CN113917518A - Device for measuring spatial distribution of different radiation components of irradiation beam for boron neutron capture treatment - Google Patents
Device for measuring spatial distribution of different radiation components of irradiation beam for boron neutron capture treatment Download PDFInfo
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- CN113917518A CN113917518A CN202111097752.0A CN202111097752A CN113917518A CN 113917518 A CN113917518 A CN 113917518A CN 202111097752 A CN202111097752 A CN 202111097752A CN 113917518 A CN113917518 A CN 113917518A
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- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 title claims abstract description 38
- 229910052796 boron Inorganic materials 0.000 title claims abstract description 38
- 230000005855 radiation Effects 0.000 title claims abstract description 35
- 238000001514 detection method Methods 0.000 claims abstract description 24
- 238000005259 measurement Methods 0.000 claims abstract description 22
- 230000005251 gamma ray Effects 0.000 claims abstract description 8
- 238000004980 dosimetry Methods 0.000 claims abstract description 4
- 239000002245 particle Substances 0.000 claims description 17
- 229910003460 diamond Inorganic materials 0.000 claims description 15
- 239000010432 diamond Substances 0.000 claims description 15
- 238000002560 therapeutic procedure Methods 0.000 claims description 11
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 10
- 229910052782 aluminium Inorganic materials 0.000 claims description 10
- 239000000758 substrate Substances 0.000 claims description 8
- 239000000463 material Substances 0.000 claims description 7
- 229910052793 cadmium Inorganic materials 0.000 claims description 6
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 claims description 6
- 239000004698 Polyethylene Substances 0.000 claims description 4
- -1 polyethylene Polymers 0.000 claims description 4
- 229920000573 polyethylene Polymers 0.000 claims description 4
- 239000000919 ceramic Substances 0.000 claims description 3
- 239000013078 crystal Substances 0.000 claims description 3
- 238000001704 evaporation Methods 0.000 claims description 3
- 239000004065 semiconductor Substances 0.000 claims description 3
- 230000008020 evaporation Effects 0.000 claims description 2
- 238000000034 method Methods 0.000 description 9
- 238000006243 chemical reaction Methods 0.000 description 4
- 206010028980 Neoplasm Diseases 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 238000001228 spectrum Methods 0.000 description 3
- 230000004888 barrier function Effects 0.000 description 2
- 239000003814 drug Substances 0.000 description 2
- 229940079593 drug Drugs 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000003384 imaging method Methods 0.000 description 2
- 210000004881 tumor cell Anatomy 0.000 description 2
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 1
- 229910052688 Gadolinium Inorganic materials 0.000 description 1
- 206010063385 Intellectualisation Diseases 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000008280 blood Substances 0.000 description 1
- 210000004369 blood Anatomy 0.000 description 1
- 210000004027 cell Anatomy 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 description 1
- PCHJSUWPFVWCPO-UHFFFAOYSA-N gold Chemical compound [Au] PCHJSUWPFVWCPO-UHFFFAOYSA-N 0.000 description 1
- 238000000691 measurement method Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000001959 radiotherapy Methods 0.000 description 1
- 230000001225 therapeutic effect Effects 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/29—Measurement performed on radiation beams, e.g. position or section of the beam; Measurement of spatial distribution of radiation
- G01T1/2914—Measurement of spatial distribution of radiation
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- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
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- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Abstract
The invention relates to a device for measuring the spatial distribution of different radiation components of a boron neutron capture treatment irradiation beam, belonging to the technical field of boron neutron capture treatment equipment, wherein the device comprises a detection unit, a two-dimensional mobile platform and an electronics system; the detection unit comprises a thermal neutron detector, an epithermal neutron detector, a fast neutron detector and a gamma-ray detector which are respectively used for detecting different radiation components in the beam; the detection unit is arranged on the two-dimensional moving platform, and the two-dimensional moving platform is controlled to move according to a preset program through upper computer software, so that automatic measurement is realized; the electronics system comprises a front-end module, a high-voltage power supply module and a multi-channel data acquisition module, and is connected with the detection unit to realize the physical dosimetry measurement of boron neutron capture treatment. The device provided by the invention not only has enough spatial resolution capability, but also can work in a strong neutron field, can effectively identify neutrons/gamma in different energy regions, and also has a one-button automatic measurement completion function.
Description
Technical Field
The invention belongs to the technical field of boron neutron capture treatment equipment, and particularly relates to a device for measuring the spatial distribution of different radiation components of a boron neutron capture treatment irradiation beam.
Background
Boron Neutron Capture Therapy (BNCT) is a binary targeted radiotherapy, in which a boron-carrying agent drug that is tumor cell-philic is injected into the blood of a patient, the boron-containing drug is metabolized to aggregate in tumor cells, and then reused10B capturing low-energy neutrons (thermal or epithermal neutrons-thermal neutron beam for treating superficial tumor and epithermal neutron beam for treating deep tumor) with large reaction section to irradiate the focal region to generate alpha particles with high energy linear density (LET) and7the combined range of the Li nucleus and the Li nucleus in the tissue is about 12-13 mu m, and the combined range is equivalent to the size of one cell, so that the tumor cells are killed selectively, and the effect of precise treatment is achieved. Depending on the generation of the radiation beam and the treatment requirements, BNCT radiation beams have the following characteristics: 1) the energy range is wide (neutron: thermal energy is about 10MeV, and thermal neutrons or epithermal neutrons are used as main components; γ: tens of keV to about 10 MeV); 2) the radiation intensity is high (neutron fluence rate: about 109cm-2s-1(ii) a Gamma fluence rate: about 107cm-2s-1(ii) a 3) A diverging beam, typically conically collimated, may be accompanied by a strong room scattering background (caused by treatment room wall and ceiling and floor scattering).
BNCT requires measurement of spatial distribution of different radiation components (thermal neutrons, epithermal neutrons, fast neutrons, gamma rays) in the treatment beam, and the current measurement methods mainly include the following three types: 1) imaging methods, such as: gadolinium screens (thermal neutron sensitive), radioactive chromium dose films (gamma ray sensitive), etc.; 2) spotting, i.e. detectors (e.g.: gold foil, thermoluminescent detector-TLD) dispensing; 3) scanning, i.e. the way in which the detector scans the beam. The difficulty of measurement is that: 1) how to effectively discriminate different radiation components and have enough spatial resolution capability; 2) the measuring device can work normally in a high intensity radiation field. The imaging method is a passive method, the measuring process is simple and quick, the spatial resolution is high, neutrons and gamma rays can be effectively discriminated by adopting a proper method, but the required data reading equipment is expensive, the reading process is complicated, and fast neutrons are difficult to effectively discriminate; the point distribution method generally adopts a passive detector, can obtain good spatial resolution, can effectively discriminate neutrons and gamma rays by adopting a proper method, but is difficult to effectively discriminate fast neutrons, and has a complex and long data acquisition process; the scanning method generally adopts an active detector, can obtain good spatial resolution, can realize effective discrimination of different neutron components by adopting a proper method, is easy to realize intellectualization, can work in a strong neutron/gamma mixed field by selecting a proper detector, and can discriminate neutrons and gamma rays in different energy regions.
Disclosure of Invention
In order to solve the defects in the prior art, the invention aims to provide a device for measuring the spatial distribution of different radiation components of a boron neutron capture treatment irradiation beam, which not only has enough spatial resolution capability, but also can work in a strong neutron field, can effectively identify neutrons/gamma in different energy regions, and has a function of automatically completing measurement in a one-key manner.
In order to achieve the above purposes, the invention adopts a technical scheme that:
a device for measuring the spatial distribution of different radiation components of a boron neutron capture treatment irradiation beam comprises a detection unit, a two-dimensional mobile platform and an electronics system;
the detection unit comprises a thermal neutron detector, an epithermal neutron detector, a fast neutron detector and a gamma ray detector, and is respectively used for detecting four radiation components of thermal neutrons, epithermal neutrons, fast neutrons and gamma rays in the boron neutron capture treatment irradiation beam;
the detection unit is arranged on the two-dimensional moving platform, and the two-dimensional moving platform is controlled to move according to a preset program through upper computer software, so that automatic measurement is realized;
the electronics system comprises a front-end module, a high-voltage power supply module and a multi-channel data acquisition module, and is connected with the detection unit to realize boron neutron capture therapy physical dosimetry measurement.
Further, according to the apparatus for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture therapy as described above, each of the thermal neutron detector, the epithermal neutron detector and the fast neutron detector includes a detector, a neutron-charged particle converter for converting neutrons into detectable charged particles, and a limiting diaphragm disposed between the detector and the neutron-charged particle converter, and is integrally packaged in an aluminum shell.
Still further, according to the device for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture therapy, the surface of the detector is provided with a ceramic substrate package, and the surface of the neutron-charged particle converter is provided with a high-purity aluminum substrate.
Further, the apparatus for measuring the spatial distribution of different radiation components of a boron neutron capture therapeutic irradiation beam as described above, the limiting diaphragm being used to control the counting rate of the detector to avoid overloading the electronics system.
Further, according to the device for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture treatment, the structure of the gamma ray detector is a bare diamond detector.
Further, according to the device for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture therapy, the detector is made of high-purity single-crystal diamond semiconductor materials, and the sensitive area is 3.6mm by 3.6 mm.
Further, according to the device for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture treatment, the neutron-charged particle converter materials of the thermal neutron detector and the epithermal neutron detector are prepared by evaporation method6A LiF film.
Further, according to the device for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture treatment, the outer surface of the epithermal neutron detector is covered with a layer of cadmium with the thickness of 1mm, and the cadmium is arranged on the outer side surface of the aluminum shell and the front end surface of the high-purity aluminum substrate.
Further, according to the apparatus for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture therapy, the neutron-charged particle converter material of the fast neutron detector is a polyethylene film.
Further, according to the device for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture treatment, the moving precision of the two-dimensional moving platform is less than 0.1 mm.
The device for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture treatment provided by the invention has the following remarkable technical effects:
1) because the BNCT irradiation beam is a neutron/gamma mixed field with wide energy and high intensity, the detection efficiency is reduced by adding a small amount of conversion bodies, adding light barriers and an air layer, the counting rate of the detector is controlled to reach an acceptable level (an electronic system is not overloaded), the measurement of a neutron energy spectrum under a high neutron fluence rate (under the intensity of treatment beam current) can be realized, and meanwhile, the detection system is in an active mode, can give instantaneous pulse signals, and realizes on-line rapid measurement;
2) the sensitive area of the diamond detector is 3.6mm by 3.6mm, and the spatial distribution measurement with the resolution less than 5mm can be realized;
3) the measuring time of each measuring point is predicted to be 10 seconds, and each measuring time can be shortened to be within 10 minutes according to the size of an irradiation beam outlet.
Drawings
FIG. 1 is a block diagram of an apparatus for measuring spatial distribution of different radiation components of an irradiation beam for boron neutron capture therapy provided in an embodiment of the present invention;
FIG. 2 is a schematic diagram of a thermal neutron detector in the apparatus of FIG. 1;
fig. 3 is a graph of the spatial distribution measurements of the apparatus of fig. 1.
Detailed Description
The invention is further described with reference to specific embodiments and drawings attached to the description.
Fig. 1 shows a block diagram of the structure of the device for measuring the spatial distribution of different radiation components of a boron neutron capture treatment irradiation beam, which comprises a detection unit 1, a two-dimensional moving platform 2 and an electronic system 3.
The detection unit 1 is the core of the whole measuring device and is used for measuring the spatial distribution of different radiation components in the boron neutron capture treatment irradiation beam. The boron neutron capture treatment irradiation beam comprises four radiation components of thermal neutrons, epithermal neutrons, fast neutrons and gamma rays, so the detection unit 1 correspondingly comprises a thermal neutron detector 11, an epithermal neutron detector 12, a fast neutron detector 13 and a gamma ray detector 14.
Wherein the thermal neutron detector 11 adopts a belt6The diamond detector of the LiF film converter measures the spatial distribution of thermal neutrons in a boron neutron capture treatment irradiation beam, the structure of the diamond detector is shown in figure 2, the thermal neutron detector is composed of a detector 111 and a neutron-charged particle converter 112, a limiting diaphragm is arranged between the detector 111 and the neutron-charged particle converter 112, and the whole diamond detector is packaged in an aluminum shell 113.
In this embodiment, the detector 111 is made of a high-purity single-crystal diamond semiconductor material and is packaged by a ceramic substrate 114. The diamond detector has the advantages that the sensitive area is 3.6mm by 3.6mm, the energy resolution is high, the detection efficiency is low, and the spatial distribution measurement with the resolution smaller than 5mm can be realized.
The neutron-charged particle converter 112 is prepared by evaporation6The LiF film, protected by a high purity aluminum substrate 115 on the outside, is used to convert neutrons into detectable charged particles.
The limiting diaphragm is used to control the count rate of the detector to an acceptable level (the electronics system is not overloaded).
The thermal neutron detector 11 can reduce the detection efficiency to control the counting rate of the detector to reach an acceptable level, so that the detector can normally work in a strong neutron and gamma mixed field; the measurement of neutron energy spectrum under high neutron fluence rate (under the intensity of treatment beam current) can be realized; meanwhile, the detection system is in an active mode, and can give out instantaneous pulse signals to realize online rapid measurement.
The epithermal neutron detector 12 uses cadmium-coated tape6The diamond detector of the LiF film converter measures epithermal neutrons in the boron neutron capture treatment irradiation beam. The structure of the detector is basically the same as that of a thermal neutron detector, and the difference is that: and a layer of cadmium with the thickness of 1mm is covered on the outer side surface and the front end surface of the thermal neutron detector and is used for absorbing thermal neutrons.
The fast neutron detector 13 measures fast neutrons in the boron neutron capture treatment irradiation beam by adopting a diamond detector with a polyethylene film conversion body, and completes the detection of the neutrons by recording the recoil protons. The structure of the detector is basically the same as that of a thermal neutron detector, and the difference is that: will be provided with6The LiF film is replaced by a polyethylene film.
The gamma ray detector 14 measures gamma rays using a bare diamond detector. Because the diamond is sensitive to gamma rays, the diamond can be directly used for detecting the gamma rays.
The two-dimensional moving platform 2 can move along an X axis and a Y axis and is controlled by self-grinding upper computer software, and the moving precision is less than 0.1 mm. The two-dimensional mobile platform is used for carrying the detection unit 1 to move according to a preset program, and automatic measurement is achieved.
The electronic system 3 comprises a front-end module, a high-voltage power supply module and a multi-channel data acquisition module, is manufactured into a standard edition card and is placed in a PXIe cabinet, and can meet the measurement requirement of BNCT physical dosimetry.
The device for measuring the spatial distribution of different radiation components of the irradiation beam for boron neutron capture treatment provided by the invention has the following beneficial effects:
1) because the BNCT irradiation beam is a neutron/gamma mixed field with wide energy and high intensity, the detection efficiency is reduced by adding a small amount of conversion bodies, adding light barriers and an air layer, the counting rate of the detector is controlled to reach an acceptable level (an electronic system is not overloaded), the measurement of a neutron energy spectrum under a high neutron fluence rate (under the intensity of treatment beam current) can be realized, and meanwhile, the detection system is in an active mode, can give instantaneous pulse signals, and realizes on-line rapid measurement;
2) the sensitive area of the diamond detector is 3.6mm by 3.6mm, and the spatial distribution measurement with the resolution less than 5mm can be realized;
3) the measuring time of each measuring point is predicted to be 10 seconds, and each measuring time can be shortened to be within 10 minutes according to the size of an irradiation beam outlet.
The above-described embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (10)
1. A device for measuring the spatial distribution of different radiation components of a boron neutron capture treatment irradiation beam is characterized by comprising a detection unit, a two-dimensional moving platform and an electronic system;
the detection unit comprises a thermal neutron detector, an epithermal neutron detector, a fast neutron detector and a gamma ray detector, and is respectively used for detecting four radiation components of thermal neutrons, epithermal neutrons, fast neutrons and gamma rays in the boron neutron capture treatment irradiation beam;
the detection unit is arranged on the two-dimensional moving platform, and the two-dimensional moving platform is controlled to move according to a preset program through upper computer software, so that automatic measurement is realized;
the electronics system comprises a front-end module, a high-voltage power supply module and a multi-channel data acquisition module, and is connected with the detection unit to realize boron neutron capture therapy physical dosimetry measurement.
2. The apparatus of claim 1, wherein the thermal neutron detector, the epithermal neutron detector, and the fast neutron detector each comprise a detector, a neutron-to-charged particle converter for converting neutrons into detectable charged particles, and a limiting diaphragm disposed between the detector and the neutron-to-charged particle converter, and are integrally encapsulated in an aluminum housing.
3. The apparatus according to claim 2, wherein the detector surfaces of the thermal neutron detector, the epithermal neutron detector and the fast neutron detector are provided with ceramic substrate packages, and the neutron-charged particle converter surface is provided with a high-purity aluminum substrate.
4. An apparatus for measuring the spatial distribution of different radiation components of a boron neutron capture treatment irradiation beam according to claim 3, wherein the limiting diaphragm is used to control the count rate of the detector to avoid overloading the electronics system.
5. The apparatus for measuring the spatial distribution of different radiation components of an irradiation beam for boron neutron capture therapy according to claim 2, wherein the structure of the gamma ray detector comprises only the detector.
6. The apparatus for measuring the spatial distribution of different radiation components of an irradiation beam for boron neutron capture therapy according to any of claims 2 to 5, wherein the detector is made of high purity single crystal diamond semiconductor material and has a sensitive area of 3.6mm by 3.6 mm.
7. The apparatus according to claim 6, wherein the neutron-charged particle converter material of the thermal neutron detector and the epithermal neutron detector is prepared by evaporation6A LiF film.
8. The apparatus of claim 7, wherein the outer surface of the epithermal neutron detector is further covered with a layer of 1mm thick cadmium, the cadmium being disposed on the outer side of the aluminum shell and the front surface of the high purity aluminum substrate.
9. The apparatus according to claim 6, wherein the neutron-charged particle converter material of the fast neutron detector is a polyethylene film.
10. The apparatus for measuring the spatial distribution of different radiation components of a boron neutron capture therapy irradiation beam of claim 1, wherein the precision of the movement of the two-dimensional moving platform is less than 0.1 mm.
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| CN202111097752.0A CN113917518A (en) | 2021-09-18 | 2021-09-18 | Device for measuring spatial distribution of different radiation components of irradiation beam for boron neutron capture treatment |
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| CN202111097752.0A CN113917518A (en) | 2021-09-18 | 2021-09-18 | Device for measuring spatial distribution of different radiation components of irradiation beam for boron neutron capture treatment |
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Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
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| CN108806818A (en) * | 2018-04-17 | 2018-11-13 | 东莞理工学院 | A kind of four knife diaphragms of adjustable neutron flow |
| CN109799527A (en) * | 2019-03-11 | 2019-05-24 | 北京大学 | A kind of neutron spectrum measurement device and bonner sphere spectrometer system |
| CN113188652A (en) * | 2021-04-21 | 2021-07-30 | 西北工业大学 | Method and device for measuring acoustic radiation force in suspension sound field |
-
2021
- 2021-09-18 CN CN202111097752.0A patent/CN113917518A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105022084A (en) * | 2015-08-20 | 2015-11-04 | 中国原子能科学研究院 | Digital neutron spectrometer |
| CN108538421A (en) * | 2018-04-17 | 2018-09-14 | 东莞理工学院 | A kind of diaphragm of rotating disc type |
| CN108806818A (en) * | 2018-04-17 | 2018-11-13 | 东莞理工学院 | A kind of four knife diaphragms of adjustable neutron flow |
| CN108682717A (en) * | 2018-06-07 | 2018-10-19 | 哈尔滨工业大学 | A kind of preparation method of diamond position sensitive detector |
| CN109799527A (en) * | 2019-03-11 | 2019-05-24 | 北京大学 | A kind of neutron spectrum measurement device and bonner sphere spectrometer system |
| CN113188652A (en) * | 2021-04-21 | 2021-07-30 | 西北工业大学 | Method and device for measuring acoustic radiation force in suspension sound field |
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| Title |
|---|
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