Boron neutron capture therapy equipment irradiation field scattered radiation measuring device
By designing a multi-point measurement device, combining multiple radiation detectors and adjustable stents, the accuracy of BNCT equipment in the field of irradiation is solved, and high-precision radiation dose control is achieved to protect patient safety.
Patent Information
- Application Number
- CN202422446347.0
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2024-10-10
- Publication Date
- 2025-08-26
- Estimated Expiration
- 2034-10-10
AI Technical Summary
When measuring the irradiated radiation in the field, existing BNCT equipment has problems such as few measurement points, complicated arrangement, single detector types, large deviations in measurement results, and high-energy neutrons and gamma rays that do not form electron balance, resulting in serious underestimation of the detection results.
A device including horizontal support rods, adjustable brackets and multiple sets of measurement components is designed. A variety of radiation detectors such as thermal and light-emitting dose sheets are used to achieve multi-point accurate measurement, combining a distance indicator ruler and adjustable bracket to ensure measurement accuracy and stability.
High-precision measurement of the BNCT equipment irradiated with field leakage radiation is realized, which avoids excessive radiation of normal tissue and protects the safety of patients. The device can arrange multiple measurement points on the patient plane, reducing measurement deviations.
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Figure CN223272683U_ABST
Abstract
Description
Technical Field
[0001] The utility model relates to the technical field of quality control and detection of new radiological diagnosis and treatment equipment in radiation protection, in particular to a device for measuring field leakage radiation of boron neutron capture treatment equipment. Background Art
[0002] Boron Neutron Capture Therapy (BNCT) differs fundamentally from radiotherapy devices such as proton and heavy ion accelerators and traditional electron linear accelerators. It utilizes neutrons to react with boron within tumors, producing heavy particles to destroy cancer cells. This dual-therapy approach, combining radiation and drugs, is targeted and precise at the cellular level. BNCT, with its advantages of targeted, in-depth treatment, minimal side effects, and relatively low cost, has become a new hotspot in the field of cancer treatment both domestically and internationally. The number of medical institutions in China that have implemented or are planning to implement BNCT radiotherapy is rapidly increasing.
[0003] Unlike conventional radiotherapy, which can take weeks to months to complete, BNCT treatment requires only one or two irradiation sessions. Therefore, both the tumor dose within the irradiation field and the scattered radiation dose outside the irradiation field during BNCT treatment are significantly higher than those of conventional radiotherapy. Therefore, controlling the leakage and scattered radiation dose to normal tissue outside the irradiation field during BNCT treatment to an appropriate level is crucial for protecting the patient's normal tissues from excessive radiation exposure. Therefore, measuring scattered radiation outside the BNCT irradiation field at the patient level (5 cm from the device) is particularly important.
[0004] BNCT is a new type of radiotherapy device, and currently lacks an integrated device for measuring scattered radiation. Current BNCT scattered radiation measurement systems often utilize a single-point support structure, which presents challenges such as a limited number of measurement points, cumbersome dosimeter placement, a limited number of detector types, and significant deviations in the vertical, horizontal, and forward / backward positioning of each measurement point. More critically, existing single-point measurement supports lack radiation-building materials or are inconvenient to place around dosimeters and other radiation detectors. This results in high-energy scattered neutrons and gamma rays being detected by the dosimeter before electron equilibrium is achieved, significantly underestimating the test results. Utility Model Content
[0005] The purpose of the utility model is to solve at least one technical problem in the background technology and provide a device for measuring the scattered radiation leakage in the irradiation field of a boron neutron capture therapy device.
[0006] To achieve the above-mentioned purpose, the present invention provides a device for measuring the scattered radiation of a boron neutron capture therapy device, comprising:
[0007] a horizontal support rod with scales provided thereon;
[0008] A plurality of adjustable brackets are arranged at intervals and used to support the horizontal support rod and adjust the height of the horizontal support rod;
[0009] The measuring component is detachably mounted on the horizontal support rod, and its position on the horizontal support rod can be adjusted according to measurement requirements, and is used to measure the scattered radiation dose of the boron neutron capture therapy device in the field.
[0010] According to one aspect of the present invention, the horizontal support rod is composed of a single aluminum alloy tube with a scale, or the horizontal support rod is composed of a plurality of aluminum alloy tubes with a scale spliced together.
[0011] According to one aspect of the present invention, it further includes: at least two distance indicators, each of which is spaced apart from each other and is flippably arranged on the horizontal support rod, and each of the distance indicators is used to limit the distance between the boron neutron capture therapy device and the horizontal support rod.
[0012] According to one aspect of the present invention, there are three distance indicator rulers, each of which is evenly spaced at both ends and the middle of the horizontal support rod, and the length of each distance indicator ruler is 5 cm.
[0013] According to one aspect of the present invention, the adjustable support comprises a telescopic tripod and a headrest;
[0014] The head support is supported on the top of the telescopic tripod. The head support has a U-shaped groove. The horizontal support rod is supported in the U-shaped groove. The depth of the U-shaped groove is the same as the height of the horizontal support rod.
[0015] According to one aspect of the present invention, the measurement assembly includes a fixture and a scattered radiation measurement irradiation structure;
[0016] The clamp includes a clamping claw and an adjusting bolt arranged on the clamping claw;
[0017] The scattered radiation measurement irradiation structure is supported on the top of the fixture;
[0018] The scattered radiation measurement irradiation structure includes a support and a dose sheet support plate;
[0019] The support bracket includes a bottom plate, a first bent plate and a second bent plate;
[0020] The first bent plate and the second bent plate are supported on the bottom plate opposite to and spaced apart from each other;
[0021] The dosage sheet support plate is detachably supported between the first bent plate and the second bent plate;
[0022] The dosage sheet support plate is provided with a circular mounting groove and a rectangular mounting groove.
[0023] According to one aspect of the present invention, the first bent plate and the second bent plate are organic glass plates with a thickness of 1 cm.
[0024] According to one aspect of the present utility model, the dosage sheet support plate is provided with three rows of the circular mounting grooves and one row of the rectangular mounting grooves;
[0025] Each row of circular mounting grooves is respectively equipped with thermoluminescent dose tablets LiF (Mg, Cu, P), 6 LiF(Mg,Cu,P) and 7 LiF(Mg,Cu,P);
[0026] The rectangular mounting groove is equipped with an OSL dosimeter or a gold activation detector;
[0027] The thermoluminescent dose sheet has a diameter of 4.5 mm and a thickness of 0.8 mm;
[0028] The optically luminescent dose sheet has a length of 10 mm, a width of 10 mm, and a thickness of 2 mm;
[0029] The gold activation detector can be a gold foil or a gold wire. The diameter of the gold foil is 10 mm and the thickness is 0.05 mm; the diameter of the gold wire is 0.5 mm and the length is 10 mm.
[0030] According to one aspect of the present invention, the surface of the base plate facing away from the first bent plate and the second bent plate is marked with horizontal scale lines and vertical scale lines, and the intersection of the horizontal scale lines and the vertical scale lines is the center position of the scattered radiation exposure measurement structure; during measurement, the horizontal scale lines are aligned with the treatment room positioning laser line so that the scattered radiation exposure measurement structure is located at the required measurement height.
[0031] According to one embodiment of the present invention, a device for measuring radiation leakage during field exposure of a boron neutron capture therapy device comprises: a horizontal support rod having a scale thereon; a plurality of adjustable brackets arranged at intervals to support the horizontal support rod and adjust the height of the horizontal support rod; and a plurality of measurement components detachably mounted on the horizontal support rod, the positions of which can be adjusted according to measurement requirements, for measuring radiation leakage during field exposure of the boron neutron capture therapy device. This arrangement allows the horizontal support rod and the measurement components mounted thereon to be adjusted to a suitable height via the plurality of adjustable brackets. Then, according to measurement requirements, a certain number (not less than 12 groups) of measurement components can be conveniently and precisely adjusted to relevant positions according to the scale on the horizontal support rod to accurately measure the radiation leakage dose, thereby scientifically controlling the radiation leakage level of the boron neutron capture therapy device, avoiding unnecessary excessive irradiation of normal tissues, and protecting patient safety.
[0032] According to one embodiment of the present invention, the present invention further comprises at least two distance indicators, each of which is spaced apart and reversibly disposed on the horizontal support rod, each of which is used to define the distance between the boron neutron capture therapy device and the horizontal support rod. This arrangement allows the distance between the boron neutron capture therapy device and the horizontal support rod to be defined by each distance indicator, thereby ensuring an appropriate measurement distance between the horizontal support rod and the multiple measurement assemblies thereon and the boron neutron capture therapy device, thereby ensuring accurate measurement results.
[0033] According to one embodiment of the present invention, the adjustable support comprises a telescopic tripod and a headrest. The headrest is supported on the top of the telescopic tripod and has a U-shaped groove. The horizontal support rod is supported within the U-shaped groove. The depth of the U-shaped groove is the same as the height of the horizontal support rod. This arrangement ensures that the horizontal support rod is stably and securely supported on the adjustable support. The height of the horizontal support rod and the structure above it can be adjusted using the adjustable support to ensure accurate detection position.
[0034] According to the solution of the present invention, the present invention integrates thermoluminescent dose sheets 6LiF (Mg, Cu, P), 7LiF (Mg, Cu, P), LiF (Mg, Cu, P), optically stimulated luminescent dose sheets OSL, and a gold activation detector. The BNCT can measure the scattered neutron and gamma radiation doses in one beam, and can realize the measurement of scattered gamma ray and neutron doses using two different methods, which is a domestic first; secondly, the device can arrange at least 12 measurement sites at one time with high precision within a total length of 4 meters on the patient plane, avoiding the tediousness of individual point arrangement and measurement position deviation; finally, the measurement component of the device consists of two 1 cm thick high-purity PMMA plates in the front and rear, and the dose sheet is located in the installation groove therein. When measuring the scattered radiation, an effective dose built-up area is formed in all directions, ensuring the accuracy of the measurement. BRIEF DESCRIPTION OF THE DRAWINGS
[0035] Figure 1 A diagram schematically showing a state of use of a device for measuring stray radiation leakage in an irradiation field of a boron neutron capture therapy device according to an embodiment of the present utility model;
[0036] Figure 2 A schematic diagram showing the structural arrangement of a support bracket according to an embodiment of the present invention;
[0037] Figure 3 The figure schematically shows the structural arrangement of a dosage sheet support plate according to one embodiment of the present invention. DETAILED DESCRIPTION
[0038] The present invention will now be discussed with reference to exemplary embodiments. It should be understood that the embodiments discussed are only intended to enable those skilled in the art to better understand and implement the present invention, rather than to imply any limitation on the scope of the present invention.
[0039] As used herein, the term "including" and variations thereof are to be interpreted as open-ended terms meaning "including, but not limited to." The term "based on" is to be interpreted as "based, at least in part, on." The terms "one embodiment" and "an embodiment" are to be interpreted as "at least one embodiment."
[0040] Figure 1 The following diagram schematically shows the use status of the device for measuring the stray radiation of the irradiation field of the boron neutron capture therapy device according to one embodiment of the present invention. Figure 1 As shown, in this embodiment, the device for measuring stray radiation leakage in the field of irradiation of a boron neutron capture therapy device includes:
[0041] A horizontal support rod 1 with a scale provided thereon;
[0042] A plurality of adjustable brackets 2 are arranged at intervals and are used to support the horizontal support rod 1 and adjust the height of the horizontal support rod 1;
[0043] Multiple sets of measurement assemblies 3 are removably mounted on a horizontal support rod 1, and their positions on the rod can be adjusted according to measurement requirements. They are used to measure the dose of scattered radiation from boron neutron capture therapy equipment in the field. This arrangement allows the horizontal support rod 1 and the measurement assemblies 3 mounted thereon to be adjusted to a suitable height via multiple adjustable brackets 2. Each set of measurement assemblies 3 can then be precisely adjusted to the relevant position according to the scale on the horizontal support rod 1, allowing for precise measurement of scattered radiation dose. This ensures the accuracy of the measurement results, thereby ensuring patient safety during treatment.
[0044] It should be noted that Figure 1 The boron neutron capture therapy device (BNCT device) 16 is Figure 1 The device for measuring the scattered radiation outside the irradiation field of the boron neutron capture therapy equipment of the present invention is arranged face to face, rather than up and down. The beam outlet 17 of the boron neutron capture therapy equipment 16 emits the beam horizontally. The device for measuring the scattered radiation outside the irradiation field of the boron neutron capture therapy equipment of the present invention accurately measures the scattered radiation dose in the range outside the horizontal irradiation field of the beam outlet.
[0045] Further, if Figure 1 As shown, in this embodiment, the horizontal support rod 1 is composed of a single aluminum alloy tube with scales, or the horizontal support rod 1 is composed of multiple aluminum alloy tubes with scales.
[0046] Further, if Figure 1 As shown, in this embodiment, the present invention further includes: at least two distance indicators 4, each distance indicator 4 being spaced apart and reversibly arranged on the horizontal support rod 1, and each distance indicator 4 being used to define the distance between the boron neutron capture therapy device and the horizontal support rod 1. Such an arrangement allows the distance between the boron neutron capture therapy device 16 and the horizontal support rod 1 to be defined by each distance indicator 4, thereby ensuring that a suitable measurement distance exists between the horizontal support rod 1 and the multiple groups of measurement assemblies 3 thereon and the boron neutron capture therapy device 16, thereby ensuring accurate measurement results.
[0047] Further, if Figure 1 As shown, in this embodiment, three distance indicators 4 are provided, each evenly spaced at both ends and the middle of the horizontal support rod 1. Each distance indicator 4 is 5 cm long. This arrangement ensures a uniform and precise distance between the horizontal support rod 1 and the boron neutron capture therapy device 16, ensuring a distance of 5 cm between the horizontal support rod 1 and the boron neutron capture therapy device 16.
[0048] Further, if Figure 1 As shown, in this embodiment, the adjustable support 2 includes a telescopic tripod 5 and a headrest 6;
[0049] The headrest 6 is supported on the top of the telescopic tripod 5. The headrest 6 has a U-shaped groove (not shown in the figure). The horizontal support rod 1 is supported in the U-shaped groove. The depth of the U-shaped groove is the same as the height of the horizontal support rod 1. This arrangement can ensure that the horizontal support rod 1 is stably and securely supported on the adjustable bracket 2. The adjustable bracket 2 can also be used to adjust the height of the horizontal support rod 1 and the structure above it, ensuring the accuracy of the detection position.
[0050] Further, if Figure 1As shown, in this embodiment, the measurement assembly 3 includes a fixture 7 and a scattered radiation measurement irradiation structure 8;
[0051] The clamp 7 includes a clamping claw 9 and an adjusting bolt 10 provided on the clamping claw 9;
[0052] The scattered radiation measurement irradiation structure 8 is supported on the top of the fixture 7;
[0053] The scattered radiation measurement irradiation structure 8 includes a support 11 and a dose sheet support plate 12;
[0054] like Figure 1 、 Figure 2 and Figure 3 As shown, the support bracket 11 includes a bottom plate 13, a first bent plate 14 and a second bent plate 15;
[0055] The first bent plate 14 and the second bent plate 15 are supported on the bottom plate 13 opposite to and spaced apart from each other;
[0056] The first bent plate 14 or the second bent plate 15 is provided with a mounting hole 22, and the support bracket 11 is supported on the claw 9 through the connection between the mounting hole 22 and the support rod 23;
[0057] The dose sheet support plate 12 is detachably supported between the first bent plate 14 and the second bent plate 15 and faces the boron neutron capture therapy device 16;
[0058] The dose sheet support plate 12 is provided with a circular mounting groove 18 and a rectangular mounting groove 19. Such an arrangement allows the dose sheet support plate 12 to stably support the dose sheet through the support bracket 11, and allows accurate measurement of scattered radiation through the dose sheet.
[0059] Furthermore, in this embodiment, the first bent plate 14 and the second bent plate 15 are organic glass plates with a thickness of 1 cm.
[0060] Further, if Figure 3 As shown, in this embodiment, the dose sheet support plate 12 is provided with three rows of circular mounting grooves 18 and one row of rectangular mounting grooves 19;
[0061] Each row of circular mounting grooves 18 is respectively provided with thermoluminescent dosimeters LiF (Mg, Cu, P), 6 LiF(Mg,Cu,P) and 7 LiF(Mg,Cu,P);
[0062] The rectangular mounting slot 19 is provided with an OSL dosimeter or a gold activation detector;
[0063] The diameter of the thermoluminescent dose sheet is 4.5 mm and the thickness is 0.8 mm;
[0064] The optically stimulated luminescence dose sheet is 10 mm long, 10 mm wide, and 2 mm thick;
[0065] The gold activation detector can be a gold foil or a gold wire, with the gold foil having a diameter of 10 mm and a thickness of 0.05 mm; the gold wire having a diameter of 0.5 mm and a length of 10 mm. This configuration allows the BNCT to measure the scattered neutron and gamma photon radiation doses in one beam outflow through the beam outlet 17.
[0066] Further, if Figure 1 As shown, in this embodiment, the surface of the bottom plate 13 facing away from the first bent plate 14 and the second bent plate 15 is marked with horizontal scale lines 20 and vertical scale lines 21, and the intersection of the horizontal scale lines and the vertical scale lines is the center position of the scattered radiation exposure measurement structure 8; when measuring, the horizontal scale lines are aligned with the treatment room positioning laser line, so that the scattered radiation exposure measurement structure 8 is located at the required measurement height.
[0067] According to the above scheme of the present invention, the present invention can effectively realize accurate and reliable measurement of the leakage radiation dose of the BNCT device, scientifically control the leakage radiation level of the boron neutron capture therapy device, avoid unnecessary excessive irradiation of normal tissues, and protect patient safety.
[0068] Finally, it should be noted that the above preferred embodiments are only used to illustrate the technical solutions of the present invention and are not limiting. Although the present invention has been described in detail through the above preferred embodiments, those skilled in the art should understand that various changes can be made in form and details without departing from the scope defined by the claims of the present invention.
Claims
1. Boron neutron capture therapy equipment irradiation field leakage radiation measurement device, characterized in that: include: a horizontal support rod (1) having a scale thereon; A plurality of adjustable brackets (2) are arranged at intervals from each other and are used to support the horizontal support rod (1) and to adjust the horizontal height of the horizontal support rod (1); Multiple groups of measurement components (3) are detachably clamped on the horizontal support rod (1), and the position of clamping on the horizontal support rod (1) can be adjusted according to measurement requirements, and are used to measure the dose of scattered radiation emitted by a boron neutron capture therapy device in the field.
2. The device for measuring stray radiation from a boron neutron capture therapy device according to claim 1, characterized in that: The horizontal support rod (1) is composed of a single aluminum alloy tube with scales, or the horizontal support rod (1) is composed of a plurality of aluminum alloy tubes with scales spliced together.
3. The device for measuring stray radiation from a boron neutron capture therapy device according to claim 1, characterized in that: Also includes: At least two distance indicator rulers (4) are provided, each of the distance indicator rulers (4) being spaced apart from each other and arranged flippably on the horizontal support rod (1), and each of the distance indicator rulers (4) is used to define a horizontal distance between a boron neutron capture therapy device and the horizontal support rod (1).
4. The device for measuring stray radiation leakage during irradiation of a boron neutron capture therapy device according to claim 3, characterized in that: The distance indicator rulers (4) are provided in three numbers, and each of the distance indicator rulers (4) is evenly spaced and arranged at both ends and the middle of the horizontal support rod (1). The length of each of the distance indicator rulers (4) is 5 cm.
5. The device for measuring stray radiation leakage during irradiation of a boron neutron capture therapy device according to claim 1, characterized in that: The adjustable support (2) comprises a telescopic tripod (5) and a headrest (6); The head support (6) is supported on the top end of the telescopic tripod (5), and the head support (6) has a U-shaped groove, and the horizontal support rod (1) is supported in the U-shaped groove, and the depth of the U-shaped groove is the same as the height of the horizontal support rod (1).
6. The device for measuring stray radiation leakage during irradiation of a boron neutron capture therapy device according to claim 1, characterized in that: The measuring assembly (3) comprises a fixture (7) and a scattered radiation measurement irradiation structure (8); The clamp (7) comprises a clamping claw (9) and an adjusting bolt (10) arranged on the clamping claw (9); The scattered radiation measurement irradiation structure (8) is supported on the top of the fixture (7); The scattered radiation measurement irradiation structure (8) comprises a support bracket (11) and a dose sheet support plate (12); The support bracket (11) comprises a bottom plate (13), a first bent plate (14) and a second bent plate (15); The first bent plate (14) and the second bent plate (15) are supported on the bottom plate (13) in a manner that is opposite to and spaced apart from each other; The dosage sheet support plate (12) is detachably supported between the first bent plate (14) and the second bent plate (15); The dosage sheet support plate (12) is provided with a circular mounting groove (18) and a rectangular mounting groove (19).
7. The device for measuring stray radiation leakage during irradiation of a boron neutron capture therapy device according to claim 6, characterized in that: The first bent plate (14) and the second bent plate (15) are both organic glass plates with a thickness of 1 cm.
8. The device for measuring stray radiation leakage during irradiation of a boron neutron capture therapy device according to claim 6, characterized in that: The dosage sheet support plate (12) is provided with three rows of circular mounting grooves (18) and one row of rectangular mounting grooves (19); Each row of the circular mounting grooves (18) is respectively provided with thermoluminescent dosage sheets LiF (Mg, Cu, P), 6 LiF(Mg,Cu,P) and 7 LiF(Mg,Cu,P); The rectangular mounting groove (19) is provided with an OSL dosimeter or a gold activation detector; The thermoluminescent dose sheet has a diameter of 4.5 mm and a thickness of 0.8 mm; The optically luminescent dose sheet has a length of 10 mm, a width of 10 mm, and a thickness of 2 mm; The gold activation detector can be a gold foil or a gold wire. The diameter of the gold foil is 10 mm and the thickness is 0.05 mm; the diameter of the gold wire is 0.5 mm and the length is 10 mm.
9. The device for measuring stray radiation leakage in the irradiation field of a boron neutron capture therapy device according to any one of claims 6 to 8, characterized in that: The surface of the bottom plate (13) facing away from the first bent plate (14) and the second bent plate (15) is marked with horizontal scale lines (20) and vertical scale lines (21), and the intersection of the horizontal scale lines and the vertical scale lines is the center position of the scattered radiation measurement irradiation structure (8); when measuring, the horizontal scale lines are aligned with the treatment room positioning laser line, so that the scattered radiation measurement irradiation structure (8) is located at a required measurement height.