CN110870950A - Neutron capture therapy system - Google Patents
Neutron capture therapy system Download PDFInfo
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- CN110870950A CN110870950A CN201811276920.0A CN201811276920A CN110870950A CN 110870950 A CN110870950 A CN 110870950A CN 201811276920 A CN201811276920 A CN 201811276920A CN 110870950 A CN110870950 A CN 110870950A
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Images
Classifications
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/1048—Monitoring, verifying, controlling systems and methods
-
- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/1048—Monitoring, verifying, controlling systems and methods
- A61N5/1064—Monitoring, verifying, controlling systems and methods for adjusting radiation treatment in response to monitoring
- A61N5/1065—Beam adjustment
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N2005/1085—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy characterised by the type of particles applied to the patient
- A61N2005/109—Neutrons
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N2005/1092—Details
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N2005/1092—Details
- A61N2005/1094—Shielding, protecting against radiation
Abstract
The invention provides a neutron capture treatment system, which comprises a neutron generating device and a beam shaping body, and further comprises a concrete wall which accommodates the neutron generating device and the beam shaping body and shields radiation generated by the neutron generating device and the beam shaping body, wherein a reinforcing part for supporting the beam shaping body is arranged in the concrete wall, and the material of the reinforcing part is more than 90% (weight percentage) composed of at least one element of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S and Ca. According to the neutron capture treatment system, the reinforced part arranged in the concrete wall has good anti-activation performance, and compared with a traditional reinforced concrete structure, the radiation is further attenuated.
Description
Technical Field
The invention relates to a radiation irradiation system, in particular to a neutron capture treatment system.
Background
With the development of atomic science, radiation therapy such as cobalt sixty, linacs, electron beams, etc. has become one of the main means of cancer treatment. However, the traditional photon or electron therapy is limited by the physical conditions of the radiation, and can kill tumor cells and damage a large amount of normal tissues in the beam path; in addition, due to the difference in the sensitivity of tumor cells to radiation, conventional radiotherapy is often ineffective in treating malignant tumors with relatively high radiation resistance, such as multiple glioblastoma multiforme (glioblastoma multiforme) and melanoma (melanoma).
In order to reduce the radiation damage of normal tissues around tumor, the target therapy concept in chemotherapy (chemotherapy) is applied to radiotherapy; for tumor cells with high radiation resistance, radiation sources with high Relative Biological Effect (RBE) are also actively developed, such as proton therapy, heavy particle therapy, neutron capture therapy, etc. Wherein, the neutron capture treatment combines the two concepts, such as boron neutron capture treatment, and provides better cancer treatment selection than the traditional radioactive rays by the specific accumulation of boron-containing drugs in tumor cells and the precise neutron beam regulation.
Various radioactive rays are generated in the radiation therapy process, for example, the boron neutron capture therapy process generates neutrons and photons with low energy and high energy, and the radioactive rays can cause damage to normal tissues of a human body to different degrees. Therefore, in the field of radiation therapy, it is an extremely important issue to reduce radiation contamination to the external environment, medical staff, or normal tissues of the irradiated body while achieving effective treatment. The radiotherapy equipment is usually placed in a concrete-constructed building, the radiation possibly generated by the isolation equipment, and the general reinforced concrete structure can generate radioactive isotopes with longer half-life after the reinforcing steel is activated by neutrons, such as cobalt 60 with the half-life of 5.27 years, so that radioactive wastes with long decay time are formed, and the environment and the radiation safety are negatively influenced.
Therefore, a new technical solution is needed to solve the above problems.
Disclosure of Invention
In order to solve the above problems, the present invention provides a neutron capture treatment system, including a neutron generating device and a beam shaper, wherein the neutron generating device includes an accelerator and a target, the charged particle beam generated by acceleration of the accelerator acts on the target to generate neutron rays, the beam shaper includes a reflector, a retarder, a thermal neutron absorber, a radiation shield, and a beam outlet, the retarder decelerates neutrons generated from the target to a super-thermal neutron energy region, the reflector surrounds the retarder and guides off-neutrons back to the retarder to increase the intensity of the super-thermal neutron beam, the thermal neutron absorber absorbs thermal neutrons to avoid excessive dose with normal tissue of a shallow layer during treatment, the radiation shield is disposed around the beam outlet at the rear of the reflector to shield the leaked neutrons and photons to reduce the normal tissue dose of a non-irradiation region, the neutron capture therapy system further comprises a concrete wall accommodating the neutron generating device and the beam shaping body, wherein a reinforcing part for supporting the beam shaping body is arranged in the concrete wall, and the material of the reinforcing part is more than 90% (weight percentage) composed of at least one element of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S and Ca. The concrete structure can shield neutrons and other radiation rays leaked in the working process of the neutron capture treatment system, the reinforcing part can increase the rigidity of the concrete, the tensile strength is improved, the bearing capacity is improved, the material of the reinforcing part is composed of elements which have small cross sections with the action of the neutrons or have short half-life of radioactive isotopes generated after being activated by the neutrons, and the radioactivity derived from the neutron activation is small, so that the dosage caused by secondary radiation is reasonably inhibited, and the future equipment dismantling is facilitated.
Further, the elastic modulus of the material of the reinforcing part is not lower than 40GPa, the yield strength is not lower than 200MPa, and the ultimate strength is not lower than 100 MPa.
Further, the half-life of the radioisotope produced after activation of the enhancement by neutrons is less than 1 year.
Further, the material of the reinforcing part is at least partially aluminum alloy or carbon fiber composite or glass fiber composite. The half-life of the aluminum after being activated by neutrons is shorter, the carbon fiber composite material or the glass fiber composite material has good activation resistance, and the radioactivity derived from the neutron activation is greatly reduced in a limited time compared with the traditional reinforced concrete structure.
The neutron capture treatment system further comprises a treatment table and a collimator, the collimator is arranged behind the beam outlet to converge neutron lines, the neutron lines generated by the neutron generating device irradiate an irradiated body on the treatment table through the beam shaping body and the collimator, and a radiation shielding device is arranged between the irradiated body and the beam outlet to shield the irradiation of the beams coming out of the beam outlet to normal tissues of the irradiated body. The target material can have one or more, the charged particle beam can selectively act with one or more target materials or simultaneously act with a plurality of target materials to generate one or more neutron beams for treatment, and the number of the beam shaping body, the collimator and the treatment table can also be one or more corresponding to the number of the target materials.
Further, the neutron capture treatment system further includes a charged particle beam generation chamber in which an irradiated body on the treatment table is subjected to a treatment by neutron irradiation, and an irradiation chamber in which the accelerator is accommodated, the concrete wall includes a partition wall between the charged particle beam generation chamber and the irradiation chamber, and the beam shaping body is disposed in and supported by the partition wall. The partition wall may completely separate the irradiation chamber and the charged particle beam generation chamber; the irradiation chamber and the charged particle beam generation chamber may be partially isolated from each other, and the irradiation chamber and the charged particle beam generation chamber may be communicated with each other. The treatment tables can be arranged in the same irradiation chamber, or a separate irradiation chamber can be arranged for each treatment table.
Further, an accommodation cavity is provided in the partition wall, the beam shaper is mounted in the accommodation cavity, and the accommodation cavity is through in a thickness direction of the partition wall.
In another aspect, the present invention provides a support apparatus for supporting a beam shaper for adjusting beam quality of a neutron line produced by a neutron producing device, the support apparatus comprising a receiving cavity in which the beam shaper is mounted, the support apparatus further comprising a concrete wall and a reinforcement portion at least partially disposed within the concrete wall. The concrete structure can shield neutrons and other radiant rays leaked in the working process, the beam shaping body is very sensitive to deformation, the supporting structure is required to have enough rigidity, and the reinforcing part arranged in the concrete can increase the rigidity of the concrete, improve the tensile strength and improve the bearing capacity.
Further, the elastic modulus of the material of the reinforcing part is not lower than 40GPa, the yield strength is not lower than 200MPa, and the ultimate strength is not lower than 100 MPa.
Further, the material of the reinforcement portion is 90 wt% or more of at least one element selected from the group consisting of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, and Ca. The material of the reinforcing part is composed of elements with small neutron action section or short half-life of radioactive isotopes generated after being activated by neutrons, and the radioactivity derived by neutron activation is small, so that the dose caused by secondary radiation is reasonably inhibited, and the future equipment dismantling is facilitated.
Further, the half-life of the radioisotope produced after activation of the enhancement by neutrons is less than 1 year.
Further, the holding cavity is the through-hole that forms on the concrete wall, reinforcing part includes ring, frame and distribution muscle, the ring centers on the setting of beam shaping body, the frame centers on the ring sets up, the distribution muscle is in the concrete with predetermined interval distribution in the thickness direction of level, vertical and concrete, the distribution muscle at least part pass the frame or with the frame overlap joint, the distribution muscle at least part with the ring overlap joint, the material of ring and frame is aluminum alloy or carbon fiber composite or glass fiber composite, the material of distribution muscle is steel or aluminum alloy or carbon fiber composite or glass fiber composite. The ring and the frame increase the rigidity of the concrete, the tensile strength is improved, and the distribution ribs can prevent the concrete from cracking and improve the overall performance of the wall body.
Preferably, the aluminum alloy is an aluminum-magnesium alloy, the carbon fiber composite material is a carbon fiber resin composite material, the glass fiber composite material is a glass fiber resin composite material, the circular ring is a profile or is constructed by ribs, the frame is a profile, the frame comprises a horizontal frame profile beam and a vertical frame profile column, and the horizontal frame profile beam and the vertical frame profile column are connected or welded through bolts. The concrete has high compression strength, low tensile strength and slow strain increase with time under the action of normal stress, and the aluminum-magnesium alloy section has high tensile strength, high shear strength and high rigidity, and the strain does not increase with time under the action of normal stress.
As another preferred, the aluminum alloy is an aluminum-magnesium alloy, the carbon fiber composite material is a carbon fiber resin composite material, the glass fiber composite material is a glass fiber resin composite material, the ring is a profile or is constructed by ribs, the frame comprises a horizontal frame and a vertical frame, the horizontal frame comprises a horizontal longitudinal rib and a stirrup, and the vertical frame comprises a vertical longitudinal rib and a stirrup. The compression-resistant bearing capacity of the concrete is good, the tensile bearing capacity of the aluminum-magnesium alloy bar is good, the aluminum-magnesium alloy bar is arranged at the tensile force position to make up for the deficiency of the tensile strength of the concrete, the tensile strength of the carbon fiber resin composite material or the glass fiber resin composite material is high, and the shear resistance of the wall body can be improved by arranging the stirrup.
In still another aspect, the present invention provides a building for a neutron irradiation system, the building is a concrete structure for accommodating the neutron irradiation system, a reinforcement part is disposed in the concrete structure, and a material of the reinforcement part is 90% (by weight) or more composed of at least one element selected from C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, and Ca. The concrete structure can shield neutrons and other radiation rays leaked in the working process of the neutron irradiation system, the reinforcing part can increase the rigidity of concrete, the tensile strength is improved, the bearing capacity is improved, the material of the reinforcing part is composed of elements which have small cross sections with the neutron action or have short half-life of radioactive isotopes generated after being activated by the neutrons, and the radioactivity derived from the neutron activation is small, so that the dose caused by secondary radiation is reasonably inhibited, and the future equipment dismantling is facilitated.
Further, the reinforcing part comprises horizontal and/or vertical distribution ribs which are distributed in the concrete structure at a predetermined interval in the horizontal, vertical and thickness directions of the concrete structure, and the distribution ribs can prevent concrete from cracking and improve the overall performance of the wall body.
Further, the elastic modulus of the material of the reinforcing part is not lower than 40GPa, the yield strength is not lower than 200MPa, and the ultimate strength is not lower than 100 MPa.
Further, the half-life of the radioisotope produced after activation of the enhancement by neutrons is less than 1 year.
Further, the material of the reinforcing part is at least partially aluminum alloy or carbon fiber composite or glass fiber composite. The half-life of the aluminum after being activated by neutrons is shorter, the carbon fiber composite material or the glass fiber composite material has good activation resistance, and the radioactivity derived from the neutron activation is greatly reduced in a limited time compared with the traditional reinforced concrete structure.
Further, the aluminum alloy is an aluminum-magnesium alloy, the carbon fiber composite material is a carbon fiber resin composite material, the glass fiber composite material is a glass fiber resin composite material, and the concrete of the concrete structure is boron-containing barite concrete. The aluminum-magnesium alloy, the carbon fiber composite material or the glass fiber composite material has excellent mechanical properties, the boron-containing concrete has better neutron absorption performance, the radiation shielding effect of the concrete is enhanced, and the neutron exposure of metal materials in the concrete can be reduced.
Drawings
FIG. 1 is a schematic structural diagram of a neutron capture therapy system in an embodiment of the invention;
FIG. 2 is a schematic illustration of a support structure for a beam shaper of a neutron capture therapy system according to a first embodiment of the present invention;
FIG. 3 is a schematic view of FIG. 2 taken at section A-A;
FIG. 4 is a schematic view of FIG. 2 taken at section B-B;
FIG. 5 is a schematic view of FIG. 2 at section C-C;
FIG. 6 is a schematic illustration of a support structure for a beam shaper of a neutron capture therapy system according to a second embodiment of the present invention;
FIG. 7 is a schematic view of FIG. 6 taken at section D-D;
FIG. 8 is a schematic view of FIG. 6 taken at section E-E;
FIG. 9 is a schematic view of FIG. 6 at section F-F;
FIG. 10 is a schematic illustration of a support structure for a beam shaper of a neutron capture therapy system according to a third embodiment of the present invention;
fig. 11 is a schematic view of fig. 10 at section G-G.
Detailed Description
Embodiments of the present invention will be described in further detail below with reference to the accompanying drawings so that those skilled in the art can implement the embodiments with reference to the description.
Referring to fig. 1, the neutron irradiation system in the present embodiment is preferably a boron neutron capture therapy system 100, which includes a neutron generating device 10, a beam shaper 20, a collimator 30, and a treatment table 40. The neutron generating apparatus 10 includes an accelerator 11 and a target T, and the accelerator 11 accelerates charged particles (such as protons, deuterons, and the like) to generate a charged particle beam P such as a proton beam, and the charged particle beam P irradiates the target T and reacts with the target T to generate a neutron beam (neutron beam) N, and the target T is preferably a metal target. The appropriate nuclear reactions are selected based on the desired neutron yield and energy, the available energy and current for accelerating charged particles, the physical properties of the metal target, and the like, and the nuclear reactions in question include7Li(p,n)7Be and9Be(p,n)9b, both reactions are endothermic. The energy threshold of the two nuclear reactions is 1.881MeV and 2.055MeV respectively, because the ideal neutron source for boron neutron capture treatment is epithermal neutrons with keV energy level, theoretically if a metallic lithium target is bombarded by protons with energy only slightly higher than the threshold, neutrons with relatively low energy can Be generated, and can Be used clinically without too much slowing treatment, however, the proton interaction cross section of the two targets of lithium metal (Li) and beryllium metal (Be) and the threshold energy is not high, and in order to generate enough neutron flux, protons with higher energy are usually selected to initiate the nuclear reaction. The ideal target material should have high neutron yield and neutron energyDistribution close to the hyperthermic neutron energy region (described in detail below), no generation of too much intense penetrating radiation, safety, cheapness, ease of handling, and high temperature resistance, but in practice no nuclear reaction can be found that meets all the requirements, in the examples of the present invention targets made of lithium metal are used. However, as is well known to those skilled in the art, the material of the target T may be made of a metal material other than lithium or beryllium, such as tantalum (Ta) or tungsten (W); the target T may be in the form of a disk, may be in the form of other solid, or may be in the form of a liquid (liquid metal). The accelerator 11 may be a linear accelerator, a cyclotron, a synchrotron, or a synchrocyclotron, and the neutron generating apparatus 10 may also be a nuclear reactor without using an accelerator and a target. Whether the neutron source of boron neutron capture therapy comes from a nuclear reactor or from the nuclear reaction of charged particles of an accelerator and a target, the generated radiation field is actually mixed, i.e. the beam contains neutrons, photons from low energy to high energy. For boron neutron capture therapy of deep tumors, the greater the amount of radiation other than epithermal neutrons, the greater the proportion of non-selective dose deposition in normal tissue, and therefore the unnecessary dose of radiation that these would cause should be minimized. In addition, for normal tissue of the irradiated subject, the various radiation rays should be prevented from being excessive, also resulting in unnecessary dose deposition.
The neutron beam N generated by the neutron generator 10 passes through the beam shaper 20 and the collimator 30 in order and is irradiated on the irradiation target 200 on the treatment table 40. The beam shaper 20 can adjust the beam quality of the neutron beam N generated by the neutron generator 10, the collimator 30 is used for converging the neutron beam N, so that the neutron beam N has high targeting performance in the treatment process, the collimator 30 can be adjusted to adjust the direction of the beam and the position relation between the beam and the irradiated object 200 on the treatment table 40, and the positions of the treatment table 40 and the irradiated object 200 can also be adjusted to enable the beam to be directed at the tumor cells M in the irradiated object 200. These adjustments may be manually made or may be automatically made through a series of control mechanisms. It is understood that the present invention may be practiced without a collimator and the beam exits the beam shaper 20 and is directed toward the irradiated object 200 on the treatment table 40.
The beam shaping body 20 further comprises a reflector 21, a retarder 22, a thermal neutron absorber 23, a radiation shield 24 and a beam outlet 25, neutrons generated by the neutron generating device 10 need to reduce the content of neutrons and photons of other types as much as possible to avoid injury to operators or irradiated bodies besides epithermal neutrons meeting treatment requirements due to wide energy spectrum, so that the fast neutron energy (> 40keV) of the neutrons from the neutron generating device 10 needs to be adjusted to an epithermal neutron energy region (0.5eV-40keV) and the thermal neutrons (< 0.5eV) are reduced as much as possible through the retarder 22, the retarder 22 is made of a material with a large fast neutron action section and a small epithermal neutron action section, and as a preferred embodiment, the retarder 13 is made of a material with a D-D neutron action section2O、AlF3、Fluental、CaF2、Li2CO3、MgF2And Al2O3At least one of (a); the reflector 21 surrounds the retarder 22, reflects neutrons diffused to the periphery through the retarder 22 back to the neutron beam N to improve the utilization rate of the neutrons, and is made of a material having a strong neutron reflection capability, and as a preferred embodiment, the reflector 21 is made of at least one of Pb or Ni; the rear part of the retarder 22 is provided with a thermal neutron absorber 23 which is made of a material with a large cross section for reacting with thermal neutrons, as a preferred embodiment, the thermal neutron absorber 23 is made of Li-6, and the thermal neutron absorber 23 is used for absorbing the thermal neutrons passing through the retarder 22 so as to reduce the content of the thermal neutrons in the neutron beam N and avoid causing excessive dose with shallow normal tissues during treatment; a radiation shield 24 is disposed at the rear of the reflector around the beam outlet 25 for shielding neutrons and photons leaking from a portion outside the beam outlet 25, and a material of the radiation shield 24 includes at least one of a photon shielding material and a neutron shielding material, and as a preferred embodiment, a material of the radiation shield 24 includes a photon shielding material of lead (Pb) and a neutron shielding material of Polyethylene (PE). The collimator 30 is disposed behind the beam outlet 25, and the hyperthermo neutron beam emitted from the collimator 30 irradiates the irradiated object 200, passes through a shallow normal tissue, and is slowed down to be a thermal neutron to reach the tumor cell M. It will be appreciated that the beam shaper 20 may have other configurations as long as the hyperthermia required for the treatment is obtainedA neutron beam.
After the irradiated body 200 is administered or injected with the boron-containing (B-10) drug, the boron-containing drug selectively accumulates in the tumor cells M, and then the boron-containing (B-10) drug has a high capture cross section for thermal neutrons10B(n,α)7Li neutron capture and nuclear fission reaction generation4He and7the average Energy of the two charged particles is about 2.33MeV, the two charged particles have high Linear Energy Transfer (LET) and short-range characteristics, and the Linear Energy Transfer and the range of the α short particles are 150 keV/mum and 8μm respectively7The Li-heavily-charged particles are 175 keV/mum and 5μm, and the total range of the two particles is about equal to the size of a cell, so that the radiation damage to organisms can be limited at the cell level, and the aim of locally killing tumor cells can be achieved on the premise of not causing too much damage to normal tissues.
In this embodiment, a radiation shielding device 50 is further disposed between the irradiated object 200 and the beam outlet 25 to shield the normal tissue of the irradiated object from the beam emitted from the beam outlet 25, but it should be understood that the radiation shielding device 50 may not be disposed.
The boron neutron capture therapy system 100 is entirely housed in a building having a concrete structure, specifically, the boron neutron capture therapy system 100 further includes an irradiation chamber 101 and a charged particle beam generation chamber 102, the object 200 on the therapy table 40 performs therapy in which the neutron beam N is irradiated in the irradiation chamber 101, the charged particle beam generation chamber 102 houses the accelerator 11, and the beam shaper 20 is supported by a partition wall 103 of the irradiation chamber 101 and the charged particle beam generation chamber 102. It is understood that the partition wall 103 may be a wall that completely separates the irradiation chamber 101 and the charged particle beam generation chamber 102; the irradiation chamber 101 and the charged particle beam generation chamber 102 may be partially isolated from each other, and the irradiation chamber 101 and the charged particle beam generation chamber 102 may be communicated with each other. The target material T can have one or more, and the charged particle beam P can selectively act with one or more of the target materials T or simultaneously act with a plurality of the target materials T to generate one or more therapeutic neutron beams N. One or more beam shapers 20, collimators 30 and treatment tables 40 can be provided corresponding to the number of targets T; the treatment tables can be arranged in the same irradiation chamber, or a separate irradiation chamber can be arranged for each treatment table.
The irradiation chamber 101 and the charged particle beam generation chamber 102 are spaces formed by being surrounded by a concrete wall W (including a partition wall 103), and the concrete structure can shield neutrons and other radiation rays leaking during the operation of the boron neutron capture treatment system 100. The concrete wall W comprises a reinforced part (described in detail below) at least partially arranged in the concrete to increase rigidity, improve tensile strength and improve bearing capacity, the elastic modulus of the material of the reinforced part is not less than 40GPa, the yield strength is not less than 200MPa, and the ultimate strength is not less than 100 MPa; meanwhile, the material of the reinforcement part is composed of an element having a small neutron interaction cross section or having a short half-life (less than 1 year) of a radioisotope generated after being activated by neutrons, and specifically, the material of the reinforcement part is composed of at least one of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, and Ca in an amount of 90% by weight or more. In this embodiment, the material of the reinforcement part is at least partially aluminum alloy, carbon fiber composite material, glass fiber composite material, or a combination thereof. When the aluminum alloy is selected, at least part of the aluminum alloy can be aluminum magnesium alloy, and the half life of the aluminum after being activated by neutrons is shorter, namely only 2.2 minutes; in the traditional reinforced concrete structure, elements such as iron, cobalt, nickel and the like rich in the steel bar are activated by neutrons, and then the half-life period is longer, for example, the half-life period of cobalt 60 is 5.27 years; the radioactivity derived from neutron activation is greatly reduced in a limited time by adopting the aluminum-magnesium alloy, so that the dosage caused by secondary radiation is reasonably inhibited, and the future equipment dismantling is facilitated. The aluminum-magnesium alloy has excellent mechanical properties, and other aluminum alloys can be selected. When the carbon fiber composite material or the glass fiber composite material is selected, the carbon fiber composite material or the glass fiber composite material and the resin composite material can be selected, the carbon fiber composite material or the glass fiber composite material and the resin composite material have high strength and good activation resistance, and the carbon fiber composite material or the glass fiber composite material and the resin composite material can be understood as other composite materials. In the following, the concrete structure of the partition wall 103 is described in detail, and the beam shaping body 20 is supported by the partition wall 103 and a reinforcement which is at least partly arranged in the partition wall 103.
With continued reference to fig. 2-5, in a first embodiment of the partition wall 103, the partition wall 103 is a side wall, that is, the irradiation chamber 101 and the charged particle beam generation chamber 102 are horizontally disposed, a receiving chamber 1031 is disposed on the partition wall 103, the beam shaper 20 is installed in the receiving chamber 1031, the receiving chamber 1031 is through in the thickness direction of the partition wall 103, in this embodiment, the beam shaper 20 is cylindrical as a whole, and the receiving chamber 1031 is correspondingly a circular through hole. Since the beam shaper is very sensitive to deformation, which requires a sufficient stiffness of the support structure, the partition wall 103 provides a reinforcement 1032 within the concrete structure. The reinforcement 1032 includes a circular rib a surrounding the beam shaper 20 and a frame rib b surrounding the circular rib a, the frame rib b includes a horizontal frame b1 and a vertical frame b2, the horizontal frame b1 includes a horizontal longitudinal rib b11 and a stirrup b12, the vertical frame b2 includes a vertical longitudinal rib b21 and a stirrup b22, and the number of the horizontal/vertical longitudinal ribs and the stirrups is determined according to actual conditions. The reinforcement 1032 also comprises horizontally and vertically distributed ribs c distributed over the concrete wall at predetermined intervals in the horizontal, vertical and concrete thickness directions, the intervals being determined on a case-by-case basis and being only schematically shown in the figure. The horizontal and vertical distribution ribs c penetrate through the frame ribs b, and the horizontal and vertical distribution ribs c intersected with the circular ring ribs a are lapped with the frame ribs b to improve the anchoring performance and facilitate the positioning of the frame ribs during construction; the ends of the horizontal longitudinal rib b11 and the vertical longitudinal rib b21 are provided with anchor plates d to enhance the bonding strength of the horizontal longitudinal rib b11 and the vertical longitudinal rib b 21. Except the distribution rib lapped with the circular ring rib, the distribution rib can be only arranged in the area except the frame rib, at the moment, the distribution rib and the frame rib are ensured to have certain lapping length, and the anchoring plate can not be arranged. The material of the circular ring rib a and the frame rib b is aluminum magnesium alloy or carbon fiber resin composite material or glass fiber resin composite material; the distribution ribs are made of aluminum-magnesium alloy or carbon fiber resin composite or glass fiber resin composite, and as neutrons are generated in the beam shaping body, peripheral materials are activated most seriously, so that the distribution ribs can be at least partially (such as parts except the frame ribs) made of reinforcing steel bars to reduce cost, and meanwhile, the number of the distribution ribs can meet the requirements of building construction, so that the generation of radioactive nuclides is reduced. As well known to those skilled in the art, in the construction process, the distribution rib may be further provided with a tie bar (not shown) in the concrete thickness direction, and the number of the tie bars is determined according to the actual situation; the crossed ribs are bound and connected through fixing parts such as steel wires and the like, such as horizontal and vertical distribution ribs, horizontal/vertical distribution ribs and tie bars, horizontal/vertical longitudinal ribs and hoop bars, and circular ring ribs and horizontal/vertical distribution ribs. It will be appreciated that the distribution ribs may be provided only when the other concrete wall W is not provided with, for example, beam shaping bodies. During construction, the distribution ribs of other concrete walls, the distribution ribs of the partition wall 103, the circular ring ribs, the frame ribs and the like are bound and anchored together, then templates at the edges of the walls (including the inner wall of the accommodating cavity) are erected for pouring concrete, and the beam shaping body is installed in the accommodating cavity of the partition wall after pouring is finished. It is understood that the construction process may be performed in other ways known to those skilled in the art. The compression-resistant bearing capacity of the concrete is good, the tensile bearing capacity of the aluminum magnesium alloy bar and the reinforcing steel bar is good, the aluminum magnesium alloy bar and the reinforcing steel bar are arranged at the tensile force position, the defect of the tensile strength of the concrete can be made up, and the shear resistance of the wall body can be improved by arranging the stirrup. The distributed reinforcing steel bars can prevent concrete from cracking and improve the overall performance of the wall body.
As a second embodiment of the partition wall 103 ', only the differences from the first embodiment are described below, as in fig. 6-9, the reinforcement 1032 ' of the partition wall 103 ' comprises a circular ring profile a ' surrounding the beam shaper and a frame profile b ' surrounding the circular ring profile a ', the frame profile b ' comprising a horizontal frame profile bar b1 ' and a vertical frame profile bar b2 '. The reinforcement 1032 'also includes horizontal and vertical distribution ribs c' distributed in the whole concrete wall at predetermined intervals in the horizontal, vertical and concrete thickness directions, the intervals being determined according to specific situations. The horizontal frame section bar beam b1 'and the vertical frame section bar column b 2' are connected by bolts or by welding, so long as the connection strength of the joint is ensured; the horizontal and vertical distribution ribs c ' penetrate through holes reserved in the aluminum-magnesium alloy frame section bar b ' to enhance the anchoring performance and the ductility of the wall body, and the horizontal and vertical distribution ribs c ' intersected with the circular ring section bar a ' are lapped with the horizontal and vertical distribution ribs c ' to increase the anchoring performance and facilitate positioning of the horizontal and vertical distribution ribs during construction. Besides the distribution ribs intersected with the circular ring section bar, the distribution ribs can also be arranged in the areas except the frame section bar, and the distribution ribs are lapped with the frame section bar. The ring section bar a 'and the frame section bar b' are made of aluminum magnesium alloy or carbon fiber resin composite material or glass fiber resin composite material; the distribution rib is made of aluminum-magnesium alloy or carbon fiber resin composite or glass fiber resin composite, and as neutrons are generated in the beam shaping body, peripheral materials are activated most seriously, so that the distribution rib can be at least partially (such as parts except frame profiles) made of steel bars to reduce cost, and meanwhile, the number of the distribution ribs can meet the requirements of building construction, so that the generation of radioactive nuclides is reduced. As well known to those skilled in the art, in the construction process, the distribution rib may be further provided with a tie bar (not shown) in the concrete thickness direction, and the number of the tie bars is determined according to the actual situation; the crossed ribs are bound and connected through fixing parts such as steel wires and the like, such as horizontal and vertical distribution ribs, horizontal/vertical distribution ribs and tie bars, circular ring profiles and horizontal/vertical distribution ribs. In this embodiment, the sectional shape of the aluminum magnesium alloy profile is an H shape, and it is understood that the sectional shape may be other shapes. During construction, distribution ribs of other concrete walls, distribution ribs of the partition wall 103', circular ring profiles, frame profiles and the like are bound and anchored together, then templates at the edge of the wall (including the inner wall of the accommodating cavity) are erected for pouring concrete, and after pouring is finished, the beam shaping body is installed in the accommodating cavity of the partition wall. It is understood that the construction process may be performed in other ways known to those skilled in the art. The compression strength of the concrete is high, but the tensile strength is low, the strain slowly increases along with the time under the action of normal stress, the tensile strength and the shear strength of the aluminum-magnesium alloy section are good, the rigidity is high, the strain does not increase along with the time under the action of normal stress, and the defects of the mechanical property and the material property of the concrete can be overcome. The distributed reinforcing steel bars can prevent concrete from cracking and improve the overall performance of the wall body.
It will be appreciated that the reinforcement of the partition wall may also be a combination of the two above embodiments, e.g. the reinforcement may comprise a ring rib surrounding the beam shaper and a frame profile surrounding the ring rib, or a ring profile surrounding the beam shaper and a frame rib surrounding the ring profile.
As shown in fig. 10 to 11, which is a third embodiment of the partition wall 103 ', the irradiation chamber and the charged particle beam generating chamber are arranged vertically in this embodiment, that is, the partition wall 103' is a floor (floor or ceiling), the neutron producing apparatus 10 'further includes a beam delivery portion 12', the beam delivery portion 12 'delivering the charged particle beam generated by the accelerator 11' to the target, a through hole 1031 'provided in the partition wall 103', the beam delivery portion 12 'passing through the through hole 1031'. The reinforcement 1032 ' of the partition wall 103 ' comprises a first reinforcement d provided in the concrete of the partition wall 103 ', and a second reinforcement e extending at least partly out of the concrete of the partition wall 103 ', the second reinforcement e comprising a horizontal support plate e1 and a side plate e2 connecting the support plate e1 and the first reinforcement d, the beam shaper 20 ' being supported on the horizontal support plate e 1. In this embodiment, the second reinforcing portion e is a u-shaped groove-shaped structure, the side plates e2 are 2 opposite, and the material is aluminum-magnesium alloy, carbon fiber resin composite material or glass fiber resin composite material, so as to reduce the generation of radioactive nuclides; considering that the structural steel has high strength, good plastic toughness, uniform material quality and good weldability, steel can also be adopted; it will be appreciated that other materials or other forms of construction may be employed. The side of the support plate e1 facing the first reinforcement d is provided with a flange e11, the beam shaper 20 "being located in the flange e11, the flange e11 limiting the beam shaper 20" in the horizontal direction. In this embodiment, the beam shaper is cylindrical as a whole, and the corresponding flange is a circular rib. The support plate e1 is also formed with a through hole e12 through which the neutron beam N generated by the neutron generating device 10 passes out of the through hole e12 through the beam shaper 20', and in this embodiment, the through hole e12 is formed by cutting on the support plate e 1.
The first reinforcement part on the one hand reinforces the strength of the floor opening (through hole) edge and on the other hand provides support for the beam shaping body. The first reinforcement can be configured as in the above-described embodiments to include a frame rib/profile and a circular ring rib/profile, and since here is a floor, the frame rib or the frame profile includes only a horizontal skeleton or a horizontal frame profile beam, and the vertical skeleton or the vertical frame profile column is replaced by a horizontal skeleton or a horizontal frame profile beam, and the specific configuration is not described in detail here, and only two profile beams are illustrated in the figures. When the first reinforcing part is constructed as a frame profile, the side plate e2 is welded or bolted with the frame profile, and it can be understood that other connecting modes can be adopted as long as the connecting strength is ensured; when the first reinforcing part is configured as a frame rib, the end of the side plate e2 is provided with an anchoring plate, and the anchoring plate is anchored with the frame rib. The horizontal framework or horizontal frame profile beam connected to the side plates extends over the entire length of the floor slab, taking into account the vertical stresses of the floor slab and the first reinforcement. The reinforcement 1032 ' like the above embodiment further includes (horizontal) distribution ribs c ', tie bars (not shown), etc. which are distributed in the concrete at predetermined intervals in the horizontal direction and the thickness direction of the concrete, and when constructing, the distribution ribs of other concrete walls are tied and anchored together with the distribution ribs, the frame ribs/profiles, the round ribs/profiles, etc. of the partition wall 103 ', the second reinforcement is welded or anchored to the first reinforcement, then a formwork of the wall edge (including the inner wall of the through hole) is erected to perform concrete pouring, and after the pouring, the beam shaping body is fitted into the flange from the side of the second reinforcement without the side plate, and the beam transmitting portion is installed through the through hole. It is understood that the construction process may be performed in other ways known to those skilled in the art.
The boron neutron capture treatment system 100 can further comprise a preparation room, a control room and other spaces for auxiliary treatment, each irradiation room can be provided with a preparation room for fixing the irradiated object to the treatment table, injecting boron medicine, simulating a treatment plan and the like before irradiation treatment, a connecting channel is arranged between the preparation room and the irradiation room, and the irradiated object is directly pushed into the irradiation room after the preparation is completed or automatically enters the irradiation room under the control of the control mechanism through a track. The control room is used for controlling the accelerator, the beam transmission part, the treatment table and the like, the whole irradiation process is controlled and managed, and a manager can simultaneously monitor a plurality of irradiation rooms in the control room.
The concrete wall in the embodiment is a boron-containing barite concrete wall with the thickness of more than 1m and the density of 3g/c.c., the boron-containing concrete has better neutron absorption performance, the radiation shielding effect of the concrete is enhanced, and the neutron exposure amount of metal materials in the concrete can be reduced. It will be appreciated that other thicknesses or densities are possible or other materials may be substituted and that different portions of the concrete wall may differ in thickness, density or material. It is to be understood that the present invention is also applicable to other types of neutron irradiation systems.
Although illustrative embodiments of the invention have been described above to facilitate the understanding of the invention by those skilled in the art, it should be understood that the invention is not limited to the scope of the embodiments, and that various changes will become apparent to those skilled in the art within the spirit and scope of the invention as defined and defined in the appended claims.
Claims (10)
1. A neutron capture treatment system is characterized by comprising a neutron generating device and a beam shaper, wherein the neutron generating device comprises an accelerator and a target, charged particle rays generated by acceleration of the accelerator and the target act to generate neutron rays, the beam shaper comprises a reflector, a retarder, a thermal neutron absorber, a radiation shield and a beam outlet, the retarder decelerates neutrons generated from the target to a super-thermal neutron energy region, the reflector surrounds the retarder and guides deviated neutrons back to the retarder to improve the intensity of a super-thermal neutron beam, the thermal neutron absorber is used for absorbing thermal neutrons to avoid excessive dose caused by shallow normal tissues during treatment, the radiation shield is arranged at the rear part of the reflector around the beam outlet and used for shielding leaked neutrons and photons to reduce the normal tissue dose of a non-irradiation region, the neutron capture therapy system further comprises a concrete wall accommodating the neutron generating device and the beam shaping body, wherein a reinforcing part for supporting the beam shaping body is arranged in the concrete wall, and the material of the reinforcing part is more than 90% (weight percentage) composed of at least one element of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S and Ca.
2. The neutron capture therapy system of claim 1, wherein the reinforcement has a material elastic modulus of not less than 40GPa, a yield strength of not less than 200MPa, an ultimate strength of not less than 100MPa, a half-life of the radioisotope generated after activation of the reinforcement by neutrons of less than 1 year, and at least a portion of the material of the reinforcement is an aluminum alloy or a carbon fiber composite or a glass fiber composite.
3. The neutron capture therapy system of claim 1, further comprising a treatment table and a collimator disposed behind the beam outlet to converge neutron rays, wherein the neutron rays generated by the neutron generating device are directed through the beam shaper and the collimator to an object on the treatment table, and wherein a radiation shield is disposed between the object and the beam outlet to shield the beam exiting the beam outlet from normal tissue of the object.
4. The neutron capture treatment system of claim 3, further comprising a charged particle beam generation chamber and an irradiation chamber, wherein the irradiated body on the treatment table is subjected to a treatment by neutron irradiation in the irradiation chamber, the charged particle beam generation chamber accommodates the accelerator, the concrete wall includes a partition wall between the charged particle beam generation chamber and the irradiation chamber, and the beam shaping body is disposed in and supported by the partition wall.
5. The neutron capture therapy system of claim 4, wherein a receiving cavity is provided in the dividing wall, the beam shaper being mounted in the receiving cavity, the receiving cavity being through in a thickness direction of the dividing wall.
6. A support device for supporting a beam shaper for adjusting the beam quality of neutron lines produced by a neutron production device, characterized in that the support device comprises a receiving cavity in which the beam shaper is mounted, the support device further comprising a concrete wall and a reinforcement at least partly arranged within the concrete wall.
7. The support apparatus according to claim 6, wherein the reinforcing member has a material elastic modulus of not less than 40GPa, a yield strength of not less than 200MPa, and an ultimate strength of not less than 100MPa, the material of the reinforcing member is composed of at least one element selected from C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, and Ca in an amount of 90 wt% or more, and the reinforcing member has a half-life of less than 1 year in a radioisotope produced after activation by neutrons.
8. The support apparatus of claim 6 wherein the receiving chamber is a through-hole formed in the concrete wall, the reinforcement comprises a ring disposed around the beam shaper, a frame disposed around the ring, and distribution ribs distributed within the concrete at predetermined intervals in the horizontal, vertical and thickness directions of the concrete, the distribution ribs at least partially passing through or overlapping the frame, the distribution ribs at least partially overlapping the ring, the ring and frame being made of an aluminum alloy or a carbon fiber composite or a glass fiber composite, and the distribution ribs being made of a steel or an aluminum alloy or a carbon fiber composite or a glass fiber composite.
9. The support device of claim 8, wherein the aluminum alloy is aluminum magnesium alloy, the carbon fiber composite is carbon fiber resin composite, the glass fiber composite is glass fiber resin composite, the ring is a profile or is constructed with ribs, the frame is a profile, the frame comprises horizontal frame profile beams and vertical frame profile columns, and the horizontal frame profile beams and the vertical frame profile columns are connected by bolts or welded.
10. The support apparatus according to claim 8, wherein the aluminum alloy is aluminum-magnesium alloy, the carbon fiber composite is carbon fiber-resin composite, the glass fiber composite is glass fiber-resin composite, the annular ring is a profile or is constructed of ribs, the frame comprises a horizontal frame and a vertical frame, the horizontal frame comprises horizontal longitudinal ribs and stirrups, and the vertical frame comprises vertical longitudinal ribs and stirrups.
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