CN116271568B - Beam leakage reduction method of radiation field regulation and control system using same - Google Patents

Beam leakage reduction method of radiation field regulation and control system using same Download PDF

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CN116271568B
CN116271568B CN202310065603.9A CN202310065603A CN116271568B CN 116271568 B CN116271568 B CN 116271568B CN 202310065603 A CN202310065603 A CN 202310065603A CN 116271568 B CN116271568 B CN 116271568B
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neutron
gamma
shielding
beam outlet
radiation field
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CN116271568A (en
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请求不公布姓名
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Guozhong Medical Technology Chongqing Co ltd
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Neutron High Tech Industry Development Chongqing Co ltd
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    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/02Dosimeters
    • AHUMAN NECESSITIES
    • A61MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61NELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00Radiation therapy
    • A61N5/10X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N5/1048Monitoring, verifying, controlling systems and methods
    • A61N5/1064Monitoring, verifying, controlling systems and methods for adjusting radiation treatment in response to monitoring
    • A61N5/1065Beam adjustment
    • AHUMAN NECESSITIES
    • A61MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61NELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00Radiation therapy
    • A61N5/10X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N5/1048Monitoring, verifying, controlling systems and methods
    • A61N5/1071Monitoring, verifying, controlling systems and methods for verifying the dose delivered by the treatment plan
    • AHUMAN NECESSITIES
    • A61MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61NELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00Radiation therapy
    • A61N5/10X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N5/1077Beam delivery systems
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F1/00Shielding characterised by the composition of the materials
    • G21F1/12Laminated shielding materials
    • G21F1/125Laminated shielding materials comprising metals
    • AHUMAN NECESSITIES
    • A61MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61NELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00Radiation therapy
    • A61N5/10X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N2005/1085X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy characterised by the type of particles applied to the patient
    • A61N2005/109Neutrons
    • AHUMAN NECESSITIES
    • A61MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61NELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00Radiation therapy
    • A61N5/10X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N2005/1092Details
    • A61N2005/1094Shielding, protecting against radiation
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Health & Medical Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Biomedical Technology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Nuclear Medicine, Radiotherapy & Molecular Imaging (AREA)
  • Veterinary Medicine (AREA)
  • Public Health (AREA)
  • General Health & Medical Sciences (AREA)
  • Animal Behavior & Ethology (AREA)
  • Radiology & Medical Imaging (AREA)
  • Pathology (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Molecular Biology (AREA)
  • General Physics & Mathematics (AREA)
  • Measurement Of Radiation (AREA)

Abstract

The invention relates to the technical field of radiation field regulation and control, in particular to a beam leakage reduction method of a radiation field regulation and control system applying the method, and aims to solve the technical problems that in the prior art, a detection blind area and a control blind area exist in the radiation quantity at a beam outlet in a radiation field application scene. The beam leakage reduction method of the radiation field regulation and control system comprises a control center, a beam outlet, a neutron shielding piece, a gamma shielding piece, a neutron detector and a gamma detector, wherein the neutron shielding piece and the gamma shielding piece are controlled to move by the control center, and the neutron detector and the gamma detector detect and feed back the beam outlet in real time, so that the beam leakage shielding at the beam outlet can be realized under the condition of reducing the volume of equipment, the detection blind area and the control blind area of the radiation quantity at the beam outlet are eliminated, and the application safety of the radiation field is improved.

Description

Beam leakage reduction method of radiation field regulation and control system using same
Technical Field
The invention relates to the technical field of radiation field regulation and control, and particularly provides a beam leakage reduction method of a radiation field regulation and control system using the method.
Background
With the development of people on the microcosmic world, the application of radiation fields to the fields of modern society is gradually increased, such as the technical fields of radiation breeding, radiation therapy and the like, but many problems still exist in the application of the current radiation fields, which need to be solved, wherein the current control means for the radiation quantity in the radiation fields are simpler and coarser, and particularly for neutron beam and gamma radiation, and the prior art also has a very large short plate.
In the prior art, aiming at the problem of beam leakage of neutron beam, a neutron regulation system is often added with a material with a large neutron reflection section and a material with a large neutron absorption section to reduce beam leakage, but the effect of reducing beam leakage is not ideal, and in addition, the volume of the regulation system is increased, so that the cost is greatly increased in the construction process; for gamma radiation, the conventional mode only shields gamma rays through a shielding wall of a treatment room and a shielding door, and no extra shielding measures are provided around the beam outlet, which also causes harm to a certain extent.
Besides, in the prior art, an effective control shielding means is not provided, and a monitoring means is also provided in the running process, so that the fixed neutron and gamma dose equivalent rate meter in the prior art is too large in volume, the application scene is limited, the situation of a beam outlet in the using process is difficult to detect, a certain detection blind area is often provided in the application process of a radiation field, the radiation effect of the application of the radiation field is poor, and even the radiation safety accident risk is caused.
Accordingly, there is a need in the art for a new radiation field detection method and apparatus that addresses the above-described problems.
Disclosure of Invention
The invention aims to solve the technical problems, namely the technical problems of detection blind areas and control blind areas existing in the radiation quantity at the beam outlet in the application scene of the radiation field in the prior art. To this end, the invention provides a beam leakage reduction method of a radiation field regulation system, the radiation field regulation system comprises a beam outlet, the radiation field regulation system further comprises a neutron shielding piece and a gamma shielding piece which are movably arranged on the side face of the beam outlet, a neutron detector is arranged on the neutron shielding piece, a gamma detector is arranged on the gamma shielding piece,
the beam leakage reduction method comprises the following steps:
s100: entering a radiation source into a beam-out preparation stage, and controlling the neutron shielding piece to move to the beam-out opening;
s200: controlling the neutron detector to detect the neutron dose near the beam outlet, judging whether the neutron beam is stable, if so, continuing to run to the end, and finally stopping the beam; if the neutron beam is unstable, immediately stopping the beam;
s300: after stopping the neutron beam, controlling the neutron shielding piece to be opened and controlling the gamma shielding piece to move to the beam outlet;
s400: and controlling the gamma detector to detect the gamma rays of the beam outlet, controlling the gamma shielding piece to be opened if the gamma rays reach a safety threshold, and controlling the gamma shielding piece to continuously shield and shelter if the gamma rays do not reach the safety threshold.
In the specific implementation mode of the beam leakage reduction method with the radiation field regulation and control system, the neutron shielding piece is of a split structure and comprises at least two neutron shielding single elements, a plurality of neutron shielding single elements enclose a beam outlet channel, the splicing ends of the neutron shielding single elements are provided with fixing pieces,
the step S100 specifically includes:
and (3) enabling the radiation source to enter a beam-out preparation stage, controlling a plurality of neutron shielding single elements to be close to the center of the beam-out opening and spliced into the beam-out channel, and enabling adjacent neutron shielding single elements to be mutually jointed through the fixing piece.
In the specific implementation mode of the beam leakage reduction method with the radiation field regulation and control system, the gamma shielding piece is of a split type structure and comprises at least two gamma shielding single elements, a plurality of gamma shielding single elements are spliced to form a plate body and shield the beam outlet, the splicing end of the gamma shielding single elements is provided with a fixing piece,
the step 300 specifically includes:
after the neutron beam is stopped, the neutron shielding piece is controlled to be opened, a plurality of gamma shielding single elements are controlled to be close to the beam outlet and spliced into a plate body for shielding the beam outlet, and adjacent gamma shielding single elements are mutually connected through the fixing piece.
In the specific embodiment of the beam leakage reduction method with the radiation field regulation system, the fixing piece is an electromagnet,
the beam leakage reduction method further comprises the following steps:
in the step 100 or the step 300, the electromagnet is energized when the neutron shielding element or the gamma shielding element is close to each other; when the neutron shielding unit cell or the gamma shielding unit cell is apart from each other, the electromagnet is powered off.
The radiation field regulation and control system comprises a beam outlet, and further comprises a neutron shielding piece and a gamma shielding piece which are movably arranged on the side face of the beam outlet, wherein a neutron detector is arranged on the neutron shielding piece, and a gamma detector is arranged on the gamma shielding piece.
In the specific embodiment with the radiation field regulation and control system, the neutron shielding piece is of a split type structure and comprises at least two neutron shielding single elements, a plurality of neutron shielding single elements enclose a beam outlet channel, the beam outlet channel is used for limiting neutron beam radiation to an area outside the beam outlet, and a fixing piece is arranged at the splicing end of the neutron shielding single elements.
In the specific embodiment with the radiation field regulation and control system, the gamma shielding piece is of a split type structure and comprises at least two gamma shielding single elements, a plurality of gamma shielding single elements are spliced to form a plate body and shield the beam outlet, and the splicing end of the gamma shielding single elements is provided with a fixing piece.
In the specific embodiment with the radiation field regulation system, the fixing piece is an electromagnet; and/or
The neutron detector is positioned on the side face of the beam outlet; and/or
The gamma detector comprises an arc-shaped support and a probe arranged on the inner side of the arc-shaped support, the arc-shaped support is arranged on the gamma shielding piece, and the probe is overlapped with the beam outlet center of the beam outlet.
In the specific embodiment with the radiation field regulation system, the radiation field regulation system further comprises a sliding rail arranged around the beam outlet, and the neutron shielding piece and the gamma shielding piece are both slidably arranged on the sliding rail.
In the specific embodiment with the radiation field regulation system, the gamma shielding piece comprises two layers of steel plates and one layer of lead plate; and/or
The neutron shielding piece comprises a polyethylene layer, a boron-containing polyethylene layer, a lead plate and a steel plate which are arranged in a stacked mode.
Under the condition of adopting the technical scheme, the beam leakage condition of the beam outlet of the radiation field is detected and protected in a targeted manner, so that detection blind areas and control blind areas at the beam outlet in the radiation field in the prior art are eliminated, the whole structure of the equipment is more reasonable in space structure, the occupied volume of the equipment is optimized, and meanwhile, unnecessary beam leakage caused by the lack of control and protection of neutron beam and gamma rays at the beam outlet of the radiation field can be avoided, so that negative effects brought by the radiation field in the application process are caused.
Drawings
Preferred embodiments of the present invention are described below with reference to the accompanying drawings, in which:
FIG. 1 is a schematic diagram of the layout structure at the beam exit of the present invention showing the layout of neutron and gamma shields;
FIG. 2 is a schematic diagram of a neutron shield merge state structure at the beam exit of the invention;
FIG. 3 is a schematic diagram of a combined state structure of gamma shields at the beam outlet of the present invention;
FIG. 4 is a flow chart showing the main steps of the beam leakage reduction method of the present invention;
FIG. 5 is a schematic view of the structure of a gamma shielding unit cell of the present invention, in which the structure of a gamma detector is shown;
in the figure: 1. the beam outlet comprises a beam outlet, 2, a neutron shielding piece, 3, a gamma shielding piece, 4, a neutron detector, 5, a gamma detector, 6, a neutron shielding unit element, 7, a beam outlet channel, 8, a gamma shielding unit element, 9, a fixing piece, 10, an arc-shaped bracket, 11, a probe, 12 and a sliding rail.
Detailed Description
Preferred embodiments of the present invention will be described below with reference to the accompanying drawings in connection with the application of boron neutron capture therapy to this field of radiation. It should be understood by those skilled in the art that these embodiments are merely for explaining the technical principles of the present invention, and are not intended to limit the scope of the present invention. Those skilled in the art can adapt it as desired to suit a particular application. For example, although described in the context of boron neutron capture therapy, this is not limiting and one skilled in the art can apply the present invention to any other field of radiation field application as desired, so long as the field of radiation is required to avoid beam leakage from the radiation exit beam opening.
It should be noted that, in the description of the present invention, terms such as "upper," "lower," "left," "right," "inner," "outer," and the like indicate directional or positional relationships, and are based on the directional or positional relationships shown in the drawings, which are merely for convenience of description, and do not indicate or imply that the relevant devices or elements must have a specific orientation, be constructed and operated in a specific orientation, and thus should not be construed as limiting the invention. Furthermore, the ordinal terms "first," "second," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
Furthermore, it should be noted that, in the description of the present invention, unless explicitly specified and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium. The specific meaning of the above terms in the present invention can be understood by those skilled in the art according to the specific circumstances.
Furthermore, in order to more clearly show the core technical solution of the present invention, descriptions of well-known structures of related devices for boron neutron capture therapy are omitted in the following description, but such omission is merely for convenience of description and does not mean that the related devices for boron neutron capture therapy may have no such structures.
As shown in fig. 1 to 4, the present invention proposes a beam leakage reduction method of a radiation field regulation system, the radiation field regulation system including a beam outlet 1, the radiation field regulation system further including a neutron shielding member 2 and a gamma shielding member 3 movably disposed at a side surface of the beam outlet, a neutron detector 4 being disposed on the neutron shielding member 2, and a gamma detector 5 being disposed on the gamma shielding member 3, the beam leakage reduction method comprising:
s100: the radiation source enters a beam-out preparation stage and controls the neutron shielding piece 2 to move to the beam-out opening 1;
s200: the neutron detector 4 detects neutron dose near the beam outlet 1 and judges whether neutron beam flow is stable or not;
s210: if the neutron beam is stable, continuing to run to the end, and finally stopping the beam;
s220: if the neutron beam is unstable, immediately stopping the beam;
s300: after stopping the neutron beam, controlling the neutron shielding member 2 to be opened and controlling the gamma shielding member 3 to move to the beam outlet 1;
s400: the gamma detector 5 detects gamma rays of the beam outlet 1;
s410: if the gamma rays reach a safety threshold, controlling the gamma shield 3 to open;
s420: if the gamma ray does not reach the safety threshold, the gamma shield 3 continues to shield the shielding.
In this embodiment, in order to eliminate the harm of the leakage beam from the beam outlet 1 as much as possible when the boron neutron capture treatment device is operated, the detection blind area and the control blind area of the beam outlet 1 are reduced in a targeted manner, and further a beam leakage reduction method is provided, and it should be noted that the beam leakage reduction method in this embodiment is described in connection with the boron neutron capture treatment, but this does not affect the protection scope of the present invention, specifically, the boron neutron capture treatment device has a control center and the beam outlet 1, in order to eliminate the detection blind area and the control blind area of the beam outlet 1, a neutron shielding member 2 and a gamma shielding member 3 are installed at the edge of the beam outlet 1, both the above two shielding members are moved at the edge of the beam outlet 1, and in order to control the leakage beam and detect the radiation of the beam outlet 1, a neutron detector 4 and a gamma detector 5 are installed on the neutron shielding member 2 and the gamma shielding member 3 respectively, so that the detector follows the shielding member is moved, and thus the space of the beam outlet 1 is optimally designed.
The beam leakage reduction method of the beam outlet 1 is characterized in that a control center controls a radiation source to enter a beam outlet preparation stage, at the moment, the control center simultaneously sends a moving command to a driving device of the neutron shielding member 2, the neutron shielding member 2 is driven to move to the beam outlet 1, a neutron detector 4 moves to the beam outlet 1 along with the neutron shielding member 2 and enters a detection state, the radiation source enters a working state, the beam outlet 1 radiates towards the direction of the neutron shielding member 2, neutron beams are arranged in radiation flows, the neutron shielding member 2 shields the beam leakage around the beam outlet 1, damage to personnel caused by the beam leakage around the beam outlet 1 during operation of equipment is avoided, a neutron detector 4 detects the neutron beams and feeds back a detection result to the control center, when unstable conditions such as fluctuation occur in the neutron beams, the neutron beam flow timely feeds back to the control center, the control center immediately controls the radiation source to stop the beam, after the beam is stopped, the control center opens the neutron shielding member 2 and simultaneously sends a command to drive the gamma shielding member 3 of the gamma shielding member 3 to move to the beam outlet 1; and when neutron beam operation is stable, neutron detector 4 can not feed back to control center equipment operation to the end, and after stopping the beam at last, control center can open neutron shield 2 simultaneously and close gamma shield 3 equally, and gamma detector 5 on gamma shield 3 can real-time supervision stops the indoor gamma dose of back treatment of beam, if gamma dose reaches safe threshold value, gamma detector 5 can feed back the result to control center, and control center then can open gamma shield 3, otherwise then continue to close gamma shield 3, can real-time accurate realization gamma dose's protection.
Further, as shown in fig. 1, in order to show the structural schematic diagram of the split neutron shielding member 2 and the gamma shielding member 3 at the beam outlet 1, specifically, in this embodiment, the neutron shielding member 2 and the gamma shielding member 3 are both in a two-part split form, that is, two large shielding single elements are provided, but this does not affect the protection scope of the present invention, in practical application, a plurality of parts of single elements can be selected for combination, in this embodiment, two neutron shielding single elements 6 are provided, two gamma shielding single elements 8 are provided, when the beam outlet 1 needs to be shielded by a neutron beam leakage, the control center drives the two neutron shielding single elements 6 to be close to the direction of the beam outlet 1 and spliced into a whole, the two neutron shielding single elements 6 are fixed together by the fixing pieces 9 at the splicing end of the two neutron shielding single elements 6, the fixing pieces 9 are preferably electromagnets, the control center can control the on-off of the electromagnets, and thus flexibly control the combination and separation of the neutron shielding single elements 6, after the neutron shielding single elements 6 are combined, a beam outlet channel 7 can be formed, the radiation shielding single elements are opposite to the beam outlet 1, and the gamma shielding single elements are also split by the gamma shielding single elements 8, and the gamma shielding single elements are split together, and the gamma shielding single elements are preferably split together, and the gamma shielding single elements are split together after the beam outlet 1 is completely and the gamma shielding single elements are split.
Referring to fig. 1 and 3, the neutron shielding member 2 and the gamma shielding member 3 are mounted around the beam outlet 1 by means of the slide rail 12, the slide rail 12 adopts a straight slide rail 12 in this embodiment, and meanwhile adopts a mutually perpendicular structure, but this does not affect the protection scope of the present invention, so long as it is possible to achieve that the neutron shielding member 2 and the gamma shielding member 3 can alternately move near the beam outlet 1 without interference, besides, the neutron detector 4 is mounted in the middle of the neutron shielding member 2, and after the neutron shielding unit 6 is combined, the neutron detector 4 is located at the edge of the beam outlet channel 7 so as to detect the beam leakage condition around the beam outlet 1, while the gamma detector 5 is divided into an arc-shaped bracket 10 and a probe 11, and the arc-shaped bracket 10 protects the probe 11 and related cables inside the arc-shaped bracket, so that the service life and the safety are ensured, and the aesthetic degree is improved, and when the gamma shielding unit 8 is combined, the probe 11 is located on the central axis of the beam outlet 1, the remainder of gamma dosage can be detected more comprehensively.
Furthermore, the neutron shielding member 2 and the gamma shielding member 3 of the invention adopt a layered structure, in the embodiment, the gamma shielding member 3 adopts a lead plate added between two layers of steel plates for shielding gamma rays, the neutron shielding member 2 comprises a polyethylene layer, a boron-containing polyethylene layer, a lead plate and steel plates which are sequentially connected for shielding leakage beams, and the neutron shielding member 2 and the gamma shielding member 3 are not limited in pattern and material sequence as long as the leakage beams and the gamma rays can be reduced.
Thus far, the technical solution of the present invention has been described in connection with the preferred embodiments shown in the drawings, but it is easily understood by those skilled in the art that the scope of protection of the present invention is not limited to these specific embodiments. Equivalent modifications and substitutions for related technical features may be made by those skilled in the art without departing from the principles of the present invention, and such modifications and substitutions will fall within the scope of the present invention.

Claims (8)

1. A beam leakage reduction method of a radiation field regulation system, the radiation field regulation system including a beam outlet (1), characterized in that the radiation field regulation system further includes a neutron shielding member (2) and a gamma shielding member (3) movably disposed at a side surface of the beam outlet (1), a neutron detector (4) is disposed on the neutron shielding member (2), a gamma detector (5) is disposed on the gamma shielding member (3), the beam leakage reduction method includes:
s100: -entering a radiation source into a beam-out preparation phase and controlling the neutron shield (2) to move to the beam-out opening (1);
s200: controlling the neutron detector (4) to detect neutron dose near the beam outlet (1), judging whether neutron beam flow is stable, if so, continuing to run to the end, and finally stopping the beam; if the neutron beam is unstable, immediately stopping the beam;
s300: controlling the neutron shielding piece (2) to be opened and controlling the gamma shielding piece (3) to move to the beam outlet (1) when the neutron beam is stopped;
s400: and controlling the gamma detector (5) to detect the gamma rays of the beam outlet (1), controlling the gamma shielding piece (3) to be opened if the gamma rays reach a safety threshold, and controlling the gamma shielding piece (3) to continuously shield and shelter if the gamma rays do not reach the safety threshold.
2. The beam leakage reduction method of the radiation field regulation system according to claim 1, wherein the neutron shielding member (2) is of a split structure and comprises at least two neutron shielding unit elements (6), a plurality of the neutron shielding unit elements (6) enclose a beam outlet channel (7), a fixing piece (9) is arranged at a splicing end of the neutron shielding unit elements (6), and the step S100 specifically comprises:
the radiation source enters a beam-out preparation stage, a plurality of neutron shielding single elements (6) are controlled to be close to the center of the beam-out opening (1) and spliced into the beam-out channel (7), and the adjacent neutron shielding single elements (6) are mutually jointed through the fixing piece (9).
3. The beam leakage reduction method of the radiation field regulation system according to claim 1, wherein the gamma shielding member (3) is of a split structure and comprises at least two gamma shielding unit elements (8), a plurality of the gamma shielding unit elements (8) are spliced to form a plate body and shield the beam outlet (1), and a fixing member (9) is arranged at the splicing end of the gamma shielding unit elements (8), and the step 300 specifically comprises:
after the neutron beam is stopped, the neutron shielding piece (2) is controlled to be opened, a plurality of gamma shielding single elements (8) are controlled to be close to the beam outlet (1) and spliced into a plate body for shielding the beam outlet (1), and the adjacent gamma shielding single elements (8) are mutually connected through the fixing piece (9).
4. A beam leakage reduction method of a radiation field regulation system according to claim 2 or 3, wherein the fixture (9) is an electromagnet, the beam leakage reduction method further comprising:
in the step 100 or the step 300, when the neutron shielding unit (6) or the gamma shielding unit (8) is close to each other, the electromagnet is energized; when the neutron shielding unit (6) or the gamma shielding unit (8) is far away from each other, the electromagnet is powered off.
5. The radiation field regulation and control system comprises a beam outlet (1), and is characterized by further comprising a neutron shielding piece (2) and a gamma shielding piece (3) which are movably arranged on the side face of the beam outlet (1), wherein a neutron detector (4) is arranged on the neutron shielding piece (2), and a gamma detector (5) is arranged on the gamma shielding piece (3);
the neutron shielding piece (2) is of a split structure and comprises at least two neutron shielding single elements (6), a plurality of neutron shielding single elements (6) are surrounded to form a beam outlet channel (7), the beam outlet channel (7) is used for limiting neutron beam radiation to an area outside the beam outlet (1), and a fixing piece (9) is arranged at the splicing end of the neutron shielding single elements (6);
the gamma shielding piece (3) is of a split type structure and comprises at least two gamma shielding single elements (8), a plurality of gamma shielding single elements (8) are spliced to form a plate body and shield the beam outlet (1), and a fixing piece (9) is arranged at the splicing end of each gamma shielding single element (8).
6. The radiation field control system according to claim 5, characterized in that the fixing element (9) is an electromagnet; and/or
The neutron detector (4) is positioned on the side face of the beam outlet (1); and/or
The gamma detector (5) comprises an arc-shaped support (10) and a probe (11) arranged on the inner side of the arc-shaped support (10), the arc-shaped support (10) is arranged on the gamma shielding piece (3), and the probe (11) is overlapped with the beam outlet center of the beam outlet (1).
7. The radiation field control system according to claim 5, further comprising a sliding rail (12) arranged around the beam outlet (1), wherein the neutron shield (2) and the gamma shield (3) are both slidably arranged on the sliding rail (12).
8. The radiation field control system according to claim 5, characterized in that the gamma shield (3) comprises two layers of steel plates and one layer of lead plate; and/or
The neutron shielding piece (2) comprises a polyethylene layer, a boron-containing polyethylene layer, a lead plate and a steel plate which are arranged in a laminated mode.
CN202310065603.9A 2023-01-13 2023-01-13 Beam leakage reduction method of radiation field regulation and control system using same Active CN116271568B (en)

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Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2007242422A (en) * 2006-03-08 2007-09-20 Mitsubishi Heavy Ind Ltd Neutron generator and neutron irradiation system
JP2017042311A (en) * 2015-08-25 2017-03-02 住友重機械工業株式会社 Neutron capture therapy system and control method for neutron capture therapy system
EP3381514A1 (en) * 2017-03-29 2018-10-03 Sumitomo Heavy Industries, Ltd. Neutron capture therapy system and gamma ray detector for neutron capture therapy
CN110650777A (en) * 2017-05-16 2020-01-03 住友重机械工业株式会社 Neutron capture therapy system
CN110785820A (en) * 2017-06-23 2020-02-11 澳洲快索有限公司 X-ray radiation shielding device
CN110967727A (en) * 2019-12-09 2020-04-07 中国原子能科学研究院 Gamma energy spectrometer for boron neutron capture treatment irradiation beam
KR20200052099A (en) * 2018-11-06 2020-05-14 한국원자력의학원 Collimator for Neutron Capture Therapy System
CN212434267U (en) * 2020-02-04 2021-01-29 中国海洋石油集团有限公司 Radioactive source bank
CN212694850U (en) * 2020-08-10 2021-03-12 东营荟萃石油科技有限公司 Novel probe tube type azimuth gamma shielding structure
CN214897649U (en) * 2021-04-02 2021-11-26 北京普达迪泰科技有限公司 Radiation-resistant camera mechanism for neutron and gamma radiation environment
CN115499993A (en) * 2022-10-21 2022-12-20 中子高新技术产业发展(重庆)有限公司 Neutron target system

Patent Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2007242422A (en) * 2006-03-08 2007-09-20 Mitsubishi Heavy Ind Ltd Neutron generator and neutron irradiation system
JP2017042311A (en) * 2015-08-25 2017-03-02 住友重機械工業株式会社 Neutron capture therapy system and control method for neutron capture therapy system
EP3381514A1 (en) * 2017-03-29 2018-10-03 Sumitomo Heavy Industries, Ltd. Neutron capture therapy system and gamma ray detector for neutron capture therapy
CN110650777A (en) * 2017-05-16 2020-01-03 住友重机械工业株式会社 Neutron capture therapy system
CN110785820A (en) * 2017-06-23 2020-02-11 澳洲快索有限公司 X-ray radiation shielding device
KR20200052099A (en) * 2018-11-06 2020-05-14 한국원자력의학원 Collimator for Neutron Capture Therapy System
CN110967727A (en) * 2019-12-09 2020-04-07 中国原子能科学研究院 Gamma energy spectrometer for boron neutron capture treatment irradiation beam
CN212434267U (en) * 2020-02-04 2021-01-29 中国海洋石油集团有限公司 Radioactive source bank
CN212694850U (en) * 2020-08-10 2021-03-12 东营荟萃石油科技有限公司 Novel probe tube type azimuth gamma shielding structure
CN214897649U (en) * 2021-04-02 2021-11-26 北京普达迪泰科技有限公司 Radiation-resistant camera mechanism for neutron and gamma radiation environment
CN115499993A (en) * 2022-10-21 2022-12-20 中子高新技术产业发展(重庆)有限公司 Neutron target system

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
无均整器型加速器治疗室中子剂量分布;李定杰;邓小武;程晓军;薛莹;张有改;郭伟;王建华;;中华肿瘤防治杂志(17);全文 *

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