, one inspection-type X-γ dosimeter, and a communication device. The personal radiation dose monitoring module includes a personal dose alarm, a communication device, a display device, and a positioning device. The personal radiation dose monitoring module is worn by the staff.
[0008] As a further aspect of the present invention, in step one, the method for determining each fixed point within the control area is as follows: Obtain all floors in the proton radiotherapy facility, and denote any one of these floors as a control zone, denoted as CZ; The control area CZ is mapped using a 3D mapping tool to obtain the 3D control area map CZM associated with the control area CZ; Obtain plane M1 corresponding to the ground plane of control area CZ in the 3D control area map CZM; Determine the point corresponding to the main entrance of the control area CZ in plane M1, and denote it as point D1; Find the far corner vertex in plane M1 that is opposite to point D1, and denote it as point D2; Connect points D1 and D2, construct the perpendicular bisector of the line connecting the two points, and determine the two intersection points of this perpendicular bisector with the boundary of plane M1, denoted as points D3 and D4 respectively. Connect the four points clockwise to obtain a unique and closed quadrilateral CQ; Simultaneously translate the four sides of quadrilateral CQ inwards, with the translation distance successively taken as 1 / X, 2 / X, and 3 / X of the longest diagonal length in plane M1, to obtain three inwardly shrunk quadrilaterals, denoted as quadrilateral CQ1, quadrilateral CQ2, and quadrilateral CQ3, respectively. The value of X is determined by the operator. Quadrilaterals CQ1, CQ2, and CQ3 are all located in plane M1. At the midpoint of each side of quadrilaterals CQ, CQ1, CQ2, and CQ3, draw a perpendicular line that is perpendicular to the side and points into the quadrilateral. The length of the perpendicular line is equal to the corresponding translation distance. Mark the end point of each perpendicular line as a fixed point, resulting in 12 fixed points. Twelve fixed points were mapped to the control area CZ, and a fixed radiation dose monitoring module was installed at each fixed point at a height h preset by the operator.
[0009] As a further aspect of the present invention, in step one, the method for determining the fixed sub-region within the control area is as follows: S41. Take the 12 fixed points located at height h within the control area CZ as the center; S42. Simultaneously expand the 12 centers along the six orthogonal directions in three-dimensional space to form six expansion surfaces. The initial value of the expansion step size is 1 / 2Y of the length of the longest diagonal of plane M1, and the expansion step size gradually increases. Y is a value preset by the operator and Y is not less than X. S43. If any two centers are connected by their associated expansion surfaces, stop increasing the expansion step size. Record the closed hexahedron formed by the six expansion surfaces associated with each of the 12 centers as the fixed sub-regions associated with the corresponding centers, and label the 12 fixed sub-regions in the three-dimensional control area map CZM. S44. The first neutron dose signal and the first X-γ ray dose signal of all spatial points within the fixed sub-region are uniformly characterized by the fixed radiation dose monitoring module installed at the center of the fixed sub-region. S45. If the control area CZ undergoes physical changes, repeat steps S41 to S44 to refresh the geometric boundaries of all fixed sub-areas.
[0010] As a further aspect of the present invention, the specific method for acquiring the second neutron dose signal and the second X-ray dose signal in the non-covered area within the control zone in step one is as follows: Obtain the predefined inspection cycle T and time window ΔT by the operator; Obtain the 12 fixed sub-regions in the 3D control area map (CZM); The complete three-dimensional space volume of the three-dimensional control zone map CZM is denoted as V_total; Perform a Boolean union operation on the three-dimensional spatial volumes associated with the 12 fixed sub-regions to obtain the covered spatial volume V_cov; Perform a Boolean difference operation between the complete 3D space volume V_total and the covered space volume V_cov to obtain the remaining space volume; The remaining space volume is the non-covered area within the control area CZ, denoted as V_rem; Based on the inspection cycle T, the non-covered area V_rem within the control zone CZ is detected within a time window ΔT, and the detected second neutron dose signal and second X-γ ray dose signal are recorded.
[0011] As a further aspect of the present invention, the specific method for calculating the radiation coefficient of the fixed sub-region associated with the corresponding fixed sub-region in step two is as follows: S61. Obtain any fixed sub-region, and collect the first neutron dose signal A1 and the first X-γ ray dose signal B1 associated with this fixed sub-region. The collection frequency F and the time window Δt are determined by the operator. S62. Take the average value of the first neutron dose signal A1 and the first X-γ ray dose signal B1 within any time window Δt to obtain the average value signal of the first neutron dose A1_avg and the average value signal of the first X-γ ray dose B1_avg. S63. Extract the equivalent doses A1_avg` and B1_avg` associated with the first neutron dose mean signal A1_avg and the first X-ray gamma ray dose mean signal B1_avg, respectively. The weighted summation of the equivalent doses A1_avg` and B1_avg` yields the comprehensive dose value CDV. Among them, the weighting factor of the equivalent dose A1_avg` is α, and the weighting factor of the equivalent dose B1_avg` is β. Both α and β are predefined by the operator. Both α and β are greater than 0, and α+β=1. S64. Divide the calculated comprehensive dose value CDV by the volume of this fixed sub-region to obtain the radiation dose density ρ; S65. Compare the radiation dose density ρ with the reference dose density ρ0 preset by the operator to obtain the radiation coefficient R of the fixed sub-area: R = ρ / ρ0. S66. Repeat steps S61 to S65 to determine the radiation coefficient of each of the 12 fixed sub-regions associated with the three-dimensional control area map CZM. S67. Write the radiation coefficients of the fixed sub-regions associated with each of the 12 fixed sub-regions into the three-dimensional control area map CZM in real time to obtain the three-dimensional control area radiation coefficient map RDA.
[0012] As a further aspect of the present invention, the specific method for improving the three-dimensional control area radiation coefficient map in step three is as follows: Obtain the three-dimensional control area radiation coefficient map RDA; The second neutron dose signal and the second X-γ ray dose signal associated with the uncovered region V_rem are obtained and denoted as A2 and B2, respectively. Based on the content described in S62 to S65, determine the non-covered area radiation coefficient L associated with the non-covered area V_rem; Based on the content described in S66 to S67, the non-covered area radiation coefficient L associated with the non-covered area V_rem is written into the three-dimensional control area radiation coefficient map RDA.
[0013] As a further aspect of the present invention, the specific method for comprehensively evaluating the risk areas and safe areas within the control area in step three is as follows: Obtain the three-dimensional control area radiation coefficient map RDA; Determine the uncovered area V_rem and 12 fixed sub-regions in the three-dimensional control area radiation coefficient map RDA; If the radiation coefficient associated with any zone is greater than or equal to 1, it is marked as a risk zone; otherwise, it is marked as a safe zone. The risk areas are marked in red, and the safe areas are marked in green.
[0014] As a further aspect of the present invention, in step four, the specific method for determining the first danger signal and the second danger signal associated with the worker in real time and providing the worker with a real-time reminder is as follows: Based on the personal radiation dose monitoring module worn by the staff, the staff's location P and the third neutron dose signal and third X-γ ray dose signal at the staff's location P are acquired in real time and are denoted as A3 and B3, respectively. Based on the contents described in S62 to S65, determine the personal radiation coefficient U associated with the third neutron dose signal A3 and the third X-ray gamma-ray dose signal B3; If an individual's radiation coefficient U is greater than or equal to 1, the first danger signal is issued to the staff. If the individual radiation coefficient U is less than 1, the worker's location P is mapped to the three-dimensional control area radiation coefficient map RDA; Calculate the straight-line distance JL between the worker's location P and the nearest risk area in the three-dimensional control zone radiation coefficient map RDA. If JL is lower than a preset threshold, issue a second danger signal. Conversely, continuous monitoring is required.
[0015] A multi-point real-time radiation dose monitoring system for proton radiotherapy environments, the system comprising: The global sensing and acquisition terminal uses fixed radiation dose monitoring modules deployed at fixed points within the control area to collect the first neutron dose signal and the first X-γ ray dose signal of each fixed sub-region within the control area. The inspection personnel carry the inspection-type radiation dose monitoring module to collect the second neutron dose signal and the second X-γ ray dose signal in the non-covered area within the control zone at predefined inspection cycles. The third neutron dose signal and the third X-γ ray dose signal at the control area where the staff are located are collected using personal radiation dose monitoring modules worn by the staff. The dynamic radiation modeling end calculates the radiation coefficient of the corresponding fixed sub-region based on the first neutron dose signal and the first X-γ ray dose signal collected by the fixed radiation dose monitoring module associated with each fixed sub-region in the control area. Map the radiation coefficients of all fixed sub-regions associated with the control area to the three-dimensional control area map associated with the control area to construct the three-dimensional control area radiation coefficient map; At the regional collaborative optimization end, based on the determined three-dimensional control area radiation coefficient map, as well as the second neutron dose signal and the second X-γ ray dose signal of the non-covered area within the control area, the radiation coefficient of the non-covered area associated with the control area is calculated and mapped to the three-dimensional control area map associated with the control area to improve the three-dimensional control area radiation coefficient map. Based on the three-dimensional radiation coefficient map of the control area, the risk areas and safe areas within the control area are comprehensively assessed and marked. The intelligent radiation and personnel monitoring terminal acquires the personal radiation dose monitoring module worn by any worker, locates the worker in real time, and determines the first and second danger signals associated with the worker in real time by combining the determined three-dimensional control area radiation coefficient map, and provides real-time reminders to the worker.
[0016] The beneficial effects of this invention are: This invention constructs a multi-level collaborative monitoring system comprising fixed, patrol-type, and personal radiation dose monitoring modules. Combined with an automatic fixed-point sub-area generation algorithm based on three-dimensional spatial geometric division and a dynamic patrol mechanism for non-covered areas, it achieves all-weather, blind-spot-free coverage monitoring of radiation dose in proton therapy sites. Secondly, through intelligent spatial zoning and dynamic expansion modeling, it significantly improves monitoring accuracy and reliability, effectively avoiding blind spots that may exist in traditional deployment methods. Furthermore, this invention possesses adaptive update capabilities, allowing for rapid reconstruction of the monitoring network after environmental changes, enhancing the real-time nature and comprehensiveness of radiation protection, and providing staff with multi-dimensional, highly reliable safety assurance. This invention constructs and updates a three-dimensional control zone radiation coefficient map in real time, integrating and visualizing the radiation coefficients of fixed sub-areas and non-covered areas, thus achieving a precise digital mapping of radiation levels in proton radiotherapy sites. Its core advantage lies in its ability to automatically and intelligently distinguish and color-render risk and safety areas based on radiation coefficient thresholds, improving the intuitiveness of risk identification and decision-making efficiency. Furthermore, it can simultaneously integrate fixed-point and inspection data to ensure the comprehensiveness and timeliness of assessment results, ultimately forming a high-precision, visualized, and adaptive radiation safety situational awareness system, significantly enhancing the safety assurance capabilities for personnel and the environment. This invention establishes a dynamic and precise personal risk early warning mechanism by integrating real-time personal dose monitoring with a global radiation coefficient map. First, it directly triggers a level-one alarm based on the measured radiation coefficient at the individual's location, ensuring immediate response to danger. Second, by comparing the individual's location with a global risk map in real time, it triggers a level-two early warning based on a preset distance threshold, achieving a forward-looking extension from "current risk" to "potential risk." This effectively fills the blind spots between fixed-point monitoring and personnel movement paths, deeply integrating static environmental assessment with dynamic personnel exposure risk, and enhancing the initiative of personnel protection. Attached Figure Description
[0017] The invention will now be further described with reference to the accompanying drawings.
[0018] Figure 1 This is a schematic diagram of the system described in this invention; Figure 2 This is a flowchart illustrating the method described in Embodiment 2 of the present invention; Figure 3 This is a flowchart illustrating the method described in Embodiment 3 of the present invention. Detailed Implementation
[0019] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.
[0020] Example 1 A multi-point real-time radiation dose monitoring system for proton radiotherapy environments, such as Figure 1 As shown, this system includes the following: This system mainly includes a global sensing and acquisition terminal, a dynamic radiation modeling terminal, a regional collaborative optimization terminal, and an intelligent radiation and personnel monitoring terminal. The global sensing and acquisition terminal is primarily used to acquire neutron dose signals and X-ray / gamma-ray dose signals. Specifically: First, this module mainly monitors neutron dose signals and X-ray dose signals through three modules, including a fixed radiation dose monitoring module, a patrol-type radiation dose monitoring module, and a personal radiation dose monitoring module.
[0021] The fixed radiation dose monitoring modules are deployed in predefined fixed sub-areas within the control area. Each fixed sub-area corresponds to one fixed radiation dose monitoring module. Each fixed radiation dose monitoring module includes one fixed neutron dosimeter, one fixed X-γ dosimeter, and an associated radiation management system. The radiation management system is pre-built by the operator and is determined and unique. That is to say, each fixed radiation dose monitoring module in the fixed sub-area is connected to this determined and unique radiation management system.
[0022] The fixed radiation dose monitoring module monitors the fixed sub-region and determines the first neutron dose signal and the first X-ray dose signal associated with the fixed sub-region in real time.
[0023] The inspection-type radiation dose monitoring module is used to collect the second neutron dose signal and the second X-γ ray dose signal in the non-covered area within the control area. The non-covered area refers to the area within the control area that has not been included in the fixed sub-area.
[0024] The inspection-type radiation dose monitoring module includes one inspection-type neutron dosimeter, one inspection-type X-γ dosimeter, and a communication device. The inspection-type radiation dose monitoring module transmits the monitored second neutron dose signal and second X-γ ray dose signal to a specific and unique radiation management system through its equipped communication device.
[0025] The personal radiation dose monitoring module is mainly used to monitor the radiation dose of the staff at the current location in real time and generate a third neutron dose signal and a third X-ray gamma ray dose signal.
[0026] The personal radiation dose monitoring module includes a personal dose alarm, a communication device, a display device, and a positioning device. The display device includes a monitor and a speaker to issue audible and visual alarms to staff. The positioning device is used to determine the location of staff in real time. The positioning device also integrates an altitude measurement function, which can determine the altitude of the staff's current location and further determine the floor of the control area where the staff is currently located.
[0027] The dynamic radiation modeling terminal mainly includes the following parts: First, based on the fixed radiation dose monitoring module associated with each fixed sub-region in the control area, the first neutron dose signal and the first X-γ ray dose signal associated with the corresponding fixed sub-region are obtained; and the radiation coefficient of the fixed sub-region associated with the corresponding fixed sub-region is calculated through the determined first neutron dose signal and the first X-γ ray dose signal.
[0028] Next, the radiation coefficients of each fixed sub-region associated with the control area are mapped to the three-dimensional control area map associated with the control area (the three-dimensional control area map is constructed using three-dimensional mapping technology, which is part of the existing technology), and a three-dimensional control area radiation coefficient map is constructed (the radiation coefficients of the fixed sub-regions are combined with the three-dimensional control area map by the Information Bureau).
[0029] The regional collaborative optimization module is primarily used to refine the constructed 3D control area radiation coefficient map and simultaneously assess and label the risk and safety areas within the control area associated with the 3D control area radiation coefficient map. Specifically: First, obtain the three-dimensional control area radiation coefficient map (which integrates the radiation coefficient of the fixed sub-region) as determined above. Then, extract the second neutron dose signal and the second X-γ ray dose signal of the uncovered area within the control area to calculate the radiation coefficient of the uncovered area associated with the uncovered area within the control area; The calculated radiation coefficients of the uncovered areas are mapped to the three-dimensional radiation coefficient map of the control areas using the method described above, thereby improving the three-dimensional radiation coefficient map of the control areas.
[0030] At this point, the radiation coefficients associated with all fixed sub-regions and uncovered regions within the three-dimensional control area radiation coefficient map have been determined. Based on the determined radiation coefficients, all fixed sub-regions and uncovered regions are comprehensively evaluated to identify risk areas with excessive radiation doses and safe areas with normal radiation doses. These are then rendered and marked for operators to view in real time.
[0031] The intelligent radiation and personnel monitoring terminal is primarily designed for staff members. It processes the current location of staff members, including acquiring the personal radiation dose monitoring module worn by any staff member. The positioning device equipped with this personal radiation dose monitoring module determines the staff member's location in real time. Combined with the altitude measurement function in the positioning device, the altitude of the staff member's location is determined. The floor of the staff member's current location is derived from the location. Combined with the determined three-dimensional control zone radiation coefficient map, the first danger signal and the second danger signal of the staff member's current floor location are further determined, and timely reminders are given to the staff member.
[0032] This system aims to comprehensively monitor neutron and X-ray dose signals in the control area in real time. Through the collaborative operation of the global sensing acquisition terminal, dynamic radiation modeling terminal, regional collaborative optimization terminal, and intelligent radiation and personnel monitoring terminal, it can realize the acquisition and processing of radiation data in fixed sub-areas and non-covered areas, construct and improve the three-dimensional radiation coefficient map of the control area, accurately mark risk and safety areas, and provide real-time warnings of danger signals in combination with the location information of personnel, so as to achieve comprehensive, accurate and real-time radiation monitoring and personnel safety protection.
[0033] Example 2 This embodiment, based on Embodiment 1, discloses a method for determining the radiation dose signals associated with fixed sub-regions and non-covered regions within a controlled area, such as... Figure 2 As shown, it specifically includes the following: As can be seen from the content described in Example 1, this method is mainly aimed at proton radiotherapy sites. Proton radiotherapy sites are generally single-story buildings, but there are also multi-story buildings. Therefore, this method needs to satisfy both conditions at the same time.
[0034] First, it is necessary to identify the proton therapy site that the operators need to monitor, and further determine all the floors in this proton therapy site. Take any one of these floors as a control zone, denoted as CZ, and process this control zone. It should be noted that the subsequent processing steps are all processing steps for the control zone CZ. If there are other floors in the proton therapy site, the same processing method is used to process the control zone CZ.
[0035] Next, the control area CZ is mapped using a 3D mapping tool to obtain a 3D control area map associated with this control area CZ, which is denoted as CZM. Based on the determined three-dimensional control zone map CZM, the plane of the ground plane associated with this control zone CZ in the three-dimensional control zone map CZM is determined and denoted as M1. Next, determine the point corresponding to the main entrance of this control area CZ in plane M1, and denote this point as point D1; Then, determine the far corner vertex opposite point D1 from plane M1, and denote this point as D2; Connect points D1 and D2 with a line segment to obtain a line with endpoints D1 and D2. Construct the perpendicular bisector of this line in plane M1. The perpendicular bisector will intersect the boundary of plane M1 at two points, which are denoted as points D3 and D4 respectively.
[0036] At this point, four points have been identified: D1, D2, D3, and D4. Connect the four points in a clockwise order (the lines should not intersect). For example, start with point D1, connect point D3, then connect point D2, and finally connect point D4.
[0037] After the connection operation is completed, a unique and closed quadrilateral consisting of points D1, D2, D3 and D4 will be obtained, and this quadrilateral will be denoted as CQ.
[0038] Determine the four sides of quadrilateral CQ, and simultaneously translate these four sides into the interior of the quadrilateral (during the translation, shorten the four sides to ensure that it is a closed quadrilateral).
[0039] The translation distances of the four sides simultaneously translating into the interior of the quadrilateral are successively taken as 1 / X, 2 / X, and 3 / X of the longest diagonal length in plane M1. After three translations, three inward-shrinking quadrilaterals are obtained, which are denoted as quadrilateral CQ1, quadrilateral CQ2, and quadrilateral CQ3, respectively. The value of X is determined by the operator based on the actual situation, and quadrilaterals CQ1, CQ2, and CQ3 are all located in plane M1.
[0040] Next, obtain quadrilaterals CQ, CQ1, CQ2, and CQ3. Construct a perpendicular line through the midpoint of each side of these four quadrilaterals, perpendicular to the corresponding side and pointing into the quadrilateral. Each quadrilateral has four perpendicular lines, and the length of the perpendicular line is equal to the translation distance of the corresponding quadrilateral. Mark the end point of each perpendicular line as a fixed point, and finally obtain 12 fixed points. It needs to be explained that there are 4 perpendicular lines between quadrilateral CQ and quadrilateral CQ1, 4 perpendicular lines between quadrilateral CQ1 and quadrilateral CQ2, and 4 perpendicular lines between quadrilateral CQ2 and quadrilateral CQ3, for a total of 12 perpendicular lines, which means 12 fixed points.
[0041] The 12 fixed points determined in plane M1 are mapped to the control area CZ. At this time, the 12 fixed points are located on the plane where the ground of the control area CZ is located. The operator's preset height h is obtained, and fixed radiation dose monitoring modules are installed at the 12 fixed points at the preset height h. After installing the fixed radiation dose monitoring module, 12 centers are obtained by taking 12 fixed points located at height h within the control area CZ as centers.
[0042] Next, the 12 centers are simultaneously expanded outward along the six expansion surfaces formed by the six orthogonal directions in three-dimensional space; The six orthogonal directions in the three-dimensional space correspond to the positive and negative directions of the horizontal axis, the vertical axis, and the Z-axis in the three-dimensional space, respectively. The six outward-expanding surfaces form a closed hexahedron (refer to a cube) with each face being a quadrilateral. The initial value of the expansion step size for the expansion operation of the outer surface is 1 / 2Y of the longest diagonal length of plane M1, and the expansion step size gradually increases, where Y is a value preset by the operator and Y is not less than X; If, during the expansion operation, any two expansion surfaces associated with the centers come into contact, the expansion step size is stopped, and the closed hexahedrons formed by the six expansion surfaces associated with each of the 12 centers within the three-dimensional control area map CZM are recorded as the fixed sub-regions associated with the corresponding centers. Only the closed hexahedrons within the three-dimensional control area map CZM are preserved.
[0043] At this point, 12 fixed sub-regions were identified, and these 12 fixed sub-regions were sequentially labeled in the 3D control area map CZM. The first neutron dose signal and the first X-ray dose signal of all spatial points within the fixed sub-region are uniformly characterized by the fixed radiation dose monitoring module installed at the center of the corresponding fixed sub-region. If the control area CZ undergoes physical changes, the fixed sub-regions need to be redefined in the same way as the steps described above. After the redefined sub-regions are defined, the geometric boundaries of all fixed sub-regions in the three-dimensional control area map CZM are updated.
[0044] Based on the above, all the fixed sub-regions in the three-dimensional control zone map (CZM) have been determined. Next, it is necessary to determine all the uncovered regions in the three-dimensional control zone map (CZM) and the second neutron dose signal and the second X-ray dose signal associated with the uncovered regions. First, it is necessary to clarify the inspection cycle T and time window ΔT preset by the operators. This is because when the staff uses the inspection-type radiation dose monitoring module to inspect the control area CZ, they need to perform periodic operations, and each periodic operation needs to maintain a certain time window to ensure the stability of the detection data.
[0045] Then, based on the above, the 12 fixed sub-regions within the three-dimensional control area map CZM are determined, and the complete three-dimensional space volume of the three-dimensional control area map CZM is denoted as V_total.
[0046] Perform a Boolean union operation on the three-dimensional spatial volumes corresponding to the 12 fixed sub-regions within the three-dimensional control area map CZM to obtain the covered spatial volume that is associated with the 12 fixed sub-regions, and denote it as V_cov.
[0047] Next, a Boolean difference operation is performed between the complete three-dimensional space volume V_total and the covered space volume V_cov. After the Boolean difference operation, the remaining space volume is obtained. The remaining space volume is the non-covered area within the control region CZ, and the non-covered area is denoted as V_rem.
[0048] Thus, the uncovered area V_rem within the control zone CZ was determined. Based on the operator's preset inspection cycle T and time window ΔT, the uncovered area V_rem was inspected, and the radiation dose information associated with the uncovered area V_rem obtained from each inspection was collected, namely the second neutron dose signal and the second X-γ ray dose signal.
[0049] This embodiment describes a method for dividing fixed sub-areas and non-covered areas in proton radiotherapy sites. Its core purpose is to provide a scientific and reasonable layout plan for radiation monitoring through precise geometric modeling and spatial analysis. Specifically, a three-dimensional model of the control area is first obtained using a three-dimensional mapping tool. Multiple fixed points and fixed sub-areas are generated through perpendicular bisector division, translation operations, and outward expansion to provide reference positions for subsequent radiation monitoring. At the same time, non-covered areas are identified through Boolean operations. Combined with the setting of inspection cycles and time windows, the stability and comprehensiveness of monitoring data are ensured. This method not only improves monitoring efficiency but also adapts to proton radiotherapy sites in single-story or multi-story buildings, providing a flexible and accurate spatial layout scheme for radiation monitoring.
[0050] Example 3 This embodiment, based on Embodiment 2, discloses a method for assessing risk areas and safe areas within a controlled area, such as... Figure 3 As shown, it specifically includes the following: Based on the content described in Example 2, the final three-dimensional control area diagram CZM integrating the fixed sub-region and the non-covered region can be obtained; First, a fixed sub-region in any three-dimensional control zone map (CZM) is obtained. Based on this fixed sub-region, the fixed radiation dose monitoring module continuously collects the first neutron dose signal A1 and the first X-ray gamma-ray dose signal B1 associated with this fixed sub-region. It should be noted that the fixed radiation dose monitoring module continuously collects radiation doses in the fixed sub-region based on the sampling frequency F and time window Δt preset by the operator according to the actual situation.
[0051] The average values of the first neutron dose signal A1 and the first X-ray dose signal B1 obtained in any time window Δt for this fixed sub-region are calculated to obtain the average first neutron dose signal and the average first X-ray dose signal, which are denoted as A1_avg and B1_avg, respectively.
[0052] Based on the determined first neutron dose mean signal A1_avg and first X-ray dose mean signal B1_avg, extract the equivalent dose A1_avg` associated with the first neutron dose mean signal A1_avg and the equivalent dose B1_avg` associated with the first X-ray dose mean signal B1_avg (this step can be directly extracted using the algorithm module built into the professional radiation monitoring equipment).
[0053] After determining the equivalent doses A1_avg` and B1_avg` associated with the first neutron dose mean signal A1_avg and the first X-γ ray dose mean signal B1_avg, a weighted summation of the equivalent doses A1_avg` and B1_avg` is performed, and the final result is recorded as the comprehensive dose value CDV. The weighted summation calculation also involves weighting factors. The weighting factor associated with the equivalent dose A1_avg` is α; the weighting factor associated with the equivalent dose B1_avg` is β. Both weighting factors α and β are predefined values by the operator, and both weighting factors α and β need to be greater than 0, and α+β=1.
[0054] Next, the calculated comprehensive dose value CDV is divided by the volume of this fixed sub-region (the volume of each fixed sub-region is considered a known value and determined according to the above steps for the closed hexahedron) to finally obtain the radiation dose density ρ associated with this fixed sub-region.
[0055] Then, the reference dose density ρ0 preset by the operator based on the actual situation is obtained, and the radiation dose density ρ associated with this fixed sub-region is compared with the reference dose density ρ0. Thus: R=ρ / ρ0, and the radiation coefficient R of the fixed sub-region associated with this fixed sub-region is obtained.
[0056] By repeating the above steps, the radiation coefficients of each of the 12 fixed sub-regions in the three-dimensional control zone map (CZM) can be determined. The radiation coefficients of each of the 12 fixed sub-regions are written into the corresponding fixed sub-regions in the three-dimensional control zone map (CZM) to obtain the three-dimensional control zone radiation coefficient map, which is denoted as RDA.
[0057] At this point, the 3D control area radiation coefficient map RDA integrates the radiation coefficients associated with the fixed sub-regions, and also needs to integrate the radiation coefficients associated with the non-covered areas.
[0058] The second neutron dose signal and the second X-ray dose signal associated with the non-covered region V_rem are obtained and denoted as A2 and B2, respectively.
[0059] The second neutron dose signal A2 and the second X-ray dose signal B2 associated with the uncovered region V_rem are processed according to the method described above for determining the radiation coefficient of the fixed sub-region associated with the fixed sub-region, to obtain the radiation coefficient of the uncovered region associated with the uncovered region V_rem, denoted as L.
[0060] Next, the non-covered area radiation coefficient L associated with the non-covered area V_rem is written into the corresponding non-covered area V_rem position in the three-dimensional control area radiation coefficient map RDA, thus obtaining the improved three-dimensional control area radiation coefficient map RDA.
[0061] Thus, the three-dimensional control area radiation coefficient map RDA integrates both the radiation coefficient of the fixed sub-area and the radiation coefficient of the non-covered area V_rem. If the radiation coefficient of any area is greater than or equal to 1, it means that the radiation coefficient of the area has reached or exceeded the predefined benchmark value, and the area is marked as a risk area. Conversely, if the radiation coefficient of any zone is less than 1, it means that the radiation coefficient of that zone is within the normal range, and that zone is marked as a safe zone.
[0062] The risk areas are marked in red to indicate that there is a risk in the area; the safe areas are marked in green to indicate that the area is safe.
[0063] This embodiment integrates radiation data from fixed sub-regions and non-covered areas in a three-dimensional control zone map. It calculates the radiation coefficient of each region by combining a weighted calculation of neutron dose and X-ray dose with density standardization, and marks the regions as risk and safe areas based on preset benchmark values. The aim is to achieve comprehensive radiation monitoring of proton radiotherapy sites and to visually present risk and safe areas to improve radiation management efficiency and ensure site safety.
[0064] Example 4 This embodiment, based on embodiment 3, further discloses a method for providing real-time reminders to staff within a controlled area, specifically including the following: As can be seen from the description in Example 1, the personal radiation dose monitoring module integrates a positioning device, a display device, and a communication device. The location of the worker, P, can be obtained in real time through the positioning device. Combined with the personal radiation dose monitoring module, the third neutron dose signal and the third X-ray dose signal associated with the worker's location P can be further determined and denoted as A3 and B3, respectively.
[0065] Next, based on the content described in Example 3, and in conjunction with the third neutron dose signal A3 and the third X-γ ray dose signal B3, the radiation coefficient at the worker's position P is determined and denoted as the personal radiation coefficient U. Next, the individual radiation coefficient U is determined. If the individual radiation coefficient U is greater than or equal to 1, the first danger signal is issued to the staff (through an audible and visual alarm) to remind the staff to stay away from the current area. If the individual radiation coefficient U is less than 1, the staff location P is mapped to the three-dimensional control area radiation coefficient map RDA, and the straight-line distance JL between the risk area closest to the staff location P and the staff location P is determined in real time in the three-dimensional control area radiation coefficient map RDA. The system determines the straight-line distance JL. If the straight-line distance JL is lower than the operator's preset straight-line distance threshold, a second danger signal (via audible and visual alarm) is issued to the operator to remind them that they are about to approach a risk area.
[0066] All data in the formulas described above are numerical calculations performed with dimensions removed. Furthermore, any content not described in detail in this specification is existing technology known to those skilled in the art.
[0067] The above description is merely an example and illustration of the present invention. Those skilled in the art can make various modifications or additions to the specific embodiments described, or use similar methods to replace them, as long as they do not deviate from the invention or exceed the scope defined in the claims, all of which should fall within the protection scope of the present invention.
[0068] It should be stated that all user data collected in this application was collected with the user's consent and authorization. Furthermore, the uses of user data are legal and compliant, and the use and processing of user data comply with the relevant laws, regulations, and standards of the relevant regions.
Claims
1. A method for real-time monitoring of multi-point radiation dose in a proton radiotherapy environment, characterized in that, The method includes: Step 1: Use fixed radiation dose monitoring modules deployed at fixed points within the control area to collect the first neutron dose signal and the first X-ray dose signal of each fixed sub-region within the control area. The inspection personnel carry the inspection-type radiation dose monitoring module to collect the second neutron dose signal and the second X-γ ray dose signal in the non-covered area within the control zone at predefined inspection cycles. The third neutron dose signal and the third X-γ ray dose signal at the control area where the staff are located are collected using personal radiation dose monitoring modules worn by the staff. Step 2: Calculate the radiation coefficient of the corresponding fixed sub-region based on the first neutron dose signal and the first X-γ ray dose signal collected by the fixed radiation dose monitoring module associated with each fixed sub-region within the control area. Map the radiation coefficients of all fixed sub-regions associated with the control area to the three-dimensional control area map associated with the control area to construct the three-dimensional control area radiation coefficient map; Step 3: Based on the determined three-dimensional control area radiation coefficient map, as well as the second neutron dose signal and the second X-γ ray dose signal of the non-covered area within the control area, calculate the radiation coefficient of the non-covered area associated with the non-covered area within the control area, and map it to the three-dimensional control area radiation coefficient map associated with the control area to improve the three-dimensional control area radiation coefficient map. Based on the three-dimensional radiation coefficient map of the control area, the risk areas and safe areas within the control area are comprehensively assessed and marked. Step 4: Obtain the personal radiation dose monitoring module worn by any staff member, locate the staff member in real time, and determine the first and second danger signals associated with the staff member in real time by combining the determined three-dimensional control area radiation coefficient map, and give the staff member a real-time reminder.
2. The method according to claim 1, characterized in that, In step one, the fixed radiation dose monitoring module includes one fixed neutron dosimeter, one fixed X-γ dosimeter, and a radiation management system. The radiation management system is pre-built by the operator and is determined and unique. The inspection-type radiation dose monitoring module includes one inspection-type neutron dosimeter, one inspection-type X-γ dosimeter, and a communication device. The personal radiation dose monitoring module includes a personal dose alarm, a communication device, a display device, and a positioning device. The personal radiation dose monitoring module is worn by the staff.
3. The method according to claim 1, characterized in that, In step one, the method for determining each fixed point within the control area is as follows: Obtain all floors in the proton radiotherapy facility, and denote any one of these floors as a control zone, denoted as CZ; The control area CZ is mapped using a 3D mapping tool to obtain the 3D control area map CZM associated with the control area CZ; Obtain plane M1 corresponding to the ground plane of control area CZ in the 3D control area map CZM; Determine the point corresponding to the main entrance of the control area CZ in plane M1, and denote it as point D1; Find the far corner vertex in plane M1 that is opposite to point D1, and denote it as point D2; Connect points D1 and D2, construct the perpendicular bisector of the line connecting the two points, and determine the two intersection points of this perpendicular bisector with the boundary of plane M1, denoted as points D3 and D4 respectively. Connect the four points clockwise to obtain a unique and closed quadrilateral CQ; Simultaneously translate the four sides of quadrilateral CQ inwards, with the translation distance successively taken as 1 / X, 2 / X, and 3 / X of the longest diagonal length in plane M1, to obtain three inwardly shrunk quadrilaterals, denoted as quadrilateral CQ1, quadrilateral CQ2, and quadrilateral CQ3, respectively. The value of X is determined by the operator. Quadrilaterals CQ1, CQ2, and CQ3 are all located in plane M1. At the midpoint of each side of quadrilaterals CQ, CQ1, CQ2, and CQ3, draw a perpendicular line that is perpendicular to the side and points into the quadrilateral. The length of the perpendicular line is equal to the corresponding translation distance. Mark the end point of each perpendicular line as a fixed point, resulting in 12 fixed points. Twelve fixed points were mapped to the control area CZ, and a fixed radiation dose monitoring module was installed at each fixed point at a height h preset by the operator.
4. The method according to claim 3, characterized in that, In step one, the method for determining the fixed sub-regions within the control area is as follows: S41. Take the 12 fixed points located at height h within the control area CZ as the center; S42. Simultaneously expand the 12 centers along the six orthogonal directions in three-dimensional space to form six expansion surfaces. The initial value of the expansion step size is 1 / 2Y of the length of the longest diagonal of plane M1, and the expansion step size gradually increases. Y is a value preset by the operator and Y is not less than X. S43. If any two centers are connected by their associated expansion surfaces, stop increasing the expansion step size. Record the closed hexahedron formed by the six expansion surfaces associated with each of the 12 centers as the fixed sub-regions associated with the corresponding centers, and label the 12 fixed sub-regions in the three-dimensional control area map CZM. S44. The first neutron dose signal and the first X-γ ray dose signal of all spatial points within the fixed sub-region are uniformly characterized by the fixed radiation dose monitoring module installed at the center of the fixed sub-region. S45. If the control area CZ undergoes physical changes, repeat steps S41 to S44 to refresh the geometric boundaries of all fixed sub-areas.
5. The method according to claim 4, characterized in that, In step one, the specific method for acquiring the second neutron dose signal and the second X-γ ray dose signal in the non-covered area within the control zone is as follows: Obtain the predefined inspection cycle T and time window ΔT by the operator; Obtain the 12 fixed sub-regions in the 3D control area map (CZM); The complete three-dimensional space volume of the three-dimensional control zone map CZM is denoted as V_total; Perform a Boolean union operation on the three-dimensional spatial volumes associated with the 12 fixed sub-regions to obtain the covered spatial volume V_cov; Perform a Boolean difference operation between the complete 3D space volume V_total and the covered space volume V_cov to obtain the remaining space volume; The remaining space volume is the non-covered area within the control area CZ, denoted as V_rem; Based on the inspection cycle T, the non-covered area V_rem within the control zone CZ is detected within a time window ΔT, and the detected second neutron dose signal and second X-γ ray dose signal are recorded.
6. The method according to claim 1, characterized in that, In step two, the specific method for calculating the radiation coefficient of the corresponding fixed sub-region is as follows: S61. Obtain any fixed sub-region, and collect the first neutron dose signal A1 and the first X-γ ray dose signal B1 associated with this fixed sub-region. The collection frequency F and the time window Δt are determined by the operator. S62. Take the average value of the first neutron dose signal A1 and the first X-γ ray dose signal B1 within any time window Δt to obtain the average value signal of the first neutron dose A1_avg and the average value signal of the first X-γ ray dose B1_avg. S63. Extract the equivalent doses A1_avg` and B1_avg` associated with the first neutron dose mean signal A1_avg and the first X-ray gamma ray dose mean signal B1_avg, respectively. The weighted summation of the equivalent doses A1_avg` and B1_avg` yields the comprehensive dose value CDV. Among them, the weighting factor of the equivalent dose A1_avg` is α, and the weighting factor of the equivalent dose B1_avg` is β. Both α and β are predefined by the operator. Both α and β are greater than 0, and α+β=1. S64. Divide the calculated comprehensive dose value CDV by the volume of this fixed sub-region to obtain the radiation dose density ρ; S65. Compare the radiation dose density ρ with the reference dose density ρ0 preset by the operator to obtain the radiation coefficient R of the fixed sub-area: R = ρ / ρ0. S66. Repeat steps S61 to S65 to determine the radiation coefficient of each of the 12 fixed sub-regions associated with the three-dimensional control area map CZM. S67. Write the radiation coefficients of the fixed sub-regions associated with each of the 12 fixed sub-regions into the three-dimensional control area map CZM in real time to obtain the three-dimensional control area radiation coefficient map RDA.
7. The method according to claim 6, characterized in that, In step three, the specific method for improving the three-dimensional control area radiation coefficient map is as follows: Obtain the three-dimensional control area radiation coefficient map RDA; The second neutron dose signal and the second X-γ ray dose signal associated with the uncovered region V_rem are obtained and denoted as A2 and B2, respectively. Based on the content described in S62 to S65, determine the non-covered area radiation coefficient L associated with the non-covered area V_rem; Based on the content described in S66 to S67, the non-covered area radiation coefficient L associated with the non-covered area V_rem is written into the three-dimensional control area radiation coefficient map RDA.
8. The method according to claim 7, characterized in that, In step three, the specific method for comprehensively assessing the risk areas and safe areas within the control zone is as follows: Obtain the three-dimensional control area radiation coefficient map RDA; Determine the uncovered area V_rem and 12 fixed sub-regions in the three-dimensional control area radiation coefficient map RDA; If the radiation coefficient associated with any zone is greater than or equal to 1, it is marked as a risk zone; otherwise, it is marked as a safe zone. The risk areas are marked in red, and the safe areas are marked in green.
9. The method according to claim 8, characterized in that, In step four, the specific method for determining the first and second danger signals associated with the staff in real time and providing real-time alerts to the staff is as follows: Based on the personal radiation dose monitoring module worn by the staff, the staff's location P and the third neutron dose signal and third X-γ ray dose signal at the staff's location P are acquired in real time and are denoted as A3 and B3, respectively. Based on the contents described in S62 to S65, determine the personal radiation coefficient U associated with the third neutron dose signal A3 and the third X-ray gamma-ray dose signal B3; If an individual's radiation coefficient U is greater than or equal to 1, the first danger signal is issued to the staff. If the individual radiation coefficient U is less than 1, the worker's location P is mapped to the three-dimensional control area radiation coefficient map RDA; Calculate the straight-line distance JL between the worker's location P and the nearest risk area in the three-dimensional control zone radiation coefficient map RDA. If JL is lower than a preset threshold, issue a second danger signal. Conversely, continuous monitoring is required.
10. A multi-point real-time radiation dose monitoring system for proton radiotherapy environments, characterized in that, The system includes: The global sensing and acquisition terminal uses fixed radiation dose monitoring modules deployed at fixed points within the control area to collect the first neutron dose signal and the first X-γ ray dose signal of each fixed sub-region within the control area. The inspection personnel carry the inspection-type radiation dose monitoring module to collect the second neutron dose signal and the second X-γ ray dose signal in the non-covered area within the control zone at predefined inspection cycles. The third neutron dose signal and the third X-γ ray dose signal at the control area where the staff are located are collected using personal radiation dose monitoring modules worn by the staff. The dynamic radiation modeling end calculates the radiation coefficient of the corresponding fixed sub-region based on the first neutron dose signal and the first X-γ ray dose signal collected by the fixed radiation dose monitoring module associated with each fixed sub-region in the control area. Map the radiation coefficients of all fixed sub-regions associated with the control area to the three-dimensional control area map associated with the control area to construct the three-dimensional control area radiation coefficient map; At the regional collaborative optimization end, based on the determined three-dimensional control area radiation coefficient map, as well as the second neutron dose signal and the second X-γ ray dose signal of the non-covered area within the control area, the radiation coefficient of the non-covered area associated with the control area is calculated and mapped to the three-dimensional control area map associated with the control area to improve the three-dimensional control area radiation coefficient map. Based on the three-dimensional radiation coefficient map of the control area, the risk areas and safe areas within the control area are comprehensively assessed and marked. The intelligent radiation and personnel monitoring terminal acquires the personal radiation dose monitoring module worn by any worker, locates the worker in real time, and determines the first and second danger signals associated with the worker in real time by combining the determined three-dimensional control area radiation coefficient map, and provides real-time reminders to the worker.