Dose verification device for boron neutron capture therapy

Abstract

The invention relates to the technical field of boron neutron capture therapy, in particular to a dose verification device for boron neutron capture therapy. The objective of the invention is to solve the technical problem that dose distribution of tumor tissues and surrounding thereof cannot be accurately measured. To this end, the dose verification device of the present application comprises: a box; the die body assemblies move in the incident direction of the neutron beam and are arranged in a stacked mode; the die body insertion plate comprises a tumor tissue simulation positioning area containing boron-10 with a first concentration and / or a normal tissue simulation positioning area containing boron-10 with a second concentration, and the first concentration is greater than the second concentration; the dose detection module is used for detecting distribution data of secondary particles generated after the boron-10 and neutrons are subjected to nuclear reaction; and the data processing module is used for acquiring the distribution data and determining the dose distribution in the die body assembly according to the distribution data. According to the application, the difference of the boron-10 concentration of the tumor tissue and the normal tissue can be better simulated, and the dose distribution of the tumor tissue and the surrounding thereof can be more accurately measured.

Description

Technical Field

[0001] The present application relates to the technical field of boron neutron capture therapy, and particularly relates to a dose verification device for boron neutron capture therapy. Background Art

[0002] Boron Neutron Capture Therapy (BNCT) is a radiotherapy technique based on nuclear reactions. Its principle is to inject a boron-10-containing drug into a patient's body, and utilize the high selectivity of tumor tissues for boron-10 uptake, so that the boron-10 atomic nucleus undergoes 10 B(n,α) 7 Li nuclear reaction under thermal neutron irradiation, releasing high-energy α particles and 7 Li recoil nuclei, thereby accurately killing tumor cells. In order to ensure the treatment effect and minimize the damage to normal tissues, it is necessary to conduct a dose verification experiment before the patient's treatment to accurately evaluate the dose distribution absorbed by each tissue in the organism.

[0003] Related technologies use a water tank to simulate human tissues for dose verification experiments, and calculate the dose distribution in human tissues by measuring the distribution of neutron beams in the water tank. However, it is difficult for the water tank to simulate the boron-10 distribution around tumor tissues, and it is impossible to accurately measure the dose distribution of tumor tissues and their surroundings.

[0004] Correspondingly, a new technical solution is needed in this field to solve the above problems. Summary of the Invention

[0005] In order to solve at least one of the above problems in the prior art, that is, to solve the technical problem that it is difficult for a water tank to simulate the boron-10 distribution around tumor tissues and it is impossible to accurately measure the dose distribution of tumor tissues and their surroundings.

[0006] The present application provides a dose verification device for boron neutron capture therapy. The dose verification device includes: a box body disposed in a neutron radiation field; a phantom assembly including a plurality of phantom inserts movably disposed in the box body, and the phantom inserts are stacked along the incident direction of the neutron beam; wherein each of the phantom inserts includes a tumor tissue-like positioning area and / or a normal tissue-like positioning area, and the concentration of boron-10 nuclide contained in the tumor tissue-like positioning area is greater than the concentration of boron-10 nuclide contained in the normal tissue-like positioning area; a dose detection module for detecting distribution data of secondary particles generated after the boron-10 nuclide undergoes a nuclear reaction with neutrons in the phantom assembly; and a data processing module for acquiring the distribution data and determining the dose distribution in the phantom assembly according to the distribution data.

[0007] In some embodiments, the phantom insert plate includes: a first housing; a plurality of first sub-phantoms disposed within the first housing; a plurality of second sub-phantoms disposed within the first housing; wherein, the concentration of boron-10 contained in the first sub-phantom is greater than the concentration of boron-10 contained in the second sub-phantom; the tumor-mimicking tissue positioning region is composed of one or more of the first sub-phantoms, and the normal-tissue-mimicking tissue positioning region is composed of one or more of the second sub-phantoms.

[0008] In some embodiments, the first sub-phantom and the second sub-phantom are both cubic structures, and the tumor-mimicking tissue positioning region is composed of one or more of the first sub-phantoms spliced together in a detachable manner, and the normal-tissue-mimicking tissue positioning region is composed of one or more of the second sub-phantoms spliced together in a detachable manner.

[0009] In some embodiments, the dose detection module includes: a detector insert plate disposed between two adjacent phantom insert plates for detecting distribution data of secondary particles generated after the nuclear reaction of boron-10 nuclide with neutrons in the plane where the detector insert plate is located.

[0010] In some embodiments, the box body further includes a plurality of card slots disposed along the incident direction of the neutron beam, and the phantom insert plate and the detector insert plate are detachably disposed in the card slots, wherein the sizes of the detector insert plate and the phantom insert plate match the sizes of the card slots.

[0011] In some embodiments, the thickness of the card slot ranges from 1.0 cm to 1.4 cm, and the total thickness of the plurality of card slots ranges from 25 cm to 35 cm; and / or, the material of the box body is aluminum alloy, and the wall thickness of the box body ranges from 1 mm to 2 mm; and / or, the material of the first housing is aluminum alloy, and the housing thickness of the first housing ranges from 0.5 mm to 1.5 mm; and / or, the thickness of the phantom insert plate ranges from 1.0 cm to 1.4 cm; and / or, the length and width of the phantom insert plate range from 25 cm to 35 cm.

[0012] In some embodiments, the detector insert plate includes: a second housing; a PCB board disposed within the second housing; a plurality of detector arrays disposed on the PCB board, and the detector arrays correspond one-to-one in size and position to the first sub-phantom and the second sub-phantom.

[0013] In some embodiments, the detector array includes one or more of a diamond detector with a boron nitride coating, a diamond detector with a polyethylene coating, and an uncoated diamond detector.

[0014] In some embodiments, the tumor-mimicking tissue localization region and the normal-tissue-mimicking localization region further include nitrogen-14 nuclide and hydrogen-1 nuclide with the same concentration, and the dose includes boron dose, nitrogen dose, hydrogen dose, and gamma dose.

[0015] In some embodiments, the tumor-mimicking tissue localization region contains boron-10 nuclide with a first concentration, and the normal-tissue-mimicking localization region contains boron-10 nuclide with a second concentration. The value range of the first concentration is 57.5 ppm - 127.9 ppm, and the value range of the second concentration is 20.9 ppm - 46.5 ppm; and / or, the tumor-mimicking tissue localization region corresponds to the position of the tumor tissue, and the normal-tissue-mimicking localization region corresponds to the position of the normal tissue.

[0016] In the case of adopting the above technical solution, the dose verification device provided by the present application includes a plurality of phantom inserts stacked along the incident direction of the neutron beam, simulating the tumor tissue and the surrounding normal tissue within the simulated radiation field. The phantom insert includes a tumor-mimicking tissue localization region and / or a normal-tissue-mimicking localization region, which can simulate the spatial position relationship between the tumor tissue and the normal tissue. At the same time, compared with the normal-tissue-mimicking localization region, the tumor-mimicking tissue localization region contains a higher concentration of boron-10 nuclide, which can more realistically simulate the difference in boron-10 nuclide concentration between the tumor tissue and the normal tissue, so as to more accurately measure the dose distribution of the tumor tissue and its surrounding area. In addition, the phantom insert can be movably arranged, and each phantom insert can independently adjust the tumor-mimicking tissue localization region and the normal-tissue-mimicking localization region, enabling the dose verification device to flexibly adapt to the tumor positions and sizes of different patients and meet the personalized dose verification requirements. Description of the Drawings

[0017] The dose verification device of the present application will be described below with reference to the drawings. In the drawings:

[0018] Figure 1 is a schematic structural diagram of the dose verification device provided by the present application;

[0019] Figure 2 is Figure 1 a schematic structural diagram of the phantom insert in

[0020] Figure 3 is Figure 2 a partial enlarged structural diagram of the tumor-mimicking tissue localization region and the normal-tissue-mimicking localization region in

[0021] Figure 4 is Figure 1 a schematic structural diagram of the detector insert of the dose detection module in

[0022] Figure 5 is Figure 4 a schematic structural diagram of the detector array of the detector insert in

[0023] Figure 6 Schematic structural diagram of the data processing module of the dose verification device;

[0024] Figure 7 Schematic structural diagram of the dose verification device arranged at the beam outlet of the collimator of the boron neutron capture therapy device.

[0025] List of reference numerals

[0026] 1. Box body; 2. Phantom assembly; 201. Phantom insert plate; 2011. First sub-phantom; 2012. Second sub-phantom; 202. Tumor-like tissue positioning area; 203. Normal tissue-like positioning area; 4. Dose detection module; 401. Detector insert plate; 4011. Detector array; 5. Data processing module. Detailed implementation manners

[0027] The preferred implementation manners of the present application will be described below with reference to the accompanying drawings. Those skilled in the art should understand that these implementation manners are only used to explain the technical principle of the present application and are not intended to limit the protection scope of the present application. For example, although the following implementation manners of the present application are described in conjunction with an air duct machine, this is not intended to limit the protection scope of the present application. Without departing from the principle of the present application, the present application can also be applied to other devices.

[0028] It should be noted that in the description of the present application, the terms indicating directions or positional relationships such as "middle", "upper", "lower", "vertical", "inner", "outer", etc. are based on the directions or positional relationships shown in the drawings. This is only for convenience of description and does not indicate or imply that the device or element must have a specific orientation, be constructed and operated in a specific orientation, and therefore cannot be understood as a limitation to the present application. In addition, the terms "first" and "second" are only used for descriptive purposes and cannot be understood as indicating or implying relative importance. "Plural" means two or more.

[0029] In addition, it should also be noted that in the description of the present application, unless otherwise clearly specified and limited, the terms "installed", "connected", and "connected" should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be directly connected or indirectly connected through an intermediate medium, and it can be the communication inside two elements. For those skilled in the art, the specific meanings of the above terms in the present application can be understood according to specific circumstances.

[0030] Such as Figure 7As shown, the fast neutrons generated by the accelerator in the boron neutron capture therapy device are moderated, filtered for thermal neutrons, gamma-filtered, and collimated, and then a mixed neutron beam mainly composed of epithermal neutrons is formed at the beam exit. When these neutron beams pass through the human body's surface tissue or an equivalent phantom, they are moderated by the human tissue into a beam mainly composed of thermal neutrons. After the thermal neutron beam reaches the tumor tissue, it undergoes a nuclear reaction with the drug containing the isotope boron-10 in the tumor tissue, generating α particles and 7 Li atomic nuclei. The ranges of these two heavy nuclei are extremely short, and they can deposit almost all of their energy inside the tumor cells, thus precisely killing the tumor cells while minimizing the damage to the surrounding normal tissues.

[0031] This application provides a dose verification device for boron neutron capture therapy. As shown in combination with Figure 1 、 Figure 2 and Figure 6 , the dose verification device includes a box body 1, a phantom assembly 2, a dose detection module 4, and a data processing module 5.

[0032] The box body 1 is arranged in the neutron radiation field. The box body 1 is arranged in the neutron radiation field and is located at the beam exit position of the collimator of the boron neutron capture therapy device to ensure that the neutron beam can be directly incident into the dose verification device for dose distribution verification.

[0033] The phantom assembly 2 includes a plurality of phantom inserts 201 movably arranged in the box body 1, and the phantom inserts 201 are stacked along the incident direction of the neutron beam. Among them, each phantom insert 201 includes a tumor tissue mimicking positioning area 202 and / or a normal tissue mimicking positioning area 203, and the concentration of the boron-10 nuclide contained in the tumor tissue mimicking positioning area 202 is greater than the concentration of the boron-10 nuclide contained in the normal tissue mimicking positioning area 203. During the actual treatment process, the boron-10 nuclide is injected into the patient's body through the drug, and the drug will mainly accumulate in the tumor tissue and be distributed in the normal tissue in small amounts. Here, by making the concentration of the boron-10 nuclide contained in the tumor tissue mimicking positioning area 202 greater than the concentration of the boron-10 nuclide contained in the normal tissue mimicking positioning area 203, the difference in boron-10 concentration between the tumor tissue and the non-tumor tissue can be simulated. Multiple cross-sectional picture models of the patient's tumor tissue and its surrounding normal tissues can be obtained through CT scanning, and then the tumor tissue mimicking positioning area 202 and the normal tissue mimicking positioning area 203 of each phantom insert 201 can be determined according to the cross-sectional picture models.

[0034] The dose detection module 4 is used to detect the distribution data of the secondary particles generated after the nuclear reaction of the boron-10 nuclide with neutrons in the phantom assembly 2.

[0035] The data processing module 5 is used to obtain the distribution data and determine the dose distribution in the phantom assembly 2 according to the distribution data.

[0036] In the case of adopting the above technical solution, the dose verification device provided by the present application includes a plurality of phantom inserts 201 stacked along the incident direction of the neutron beam, simulating the tumor tissue and the surrounding normal tissue within the radiation field. The phantom insert 201 includes a tumor tissue imitation positioning area 202 and / or a normal tissue imitation positioning area 203, which can simulate the spatial position relationship between the tumor tissue and the normal tissue. At the same time, compared with the normal tissue imitation positioning area, the tumor tissue imitation positioning area contains a higher concentration of boron-10 nuclide, which can more realistically simulate the difference in boron-10 nuclide concentration between the tumor tissue and the normal tissue, so as to more accurately measure the dose distribution of the tumor tissue and its surrounding area. In addition, the phantom insert 201 is movably arranged, and each phantom insert 201 can independently adjust the tumor tissue imitation positioning area 202 and the normal tissue imitation positioning area 203, so that the dose verification device can flexibly adapt to the tumor position and size of different patients and meet the personalized dose verification requirements.

[0037] In some embodiments, in combination with Figure 3 As shown, the phantom insert 201 includes a first housing, a plurality of first sub-phantoms 2011 and a plurality of second sub-phantoms 2012. The first sub-phantom 2011 is arranged in the first housing, and the first sub-phantom 2011 contains a first concentration of boron-10 nuclide. The second sub-phantom 2012 is arranged in the first housing, and the second sub-phantom 2012 contains a second concentration of boron-10 nuclide. Among them, the tumor tissue imitation positioning area 202 is composed of one or more first sub-phantoms 2011, and the normal tissue imitation positioning area 203 is composed of one or more second sub-phantoms 2012.

[0038] With such a setting, the first sub-phantom 2011 contains a higher concentration of boron-10 nuclide and is used to simulate the tumor tissue; the second sub-phantom 2012 contains a lower concentration of boron-10 nuclide and is used to simulate the normal tissue. This design can more realistically measure the difference in boron-10 concentration between the tumor tissue and the normal tissue, so as to more realistically reproduce the moderation process and nuclear reaction probability of the neutron beam in different tissues, and thus accurately measure the dose distribution difference between the tumor target area and the normal tissue. The tumor tissue imitation positioning area 202 is composed of one or more first sub-phantoms 2011, and the normal tissue imitation positioning area 203 is composed of one or more second sub-phantoms 2012. This modular design enables the phantom insert to be flexibly configured according to actual needs, adapt to the tumor position, size and boron-10 distribution of different patients, and meet the personalized dose verification requirements.

[0039] In some embodiments, in combination with Figure 3As shown, the first sub-module 2011 and the second sub-module 2012 are both cube structures, and the tumor-mimicking tissue positioning area 202 is composed of one or more first sub-modules 2011 spliced in a detachable manner, and the normal-tissue-mimicking tissue positioning area 203 is composed of one or more second sub-modules 2012 spliced in a detachable manner.

[0040] With such a setting, the arrangement combination of the first sub-module 2011 and the second sub-module 2012 can be flexibly adjusted according to the shape, size and distribution position of the actual tumor. This design can accurately simulate the tumor morphology of different patients and its spatial relationship with normal tissues, and improve the personalized adaptation ability of dose verification. The sub-modules with a cube structure have a standardized geometric shape, which is convenient for quick splicing and disassembly. Experimenters can easily adjust the combination mode of the tumor-mimicking tissue positioning area 202 and the normal-tissue-mimicking tissue positioning area 203 according to needs, without remanufacturing or customizing the module insert plate, which is conducive to simplifying the experimental operation process and improving the efficiency of dose verification. The sub-modules with a cube structure are easy to mass-produce and replace, reducing the manufacturing cost of the module components. At the same time, the detachable design enables the damage or replacement of a single sub-module not to affect the use of the entire module insert plate 201, reducing the maintenance difficulty and cost.

[0041] In some embodiments, as shown in combination with Figure 4 the dose detection module 4 includes a detector insert plate 401. The detector insert plate 401 is arranged between two adjacent module insert plates 201 and is used to detect the distribution data of secondary particles generated after the nuclear reaction of boron-10 nuclide and neutrons in the plane where the detector insert plate 401 is located. With such a setting, the position of the detector insert plate 401 can be flexibly set according to actual measurement requirements. The corresponding module insert plate 201 can be pulled out and then the detector insert plate 401 can be inserted. The detector insert plate 401 can be inserted into the position of any module insert plate 201 to realize the dose distribution measurement on the section at this position, which is easy to operate.

[0042] In some embodiments, the box body 1 further includes a plurality of card slots arranged along the incident direction of the neutron beam. The module insert plate 201 and the detector insert plate 401 are detachably arranged in the card slots, wherein the sizes of the detector insert plate 401 and the module insert plate 201 match the sizes of the card slots.

[0043] By setting the card slot, it is convenient to install and remove the phantom plug plate 201 and the detector plug plate 401. The experimenter can easily replace or adjust the position of the phantom plug plate 201 and the detector plug plate 401 as needed, which significantly simplifies the experimental operation process and improves the efficiency of dose verification. By matching the size of the detector plug plate 401 and the phantom plug plate 201 with the size of the card slot, it is convenient to flexibly set the arrangement and combination of the detector plug plate 401 and the phantom plug plate 201. For example, the detector plug plate 401 can be inserted at a position close to the tumor tissue to measure the dose distribution of the section, or the phantom plug plate 201 can be inserted at a position far away from the tumor tissue to measure the dose distribution around the tumor tissue, to meet different research needs.

[0044] In some embodiments, the thickness of the slot is in the range of 1.0 cm to 1.4 cm, and the total thickness of the multiple slots is in the range of 25 cm to 35 cm. For example, the thickness of the slot is 1.2 cm, and the total thickness of the multiple slots is 30 cm. The thickness of the slot matches the thickness of the phantom plug board 201, and the phantom plug board 201 can be supported by the slot. By limiting the total thickness of the slot to the above range, the thickness of the human organ can be better simulated.

[0045] In some embodiments, the material of the box body 1 is aluminum alloy, and the wall thickness of the box body 1 is in the range of 1 mm to 2 mm. For example, the wall thickness of the box body 1 is 1 mm. By setting the material of the box body 1 to aluminum alloy, and limiting the thickness of the aluminum alloy to the above range, the impact on the radiation field can be reduced, and a supporting effect can be played.

[0046] In some embodiments, the material of the first shell is aluminum alloy, and the shell thickness of the first shell is in the range of 0.5 mm to 1.5 mm. For example, the shell thickness of the first shell is 1 mm. By setting the material of the first shell to aluminum alloy and limiting the thickness of the aluminum alloy to the above range, the impact on the radiation field can be reduced and a supporting effect can be played.

[0047] In some embodiments, the thickness of the phantom plug plate 201 ranges from 1.0 cm to 1.4 cm. For example, the thickness of the phantom plug plate 201 is 1.2 cm. By limiting the thickness of the phantom plug plate 201 to the above range, the dose distribution characteristics of tumor tissue and normal tissue under the action of the neutron beam can be better simulated, and the installation is convenient for operators.

[0048] In some embodiments, the length and width of the phantom plug plate 201 range from 25 cm to 35 cm. For example, the length and width of the phantom plug plate 201 are both 30 cm. The diameter of the beam outlet is generally within 15 cm. By limiting the length and width of the phantom plug plate 201 to the above range, it is convenient to measure the irradiation dose of normal tissue outside the radiation field.

[0049] In some embodiments, in combination Figure 5 As shown, the detector plug-in board 401 includes a second shell, a PCB board and a plurality of detector arrays 4011. The material of the first shell is aluminum alloy, and the PCB board is arranged in the second shell. The plurality of detector arrays 4011 are arranged on the PCB board, and the size and position of the detector arrays 4011 correspond to the first sub-mold body 2011 and the second sub-mold body 2012 one by one. The size and position of the detector array 4011 are completely matched with the first sub-mold body 2011 and the second sub-mold body 2012, and the dose of each first sub-mold body 2011 and the second sub-mold body 2012 can be obtained, which is conducive to improving the accuracy of dose detection.

[0050] In some embodiments, the tumor tissue-simulating localization area 202 contains a first concentration of boron-10 nuclide, and the normal tissue-simulating localization area 203 contains a second concentration of boron-10 nuclide, the first concentration ranges from 57.5ppm to 127.9ppm, and the second concentration ranges from 20.9ppm to 46.5ppm. Such a setting can better simulate the difference in boron-10 nuclide concentration between tumor tissue and normal tissue, thereby more accurately simulating dose distribution. For example, the first concentration ranges from 80ppm, and the second concentration ranges from 30ppm.

[0051] In BNCT, the total dose generated by the nuclear reaction between the elements in the patient's body and neutrons after the injection of boron-10 is mainly composed of the following four parts: (1) Boron dose: Boron-10 nuclei in the patient's body, especially in the tumor target area, pass through the patient's body and generate neutrons. 10 B(n,α) 7 The α particles produced by Li neutron capture reactions and 7 Li nuclei, which is the main dose that has therapeutic effect on tumor tissue; (2) Nitrogen dose: caused by the distribution of 14 N nuclei pass 14 N(n,p) 14 C reaction produces a recoil 14 C nuclei and protons; (3) Hydrogen dose: distributed in the patient's body 1 H nuclei pass through 1 H(n,n') 1 H and other reactions produce a recoil proton; (4) Gamma dose: the distribution in the patient's body 1 H nuclei pass through 1 H(n,γ) 2The gammas generated by the H reaction and the gammas of the incident radiation field are the main sources of gammas in the patient's body, and these gammas deposit energy through effects such as ionization of cells in the body. Among them, the boron dose is the beneficial dose required for treatment, and the nitrogen dose, hydrogen dose, and gamma dose are harmful doses. In boron neutron capture therapy, it is necessary to increase the beneficial dose and control the harmful dose.

[0052] In some embodiments, the tumor-mimicking tissue localization region 202 and the normal-tissue-mimicking localization region 203 also include the same concentration of nitrogen-14 nuclide and hydrogen-1 nuclide. The detector array 4011 includes one or more of a diamond detector with a boron nitride coating, a diamond detector with a polyethylene coating, and an uncoated diamond detector. The dose includes a boron dose, a nitrogen dose, a hydrogen dose, and a gamma dose.

[0053] In boron neutron capture therapy, the original hydrogen-1 and nitrogen-14 in the human body will also undergo nuclear reactions with neutrons, generating three harmful doses: the nitrogen dose, the hydrogen dose, and the gamma dose. By making the tumor-mimicking tissue localization region 202 and the normal-tissue-mimicking localization region 203 also include the same concentration of nitrogen-14 nuclide and hydrogen-1 nuclide, the situation of the nuclear reactions of nitrogen-14 and hydrogen-1 with neutrons in the human body can be effectively simulated, the nitrogen dose, the hydrogen dose, and the gamma dose can be obtained, enabling the boron neutron capture therapy planning system to make a more accurate treatment plan, increasing the beneficial dose, and controlling the harmful dose.

[0054] The diamond detector with a boron nitride coating can respectively measure the alpha particles generated by the reaction of neutrons with boron-10 and the protons generated by the reaction of neutrons with nitrogen-14. By collecting the measurement results, the boron dose and nitrogen dose at the measured position can be deduced. The diamond detector with a polyethylene coating can measure the protons generated by the reaction of neutrons with hydrogen-1. By the measurement results, the hydrogen dose at the measured position can be deduced. The uncoated diamond detector can measure the gamma energy spectrum generated by the reaction of neutrons with hydrogen-1 and the gamma energy spectrum of the incident radiation field. By the measurement results, the gamma dose at the measured position can be deduced. In this way, the doses of four nuclides can be directly measured, the beneficial dose and harmful dose can be obtained, which is beneficial to further improving the accuracy of the dose verification device.

[0055] In some embodiments, the tumor-mimicking tissue localization region 202 corresponds to the position of the tumor tissue, and the normal-tissue-mimicking localization region 203 corresponds to the position of the normal tissue. Multiple cross-sectional picture models of the patient's tumor tissue and the surrounding normal tissue can be obtained through CT scanning, and then the tumor-mimicking tissue localization region 202 and the normal-tissue-mimicking localization region 203 of each phantom insert 201 can be determined according to the cross-sectional picture models.

[0056] It should be noted that the above preferred embodiments are only used to illustrate the principle of the present application and are not intended to limit the protection scope of the present application. Without departing from the principle of the present application, those skilled in the art can adjust the above settings so that the present application can be applied to more specific application scenarios.

[0057] Those skilled in the art can understand that although some embodiments herein include certain features included in other embodiments rather than other features, the combination of features of different embodiments means that it is within the scope of the present application and forms different embodiments. For example, in the claims of the present application, any one of the claimed embodiments can be used in any combination.

[0058] So far, the technical solutions of the present application have been described in conjunction with the preferred embodiments shown in the accompanying drawings. However, it is easy for those skilled in the art to understand that the protection scope of the present application is obviously not limited to these specific embodiments. Without departing from the principle of the present application, those skilled in the art can make equivalent changes or substitutions to the relevant technical features, and the technical solutions after these changes or substitutions will fall within the protection scope of the present application.

Claims

1. A dose verification device for boron neutron capture therapy, characterized in that: The dose verification device comprises: A box (1) is arranged in a neutron radiation field; A phantom assembly (2), comprising a plurality of phantom inserting plates (201) movably arranged in a box (1), wherein the phantom inserting plates (201) are stacked along the incident direction of the neutron beam; wherein each of the phantom inserting plates (201) comprises a tumor tissue simulating positioning area (202) and / or a normal tissue simulating positioning area (203), and the concentration of boron-10 contained in the tumor tissue simulating positioning area (202) is greater than the concentration of boron-10 contained in the normal tissue simulating positioning area (203); a dose detection module (4), used for detecting distribution data of secondary particles generated after the nuclear reaction between the boron-10 and neutrons in the phantom component (2); and A data processing module (5) is used to obtain the distribution data and determine the dose distribution in the phantom component (2) based on the distribution data.

2. The dose verification device according to claim 1, characterized in that: The phantom insert plate (201) comprises: a first shell; A plurality of first sub-mold bodies (2011) are arranged in the first shell; A plurality of second sub-mold bodies (2012) are arranged in the first shell; The concentration of boron-10 contained in the first sub-phantom (2011) is greater than the second concentration of boron-10 contained in the second sub-phantom (2012); the tumor tissue simulation localization area (202) is composed of one or more of the first sub-phantoms (2011), and the normal tissue simulation localization area (203) is composed of one or more of the second sub-phantoms (2012).

3. The dose verification device according to claim 2, characterized in that: The first sub-phantom (2011) and the second sub-phantom (2012) are both cubic structures, and the simulated tumor tissue positioning area (202) is composed of one or more of the first sub-phantoms (2011) spliced ​​together in a detachable manner, and the simulated normal tissue positioning area (203) is composed of one or more of the second sub-phantoms (2012) spliced ​​together in a detachable manner.

4. The dose verification device according to claim 2, characterized in that: The dosage detection module (4) comprises: The detector plug plate (401) is arranged between two adjacent model plug plates (201) and is used to detect the distribution data of secondary particles generated after the nuclear reaction between the boron-10 and neutrons on the plane where the detector plug plate (401) is located.

5. The dose verification device according to claim 4, characterized in that: The box (1) further comprises a plurality of slots arranged along the incident direction of the neutron beam, the phantom plug-in plate (201) and the detector plug-in plate (401) being detachably arranged in the slots, wherein the dimensions of the detector plug-in plate (401) and the phantom plug-in plate (201) match the dimensions of the slots.

6. The dose verification device according to claim 5, characterized in that: The thickness of the card slot is in the range of 1.0 cm to 1.4 cm, and the total thickness of the plurality of card slots is in the range of 25 cm to 35 cm; and / or, The box body (1) is made of aluminum alloy, and the wall thickness of the box body (1) ranges from 1 mm to 2 mm; and / or, The material of the first shell is aluminum alloy, and the shell thickness of the first shell ranges from 0.5 mm to 1.5 mm; and / or, The thickness of the model plug plate (201) is in the range of 1.0 cm to 1.4 cm; and / or the length and width of the model plug plate (201) are in the range of 25 cm to 35 cm.

7. The dose verification device according to claim 4, characterized in that: The detector plug-in board (401) comprises: a second shell; A PCB board is disposed in the second housing; A plurality of detector arrays (4011) are arranged on the PCB board, and the detector arrays (4011) correspond one-to-one to the sizes and positions of the first sub-mold body (2011) and the second sub-mold body (2012).

8. The dose verification device according to claim 6, characterized in that: The detector array (4011) includes one or more of diamond detectors with boron nitride coating, diamond detectors with polyethylene coating, and uncoated diamond detectors.

9. The dose verification device according to any one of claims 1 to 8, characterized in that: The simulated tumor tissue localization area (202) and the simulated normal tissue localization area (203) further include nitrogen-14 nuclides and hydrogen-1 nuclides at the same concentration, and the dose includes boron dose, nitrogen dose, hydrogen dose and gamma dose.

10. The dose verification device according to any one of claims 1 to 8, characterized in that: The simulated tumor tissue localization area (202) contains a first concentration of boron-10, and the simulated normal tissue localization area (203) contains a second concentration of boron-10, the first concentration ranges from 57.5ppm to 127.9ppm, and the second concentration ranges from 20.9ppm to 46.5ppm; and / or, the simulated tumor tissue localization area (202) corresponds to the position of tumor tissue, and the simulated normal tissue localization area (203) corresponds to the position of normal tissue.

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