WO2020042681A1 - 中子捕获治疗系统 - Google Patents

中子捕获治疗系统 Download PDF

Info

Publication number
WO2020042681A1
WO2020042681A1 PCT/CN2019/087928 CN2019087928W WO2020042681A1 WO 2020042681 A1 WO2020042681 A1 WO 2020042681A1 CN 2019087928 W CN2019087928 W CN 2019087928W WO 2020042681 A1 WO2020042681 A1 WO 2020042681A1
Authority
WO
WIPO (PCT)
Prior art keywords
neutron
frame
composite material
concrete
reinforcing portion
Prior art date
Application number
PCT/CN2019/087928
Other languages
English (en)
French (fr)
Inventor
江涛
陈韦霖
Original Assignee
中硼(厦门)医疗器械有限公司
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 中硼(厦门)医疗器械有限公司 filed Critical 中硼(厦门)医疗器械有限公司
Priority to EP22178803.7A priority Critical patent/EP4082610B1/en
Priority to EP19855979.1A priority patent/EP3845273B1/en
Priority to JP2021520262A priority patent/JP7101312B2/ja
Publication of WO2020042681A1 publication Critical patent/WO2020042681A1/zh
Priority to US17/145,562 priority patent/US20210146163A1/en
Priority to JP2022107475A priority patent/JP2022133372A/ja
Priority to JP2024039529A priority patent/JP2024079718A/ja

Links

Images

Classifications

    • E—FIXED CONSTRUCTIONS
    • E04—BUILDING
    • E04C—STRUCTURAL ELEMENTS; BUILDING MATERIALS
    • E04C5/00—Reinforcing elements, e.g. for concrete; Auxiliary elements therefor
    • E04C5/01—Reinforcing elements of metal, e.g. with non-structural coatings
    • E04C5/06—Reinforcing elements of metal, e.g. with non-structural coatings of high bending resistance, i.e. of essentially three-dimensional extent, e.g. lattice girders
    • E04C5/0604—Prismatic or cylindrical reinforcement cages composed of longitudinal bars and open or closed stirrup rods
    • 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
    • A61N5/1077—Beam delivery systems
    • E—FIXED CONSTRUCTIONS
    • E04—BUILDING
    • E04C—STRUCTURAL ELEMENTS; BUILDING MATERIALS
    • E04C5/00—Reinforcing elements, e.g. for concrete; Auxiliary elements therefor
    • E04C5/01—Reinforcing elements of metal, e.g. with non-structural coatings
    • E04C5/06—Reinforcing elements of metal, e.g. with non-structural coatings of high bending resistance, i.e. of essentially three-dimensional extent, e.g. lattice girders
    • E04C5/0645—Shear reinforcements, e.g. shearheads for floor slabs
    • E—FIXED CONSTRUCTIONS
    • E04—BUILDING
    • E04C—STRUCTURAL ELEMENTS; BUILDING MATERIALS
    • E04C5/00—Reinforcing elements, e.g. for concrete; Auxiliary elements therefor
    • E04C5/07—Reinforcing elements of material other than metal, e.g. of glass, of plastics, or not exclusively made of metal
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F1/00—Shielding characterised by the composition of the materials
    • G21F1/02—Selection of uniform shielding materials
    • G21F1/04—Concretes; Other hydraulic hardening materials
    • G21F1/042—Concretes combined with other materials dispersed in the carrier
    • 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
    • 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
    • E—FIXED CONSTRUCTIONS
    • E04—BUILDING
    • E04B—GENERAL BUILDING CONSTRUCTIONS; WALLS, e.g. PARTITIONS; ROOFS; FLOORS; CEILINGS; INSULATION OR OTHER PROTECTION OF BUILDINGS
    • E04B1/00—Constructions in general; Structures which are not restricted either to walls, e.g. partitions, or floors or ceilings or roofs
    • E04B1/62—Insulation or other protection; Elements or use of specified material therefor
    • E04B1/92—Protection against other undesired influences or dangers
    • E04B2001/925—Protection against harmful electro-magnetic or radio-active radiations, e.g. X-rays
    • H—ELECTRICITY
    • H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
    • H05H6/00—Targets for producing nuclear reactions
    • H05H2006/007—Radiation protection arrangements, e.g. screens

Definitions

  • the invention relates to a radiation irradiation system, in particular to a neutron capture treatment system.
  • neutron capture therapy is a combination of the above two concepts, such as boron neutron capture therapy, which uses boron-containing drugs to specifically accumulate in tumor cells and cooperates with precise neutron beam regulation to provide better than traditional radiation. Cancer treatment options.
  • Radioactive isotopes with a longer half-life will be produced. For example, the half-life of cobalt 60 is 5.27. In the year, long-term radioactive waste was formed, which had a negative impact on the environment and radiation safety.
  • an aspect of the present invention provides a neutron capture treatment system, which includes a neutron generating device and a beam shaper.
  • the neutron generating device includes an accelerator and a target, and the charged particles generated by the accelerator accelerate.
  • the beam interacts with the target to generate a neutron.
  • the beam shaper includes a reflector, a retarder, a thermal neutron absorber, a radiation shield, and a beam exit.
  • the retarder will be from the target.
  • the neutron generated by the material is decelerated to the superheated neutron energy region, the reflector surrounds the retarder and directs the deviated neutron back to the retarder to increase the intensity of the superheated neutron beam.
  • the thermal neutron absorber is used to absorb thermal neutrons to avoid excessive doses with shallow normal tissue during treatment.
  • the radiation shield is arranged around the beam exit at the rear of the reflector for shielding leakage.
  • Neutrons and photons to reduce the normal tissue dose in non-irradiated areas the neutron capture treatment system further includes a concrete wall that houses the neutron generating device and a beam shaper, the concrete wall and at least a part of the concrete wall Inside the concrete wall
  • the reinforcing part is used for supporting the beam shaper. 90% (weight percentage) of the material of the reinforcing part is composed of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, It is composed of at least one element of S, Ca, and Ti.
  • the concrete structure can shield the neutrons and other radiations leaked during the working process of the neutron capture therapy system.
  • the reinforcement can increase the rigidity of the concrete, improve the tensile strength, and improve the carrying capacity.
  • the radioactive isotope produced by neutron activation has a short half-life element. The radioactivity derived from neutron activation is small. In addition to reasonably suppressing the dose caused by secondary radiation, it is more conducive to future equipment dismantling.
  • the material has an elastic modulus of not less than 40 GPa, a yield strength of not less than 100 MPa, and an ultimate strength of not less than 200 Mpa.
  • the half-life of the radioisotope generated after the enhancement part is activated by the neutron is less than one year.
  • the material of the reinforcing portion is at least partially an aluminum alloy, a carbon fiber composite material, or a glass fiber composite material.
  • Aluminum has a short half-life after being activated by neutrons, and carbon fiber composites or glass fiber composites have good anti-activation properties. Compared with traditional reinforced concrete structures, the radioactivity derived from neutron activation is greatly reduced in a limited time.
  • the neutron capture treatment system further includes a treatment table and a collimator, the collimator is disposed at the rear of the beam exit to gather neutrons, and the neutrons generated by the neutron generating device
  • the object to be irradiated on the treatment table is irradiated with the beam shaper and the collimator, and a radiation shielding device is provided between the object to be irradiated and the beam exit to shield the beam exiting from the beam exit Radiation to the normal tissue of the irradiated body.
  • the neutron capture treatment system further includes a charged particle beam generation chamber and an irradiation chamber, and the irradiated body on the treatment table performs treatment of neutron beam irradiation in the irradiation chamber, and the charged particle beam generation
  • the chamber houses the accelerator
  • the concrete wall includes a partition wall between the charged particle beam generation chamber and the irradiation chamber.
  • the partition wall may completely separate the irradiation chamber and the charged particle beam generation chamber; it may also be a partial partition between the irradiation chamber and the charged particle beam generation chamber, and the irradiation chamber and the charged particle beam generation chamber are in communication.
  • Multiple treatment tables can be set in the same irradiation room, or a separate irradiation room can be set for each treatment table.
  • the beam shaping body is disposed in the partition wall and supported by the partition wall, and a receiving cavity is provided on the partition wall, and the beam shaping body is installed in the receiving cavity.
  • the receiving cavity is penetrated in a thickness direction of the partition wall.
  • the neutron generating device further includes a beam transmission section that transmits the charged particle beam generated by the accelerator to the target, and a through hole is provided on the partition wall, so that The beam transmitting portion passes through the through hole, the reinforcing portion is at least partially disposed in the partition wall, and the beam shaping body is supported on the reinforcing portion.
  • Another aspect of the present invention provides a supporting device for supporting a beam shaping body, the beam shaping body is used for adjusting the beam quality of a neutron line generated by a neutron generating device, and the supporting device includes a receiving cavity
  • the beam shaping body is installed in the accommodating cavity, and the supporting device further includes a concrete wall and a reinforcing portion at least partially disposed in the concrete wall.
  • the concrete structure can shield neutrons and other radiation leaked during the working process, and the beam shaper is very sensitive to deformation. It requires a sufficient rigidity of the support structure.
  • the reinforcement in the concrete can increase the rigidity of the concrete and enhance the tensile strength Strength and improve carrying capacity.
  • the material has a modulus of elasticity of not less than 40 GPa, a yield strength of not less than 100 MPa, and an ultimate strength of not less than 200 MPa.
  • the material of the reinforcing portion is 90% (weight percent) or more of at least one of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti.
  • the material of the reinforcement part is composed of elements that have a small cross-section with neutrons or short-lived radioisotopes generated after being activated by neutrons. The radioactivity derived from neutron activation is small. In addition to reasonably suppressing the dose caused by secondary radiation, Facilitate the removal of future equipment.
  • the half-life of the radioisotope generated after the enhancement part is activated by the neutron is less than one year.
  • the receiving cavity is a through hole formed in the concrete wall
  • the reinforcing portion includes a ring, a frame, and a distribution rib
  • the ring is provided around the beam shaper
  • the frame surrounds the beam shaper.
  • the distribution ribs are arranged in the concrete at a predetermined interval in the horizontal, vertical and thickness direction of the concrete.
  • the distribution ribs at least partially pass through or overlap the frame, and the distribution ribs are at least partially It is partially overlapped with the ring
  • the material of the ring and the frame is aluminum alloy or carbon fiber composite material or glass fiber composite material
  • the material of the distribution rib is steel or aluminum alloy or carbon fiber composite material or glass fiber composite material .
  • the ring and frame increase the rigidity of the concrete, improve the tensile strength, and the distribution ribs can prevent the concrete from cracking and improve the overall performance of the wall.
  • 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 a rib
  • the frame For profiles or constructed from tendons.
  • the frame is a profile
  • the frame includes 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 by bolts.
  • the compressive strength of concrete is large, but its tensile strength is low, and the strain slowly increases with time under the action of constant stress, while the tensile strength and shear strength of aluminum-magnesium alloy profiles are good, and the stiffness is large, and under the action of constant stress
  • the strain does not increase with time, and the carbon fiber resin composite material or glass fiber resin composite material has high tensile strength, which can make up for the lack of concrete mechanical properties and material characteristics.
  • the frame is constructed of tendons, it includes a horizontal skeleton and a vertical skeleton, the horizontal skeleton includes a horizontal longitudinal rib and a stirrup, and the vertical skeleton includes a vertical longitudinal rib and a stirrup.
  • the compressive bearing capacity of concrete is good, and the aluminum-magnesium alloy tendons have good tensile bearing capacity.
  • the aluminum-magnesium alloy tendons can be used to compensate for the lack of tensile strength of concrete.
  • the tensile strength of carbon fiber resin composite materials or glass fiber resin composite materials. High, equipped with stirrups can improve the shear performance of the wall.
  • the reinforcing portion includes a first reinforcing portion and a second reinforcing portion, the first reinforcing portion is disposed in the concrete wall, and the second reinforcing portion at least partially protrudes from the concrete wall .
  • the first reinforcing portion includes a ring, a frame, and a distribution rib
  • the ring is provided around the beam shaper
  • the frame is provided around the ring
  • the distribution rib is horizontal and concrete.
  • the thickness direction is distributed in the concrete at a predetermined interval
  • the distribution ribs at least partially pass through or overlap the frame
  • the distribution ribs overlap at least partially with the ring, and the ring and the frame
  • the material is aluminum alloy or carbon fiber composite material or glass fiber composite material
  • the material of the distribution rib is steel or aluminum alloy or carbon fiber composite material or glass fiber composite material.
  • the ring and frame increase the rigidity of the concrete, improve the tensile strength, and the distribution ribs can prevent the concrete from cracking and improve the overall performance of the wall.
  • 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 a rib
  • the frame By a horizontal frame profile beam or a horizontal skeleton, the horizontal skeleton includes horizontal longitudinal bars and stirrups.
  • the compressive strength of concrete is large, but its tensile strength is low, and the strain slowly increases with time under the action of constant stress, while the tensile strength and shear strength of aluminum-magnesium alloy profiles are good, and the stiffness is large, and under the action of constant stress The strain does not increase with time.
  • the tensile strength of aluminum-magnesium alloy bars is good.
  • the tensile strength of carbon fiber resin composite materials or glass fiber resin composite materials is high, which can make up for the lack of mechanical properties and material properties of concrete.
  • the configuration of stirrups can improve the resistance of the wall. Shear performance.
  • the second reinforcing portion includes a horizontal supporting plate and a side plate connecting the supporting plate and the first reinforcing portion, and the receiving cavity is formed on the supporting plate.
  • a flange is provided on a side of the support plate facing the first reinforcing portion, the flange forms the receiving cavity and limits the beam shaping body in a horizontal direction, and the support plate forms a through hole. Hole, the neutron line exits the through hole through the beam shaping body.
  • the building is a concrete structure that houses the neutron irradiation system.
  • a reinforcement part is provided in the concrete structure, and the material of the reinforcement part is 90%. (Weight percentage) or more is composed of at least one element of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti.
  • the concrete structure can shield the neutrons and other radiations leaked during the working process of the neutron irradiation system.
  • the reinforcing part can increase the rigidity of the concrete, improve the tensile strength, and improve the carrying capacity.
  • the radioactive isotope produced by neutron activation has a short half-life element composition, and the radioactivity derived from neutron activation is small. In addition to reasonably suppressing the dose caused by secondary radiation, it is more conducive to future equipment dismantling.
  • the reinforcing portion includes horizontal and / or vertical distribution ribs, and the horizontal and / or vertical distribution ribs are distributed in the concrete structure at a predetermined interval in the horizontal, vertical, and thickness direction of the concrete structure. Distribution ribs can prevent concrete from cracking and improve the overall performance of the wall.
  • the material has an elastic modulus of not less than 40 GPa, a yield strength of not less than 100 MPa, and an ultimate strength of not less than 200 Mpa.
  • the half-life of the radioisotope generated after the enhancement part is activated by the neutron is less than one year.
  • the material of the reinforcing portion is at least partially an aluminum alloy, a carbon fiber composite material, or a glass fiber composite material.
  • Aluminum has a short half-life after being activated by neutrons, and carbon fiber composites or glass fiber composites have good anti-activation properties. Compared with traditional reinforced concrete structures, the radioactivity derived from neutron activation is greatly reduced in a limited time.
  • 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 concrete of the concrete structure is boron-containing barite concrete.
  • Aluminum-magnesium alloy, carbon fiber composite material or glass fiber composite material has superior mechanical properties, and boron-containing concrete has better neutron absorption performance. In addition to enhancing the radiation shielding effect of concrete, it can also reduce the neutrality of metal materials in concrete. Sub exposure.
  • FIG. 1 is a schematic structural diagram of a neutron capture treatment system in an embodiment of the present invention
  • FIG. 2 is a schematic view of a support structure of a beam shaper of a neutron capture therapy system according to a first embodiment of the present invention
  • Figure 3 is a schematic view of the section A-A in Figure 2;
  • Fig. 4 is a schematic view of the section taken along the line B-B in Fig. 2;
  • Fig. 5 is a schematic view of the section taken along the line C-C in Fig. 2;
  • FIG. 6 is a schematic view of a support structure of a beam shaper of a neutron capture therapy system according to a second embodiment of the present invention.
  • FIG. 7 is a schematic diagram of the D-D section of FIG. 6; FIG.
  • Fig. 8 is a schematic diagram of the E-E cross section of Fig. 6;
  • FIG. 9 is a schematic diagram of the F-F section of FIG. 6; FIG.
  • FIG. 10 is a schematic view of a support structure of a beam shaper of a neutron capture therapy system according to a third embodiment of the present invention.
  • Fig. 11 is a schematic view taken along the line G-G in Fig. 10.
  • the neutron irradiation system in this embodiment is preferably a boron neutron capture treatment system 100, which includes a neutron generating device 10, a beam shaper 20, a collimator 30, and a treatment table 40.
  • the neutron generating device 10 includes an accelerator 11 and a target T.
  • the accelerator 11 accelerates charged particles (such as protons, deuterons, etc.) to generate charged particle lines P such as proton lines.
  • the charged particle lines P are irradiated to the target T and interact with the target material T.
  • the target T generates a neutron (neutron beam) N, and the target T is preferably a metal target.
  • the nuclear reactions that are often discussed are 7 Li (p, n) 7 Be and 9 Be (p, n) 9 B. Both of these reactions are endothermic reactions.
  • the energy thresholds of the two nuclear reactions are 1.881 MeV and 2.055 MeV respectively. Since the ideal neutron source for boron neutron capture therapy is superheated neutrons of keV energy level, theoretically, if protons with energy only slightly above the threshold are used to bombard lithium metal Targets can generate relatively low-energy neutrons and can be used in clinical applications without much slowing down.
  • the cross-sections of protons with threshold energy of lithium metal (Li) and beryllium metal (Be) are not high.
  • higher energy protons are usually selected to initiate the nuclear reaction.
  • the ideal target should have high neutron yield, neutron energy distribution close to the superheated neutron energy region (described in detail below), no too much strong penetrating radiation, safe and cheap, easy to operate, and high temperature resistance.
  • a nuclear reaction that meets all requirements cannot be found.
  • a target made of lithium metal is used.
  • the material of the target T can also be made of metal materials other than lithium and beryllium, for example, formed of tantalum (Ta) or tungsten (W); the target T can be in the shape of a circular plate. Other solid shapes may be used, and a liquid (liquid metal) may be used.
  • the accelerator 11 may be a linear accelerator, a cyclotron, a synchrotron, a synchrocyclotron, and the neutron generating device 10 may also be a nuclear reactor without using an accelerator and a target.
  • the neutron source of boron neutron capture therapy comes from a nuclear reactor or the nuclear reaction of charged particles with the target, what is actually generated is a mixed radiation field, that is, the beam contains low-energy to high-energy neutrons and photons.
  • the beam contains low-energy to high-energy neutrons and photons.
  • various kinds of radiation should be avoided, which also causes unnecessary dose deposition.
  • the neutron beam N generated by the neutron generating device 10 is irradiated to the subject 200 on the treatment table 40 through the beam shaper 20 and the collimator 30 in this order.
  • the beam shaping body 20 can adjust the beam quality of the neutron beam N generated by the neutron generating device 10, and the collimator 30 is used for converging the neutron beam N, so that the neutron beam N has a higher quality during the treatment process.
  • Targeting, by adjusting the collimator 30, the beam direction and the positional relationship between the beam and the irradiated body 200 on the treatment table 40 can be adjusted, and the positions of the treatment table 40 and the irradiated body 200 can also be adjusted to make the radiation
  • the beam is directed at the tumor cells M in the irradiated body 200. These adjustments can be performed manually or automatically through a series of control mechanisms. It can be understood that the present invention may not have a collimator, and the beam is directly irradiated onto the object 200 on the treatment table 40 after it exits the beam shaping
  • the beam shaper 20 further includes a reflector 21, a retarder 22, a thermal neutron absorber 23, a radiation shield 24, and a beam exit 25. Since the neutrons generated by the neutron generating device 10 have a wide energy spectrum, In addition to thermal neutrons meeting the needs of treatment, other types of neutrons and photons must be reduced as much as possible to avoid harm to the operator or the irradiated body. Therefore, the neutrons from the neutron generator 10 need to pass through the retarder 22
  • the fast neutron energy > 40keV
  • the fast neutron energy is adjusted to the superthermal neutron energy range (0.5eV-40keV) and the thermal neutron is reduced as much as possible ( ⁇ 0.5eV).
  • the retarder 22 has a large cross-section with fast neutrons.
  • the superthermal neutron has a small cross-section.
  • the retarder 13 is made of D 2 O, AlF 3 , Fluental, CaF 2 , Li 2 CO 3 , MgF 2 and Al 2 O 3 .
  • the reflector 21 surrounds the retarder 22, and reflects the neutrons diffused through the retarder 22 to the neutron beam N to improve the utilization rate of the neutron.
  • the reflector 21 is made of at least one of Pb or Ni
  • the thermal neutron absorber 23 is made of a material having a large cross section that interacts with the thermal neutron.
  • the thermal neutron absorber 23 is made of Li-6,
  • the sub-absorber 23 is used to absorb the thermal neutrons passing through the retarder 22 to reduce the content of the thermal neutrons in the neutron beam N, to avoid excessive doses with shallow normal tissue during treatment;
  • the radiation shield 24 surrounds the beam
  • the outlet 25 is provided at the rear of the reflector for shielding neutrons and photons leaking from the part other than the beam exit 25.
  • the material of the radiation shielding body 24 includes at least one of a photon shielding material and a neutron shielding material, as a
  • the material of the radiation shielding body 24 includes a photon shielding material lead (Pb) and a neutron shielding material polyethylene (PE).
  • the collimator 30 is disposed at the rear of the beam exit 25, and the superheated neutron beam coming out of the collimator 30 is irradiated to the irradiated body 200, and after passing through the normal tissue in the shallow layer, it is slowed down to reach the tumor cell M by thermal neutron.
  • the beam shaper 20 may have other structures as long as the superheated neutron beam required for treatment can be obtained.
  • the boron-containing drug selectively accumulates in tumor cells M, and then the boron-containing (B-10) drug has a characteristic of high capture cross-section for thermal neutrons .
  • the average energy of two charged particles is about 2.33 MeV, which has characteristics of high linear energy transfer (LET) and short range.
  • the linear energy transfer and range of ⁇ short particles are 150 keV / ⁇ m and 8 ⁇ m, respectively, and 7 Li heavy-loaded particles It is 175keV / ⁇ m, 5 ⁇ m.
  • the total range of the two particles is about the size of a cell. Therefore, the radiation damage caused to the organism can be limited to the cell level, and it can be achieved locally without causing too much damage to normal tissues. The purpose of killing tumor cells.
  • a radiation shielding device 50 is further provided between the irradiated body 200 and the beam exit 25 to shield the radiation from the beam exiting the beam exit 25 to the normal tissue of the irradiated body. It can be understood that it may or may not be provided. Radiation shielding device 50.
  • the boron neutron capture treatment system 100 is entirely housed in a concrete structure building. Specifically, the boron neutron capture treatment system 100 further includes an irradiation chamber 101 and a charged particle beam generation chamber 102, and an irradiated body 200 on the treatment table 40.
  • the neutron beam N irradiation treatment is performed in the irradiation chamber 101.
  • the charged particle beam generating chamber 102 houses the accelerator 11.
  • the beam shaping body 20 is supported by the partition wall 103 of the irradiation chamber 101 and the charged particle beam generating chamber 102.
  • the partition wall 103 may completely separate the irradiation chamber 101 and the charged particle beam generation chamber 102; it may also be a partial partition between the irradiation chamber 101 and the charged particle beam generation chamber 102, and the irradiation chamber 101 and the charged particle beam
  • the generation chamber 102 is in communication.
  • the beam shaper 20, the collimator 30, and the treatment table 40 may be one or more; multiple treatment tables may be set in the same irradiation room, or for each treatment table Set up a separate irradiation room.
  • the irradiation chamber 101 and the charged particle beam generation chamber 102 are spaces formed by a concrete wall W (including a partition wall 103).
  • the concrete structure can shield neutrons and other radiations leaked during the working process of the boron neutron capture treatment system 100.
  • the concrete wall W includes a reinforcing part (described in detail below) at least partially inside the concrete to increase rigidity, enhance tensile strength, and improve load carrying capacity.
  • the material elastic modulus of the reinforcing part is not less than 40 GPa, and the yield strength is not less than 100 MPa.
  • the ultimate strength is not less than 200 MPa; at the same time, the material of the reinforcement part is composed of elements that have a small cross-section with neutrons or are activated by neutrons and have short half-lives (less than 1 year). Specifically, the material of the reinforcement part is 90%. (Weight percentage) or more is composed of at least one of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti.
  • the material of the reinforcing portion is at least partially an aluminum alloy, a carbon fiber composite material, a glass fiber composite material, or a combination thereof. When choosing an aluminum alloy, it can be at least partly an aluminum-magnesium alloy.
  • Aluminum has a short half-life after activation by neutrons, only 2.2 minutes; while in traditional reinforced concrete structures, iron, cobalt, nickel and other elements rich in steel are neutron
  • the half-life after activation is longer, for example, the half-life of cobalt 60 is 5.27 years; the use of aluminum-magnesium alloys significantly reduces the radioactivity derived from neutron activation in a limited time, in addition to reasonably suppressing the dose caused by secondary radiation, it is more beneficial to the future Equipment is removed.
  • Aluminum-magnesium alloys have excellent mechanical properties. It is understood that other aluminum alloys can also be selected. When selecting a carbon fiber composite material or a glass fiber composite material, it can be a carbon fiber or glass fiber and resin composite material.
  • the carbon fiber or glass fiber and resin composite material has high strength and good activation resistance. It is understandable that other composite materials can also be selected.
  • the concrete structure of the partition wall 103 is described in detail.
  • the beam shaping body 20 is supported by the partition wall 103 and a reinforcing portion provided at least partially within 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 arranged.
  • a receiving cavity 1031 is provided on the partition wall 103.
  • the beam shaping body 20 is installed in the accommodating cavity 1031, and the accommodating cavity 1031 is penetrated in the thickness direction of the partition wall 103.
  • the beam shaping body 20 is cylindrical, and the accommodating cavity 1031 is correspondingly circular. Shaped through hole. Since the beam shaping body is very sensitive to deformation, a sufficient rigidity of the supporting structure is required, and the partition wall 103 is provided with a reinforcing portion 1032 in the concrete structure.
  • the reinforcing portion 1032 includes a ring rib a surrounding the beam shaper 20 and a frame rib b surrounding the ring rib a.
  • the frame rib b includes a horizontal skeleton b1 and a vertical skeleton b2.
  • the horizontal skeleton b1 includes a horizontal longitudinal rib b11 and a hoop rib.
  • the vertical skeleton b2 includes vertical longitudinal ribs b21 and stirrups b22, and the number of horizontal / vertical longitudinal tendons and stirrups is determined according to the actual situation.
  • the reinforcement 1032 also includes horizontal and vertical distribution ribs c.
  • the horizontal and vertical distribution ribs c are distributed in the entire concrete wall at a predetermined interval in the horizontal, vertical, and thickness direction of the concrete. The spacing is determined according to the specific situation. Sexually draw.
  • the horizontal and vertical distribution ribs c pass through the frame ribs b, and the horizontal and vertical distribution ribs c that intersect with the ring ribs a overlap with them to increase anchoring performance and facilitate positioning during construction; horizontal longitudinal ribs b11 and vertical longitudinal ribs
  • An anchor plate d is provided at the end of the rib b21 to enhance the bonding strength of the horizontal longitudinal ribs b11 and the vertical longitudinal ribs b21.
  • the material of the ring rib a and the frame rib b is an aluminum-magnesium alloy or a carbon fiber resin composite material or a glass fiber resin composite material; the material of the distribution rib is also an aluminum-magnesium alloy or a carbon fiber resin composite material or a glass fiber resin composite material. It is generated in the beam shaping body. The materials around it are activated most seriously.
  • the distribution ribs can also be at least partially (such as parts other than the frame ribs) as steel bars to reduce costs. At the same time, the number of distribution ribs meets the requirements of the building structure. Yes, to reduce the production of radionuclides.
  • the distribution ribs can also be provided with tension bars (not shown) in the thickness direction of the concrete, and the number of the tension bars is determined according to the actual situation; the intersecting ribs are connected by ties such as steel wires.
  • tension bars not shown
  • tension bars such as steel wires.
  • the reinforcing portion 1032 ′ of the partition wall 103 ′ includes a ring profile a surrounding the beam shaper. 'And a frame profile b' surrounding the ring profile a ', the frame profile b' includes a horizontal frame profile beam b1 'and a vertical frame profile column b2'.
  • the reinforcing portion 1032 ' also includes horizontal and vertical distribution ribs c'. The horizontal and vertical distribution ribs c 'are distributed in the entire concrete wall at a predetermined interval in the horizontal, vertical, and thickness direction of the concrete, and the interval is determined according to specific conditions.
  • the horizontal frame profile beam b1 'and the vertical frame profile column b2' are bolted or can be connected by welding, as long as the joint connection strength is ensured; the horizontal and vertical distribution ribs c 'pass through the aluminum-magnesium alloy frame profile b 'reserved holes to strengthen the anchoring performance and ductility of the wall, horizontal and vertical distribution ribs c' intersecting with the ring profile a 'to overlap it to increase anchoring performance and facilitate its positioning during construction.
  • the distribution ribs can also be set only in areas other than the frame profile, and the distribution ribs overlap the frame profile.
  • the material of the ring profile a 'and the frame profile b' are aluminum-magnesium alloy or carbon fiber resin composite material or glass fiber resin composite material; the material of the distribution rib is also aluminum-magnesium alloy or carbon fiber resin composite material or glass fiber resin composite material. Neutrons are generated in the beam shaper, and the surrounding materials are most activated. It can be understood that the distribution ribs can also be at least partially (such as parts other than the frame profile) as reinforcement to reduce costs, and the number of distribution ribs meets the building structure. It can be required to reduce the production of radionuclides.
  • the distribution ribs can also be provided with tension bars (not shown) in the thickness direction of the concrete, and the number of the tension bars is determined according to the actual situation; the intersecting ribs are connected by ties such as steel wires.
  • ties such as steel wires.
  • the cross-sectional shape of the aluminum-magnesium alloy profile in this embodiment is an H-shape, and it can be understood that the cross-section may also be other shapes.
  • the distribution ribs of other concrete walls are first bundled and anchored with the distribution ribs of the partition wall 103 ', ring profiles, frame profiles, etc., and then the formwork of the edge of the wall (including the inner wall of the receiving cavity) is used to pour the concrete. After completion, the beam shaping body is installed in the receiving cavity of the partition wall. It can be understood that the construction process can also be performed in other manners known to those skilled in the art.
  • the compressive strength of concrete is large, but its tensile strength is low, and the strain slowly increases with time under the action of constant stress, while the tensile strength and shear strength of aluminum-magnesium alloy profiles are good, and the stiffness is large, and under the action of constant stress Strain does not increase with time, which can make up for the lack of concrete mechanical properties and material properties. Distributing reinforcing bars can prevent concrete from cracking and improve the overall performance of the wall.
  • the reinforcing portion of the partition wall may also be a combination of the above two embodiments.
  • the reinforcing portion may include a ring bar surrounding the beam shaper and a frame profile surrounding the ring shape, or a beam shape surrounding the beam shaper. Ring profile and frame ribs surrounding the ring profile.
  • the partition wall 103 '' As shown in Fig. 10-11, it is a third embodiment of the partition wall 103 ''.
  • the irradiation chamber and the charged particle beam generation chamber are vertically arranged, that is, the partition wall 103 '' is a floor (floor or ceiling).
  • the sub-generating device 10 '' further includes a beam transmission section 12 '', which transmits the charged particle lines generated by the accelerator 11 '' to the target, and a through hole 1031 '' is provided on the partition wall 103 ''.
  • the beam transmitting portion 12 '' passes through the through hole 1031 ''.
  • the reinforcing portion 1032 '' of the partition wall 103 '' includes a first reinforcing portion d and a second reinforcing portion e.
  • the first reinforcing portion d is disposed in the concrete of the partition wall 103 '', and the second reinforcing portion e at least partially protrudes out of the centrifugal portion.
  • the second reinforcing portion e includes a horizontal supporting plate e1 and a side plate e2 connecting the supporting plate e1 and the first reinforcing portion d.
  • the beam shaping body 20 '' is supported on the horizontal supporting plate e1.
  • the second reinforcing part e has a trough-shaped groove structure
  • the side plates e2 are two opposite ones
  • the material is an aluminum-magnesium alloy or a carbon fiber resin composite material or a glass fiber resin composite material, which reduces the generation of radionuclides.
  • steel can also be used; it is understood that other materials or other forms of structure can also be used.
  • a flange e11 is provided on a side of the support plate e1 facing the first reinforcing portion d.
  • the beam shaping body 20 '' is located in the flange e11, and the flange e11 limits the beam shaping body 20 '' in a horizontal direction.
  • the beam shaping body is cylindrical as a whole, and correspondingly, the flange is a ring-shaped reinforcing rib.
  • a through hole e12 is also formed on the support plate e1.
  • the neutron beam N generated by the neutron generating device 10 exits the through hole e12 through the beam shaper 20 '.
  • the through hole e12 is cut on the support plate e1. form.
  • the first reinforcing portion enhances the strength of the edge of the floor opening (through hole) on the one hand, and provides support of the beam shaping body on the other.
  • the first reinforcing part may be configured to include frame ribs / profiles and ring ribs / profiles according to the above-mentioned reinforcing parts. Because of the floor slab here, the frame ribs or frame profiles include only horizontal skeletons or horizontal frame beams, vertical The skeleton or vertical frame profile column is replaced by a horizontal skeleton or horizontal frame profile beam. The specific structure is not described in detail here, and only two profile beams are shown in the figure. When the first reinforcement part is configured as a frame profile, the side plate e2 is welded or bolted to the frame profile.
  • connection methods can also be used as long as the connection strength is ensured.
  • the side plate An e2 end is provided with an anchoring plate, which is anchored with the frame ribs.
  • the horizontal skeleton or horizontal frame profile beam connected to the side plate extends over the entire length of the floor.
  • the reinforcing portion 1032 ′ ′ is the same as the above embodiment and further includes (horizontal) distribution ribs c ′ ′, tension ribs (not shown), and the like.
  • the distribution ribs c ′ ′ are distributed in the concrete at a predetermined distance in the horizontal direction and the thickness direction of the concrete.
  • the distribution ribs of other concrete walls are bundled and anchored together with the distribution ribs of the partition wall 103 '', the frame ribs / profiles, the ring ribs / profiles, etc., and the second reinforcement part is welded or anchored to the first reinforcement part. Then form a template at the edge of the wall (including the inner wall of the through hole) to pour the concrete. After the pouring is completed, the beam shaper is inserted into the flange from the side without the side plate of the second reinforcement part, and the beam transmission part is passed through Through-hole mounting. It can be understood that the construction process can also be performed in other manners known to those skilled in the art.
  • the boron neutron capture treatment system 100 may further include a preparation room, a control room, and other spaces for auxiliary treatment.
  • Each preparation room may be provided with a preparation room for fixing the irradiated body to the treatment table and injecting boron before the irradiation treatment. Preparations for the simulation of medicines and treatment plans.
  • a connection channel is set between the preparation room and the irradiation room. After the preparation is completed, the irradiated body is directly pushed into the irradiation room or controlled by the control mechanism to automatically enter the irradiation room through the track.
  • the control room is used to control the accelerator, beam transmission department, treatment table, etc., to control and manage the entire irradiation process.
  • the management staff can also monitor multiple irradiation rooms at the same time in the control room.
  • the concrete wall in this embodiment is made of boron-containing barite concrete with a thickness of more than 1m and a density of 3g / cc.
  • the boron-containing concrete has better neutron absorption performance. In addition to enhancing the radiation shielding effect of the concrete, it can also reduce the The amount of neutron exposure to metallic materials in concrete. It can be understood that other thicknesses or densities may be used or replaced with other materials, and the thickness, density or material of the concrete wall in different parts may also be different. It can be understood that the present invention can also be applied to other types of neutron irradiation systems.

Landscapes

  • Engineering & Computer Science (AREA)
  • Architecture (AREA)
  • Health & Medical Sciences (AREA)
  • Structural Engineering (AREA)
  • Civil Engineering (AREA)
  • Biomedical Technology (AREA)
  • Veterinary Medicine (AREA)
  • Pathology (AREA)
  • General Health & Medical Sciences (AREA)
  • Public Health (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Radiology & Medical Imaging (AREA)
  • Nuclear Medicine, Radiotherapy & Molecular Imaging (AREA)
  • Animal Behavior & Ethology (AREA)
  • Chemical & Material Sciences (AREA)
  • Dispersion Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Radiation-Therapy Devices (AREA)
  • Particle Accelerators (AREA)

Abstract

本发明提供一种中子捕获治疗系统，包括中子产生装置和射束整形体，所述中子捕获治疗系统还包括容纳所述中子产生装置和射束整形体并屏蔽所述中子产生装置和射束整形体产生的辐射的混凝土壁，所述混凝土壁和至少部分设置在所述混凝土壁内的增强部用于支撑所述射束整形体，所述增强部的材料90％(重量百分比)以上由C、H、O、N、Si、Al、Mg、Li、B、Mn、Cu、Zn、S、Ca、Ti中的至少一种元素构成。本发明的中子捕获治疗系统，混凝土壁内设置的增强部抗活化性能好，相比传统的钢筋混凝土结构，进一步衰减了辐射。

Description

中子捕获治疗系统 技术领域
本发明涉及一种辐射线照射系统，尤其涉及一种中子捕获治疗系统。
背景技术
随着原子科学的发展，例如钴六十、直线加速器、电子射束等放射线治疗已成为癌症治疗的主要手段之一。然而传统光子或电子治疗受到放射线本身物理条件的限制，在杀死肿瘤细胞的同时，也会对射束途径上大量的正常组织造成伤害；另外由于肿瘤细胞对放射线敏感程度的不同，传统放射治疗对于较具抗辐射性的恶性肿瘤(如：多行性胶质母细胞瘤(glioblastoma multiforme)、黑色素细胞瘤(melanoma))的治疗成效往往不佳。
为了减少肿瘤周边正常组织的辐射伤害，化学治疗(chemotherapy)中的标靶治疗概念便被应用于放射线治疗中；而针对高抗辐射性的肿瘤细胞，目前也积极发展具有高相对生物效应(relative biological effectiveness,RBE)的辐射源，如质子治疗、重粒子治疗、中子捕获治疗等。其中，中子捕获治疗便是结合上述两种概念，如硼中子捕获治疗，借由含硼药物在肿瘤细胞的特异性集聚，配合精准的中子射束调控，提供比传统放射线更好的癌症治疗选择。
放射线治疗过程中会产生各种放射线，如硼中子捕获治疗过程产生低能至高能的中子、光子，这些放射线可能会对人体正常组织造成不同程度的损伤。因此在放射线治疗领域，如何在达到有效治疗的同时减少对外界环境、医务人员或被照射体正常组织的辐射污染是一个极为重要的课题。放射线治疗设备通常置于混凝土构造的建筑物中，隔离设备可能产生的辐射，而一般的钢筋混凝土结构，钢筋被中子活化后，会产生半衰期较长的放射性同位素，如钴60的半衰期为5.27年，形成了长衰期的放射废料，对环境及辐射安全带来负面影响。
因此，有必要提出一种新的技术方案以解决上述问题。
发明内容
为了解决上述问题，本发明一方面提供了一种中子捕获治疗系统，包括中子产生装置和射束整形体，所述中子产生装置包括加速器和靶材，所述加速器加速产生的带电粒子线与所述靶材作用产生中子线，所述射束整形体包括反射体、缓速体、热中子吸收体、辐射屏蔽体和射束出口，所述缓速体将自所述靶材产生的中子减速至超热中子能区，所述反射体包围所述缓速体并将偏离的中子导回至所述缓速体以提高超热中子射束强度，所述热中子吸收体用 于吸收热中子以避免治疗时与浅层正常组织造成过多剂量，所述辐射屏蔽体围绕所述射束出口设置在所述反射体后部用于屏蔽渗漏的中子和光子以减少非照射区的正常组织剂量，所述中子捕获治疗系统还包括容纳所述中子产生装置和射束整形体的混凝土壁，所述混凝土壁和至少部分设置在所述混凝土壁内的增强部用于支撑所述射束整形体，所述增强部的材料90％(重量百分比)以上由C、H、O、N、Si、Al、Mg、Li、B、Mn、Cu、Zn、S、Ca、Ti中的至少一种元素构成。混凝土结构可以屏蔽中子捕获治疗系统工作过程中泄露的中子及其他辐射线，增强部可以增加混凝土的刚性，提升抗拉强度，提高承载能力，增强部的材料由与中子作用截面小或被中子活化后产生的放射性同位素半衰期短的元素构成，因中子活化衍生的放射性较小，除了合理地抑制二次辐射造成的剂量，更有利于未来的设备拆除。
进一步地，所述增强部的材料弹性模量不低于40GPa，屈服强度不低于100MPa，极限强度不低于200Mpa。
进一步地，所述增强部被中子活化后产生的放射性同位素半衰期小于1年。
进一步地，所述增强部的材料至少部分为铝合金或碳纤维复合材料或玻璃纤维复合材料。铝被中子活化后半衰期较短，碳纤维复合材料或玻璃纤维复合材料抗活化性能好，相比传统的钢筋混凝土结构，在有限的时间内因中子活化衍生的放射性大幅地降低。
进一步地，所述中子捕获治疗系统还包括治疗台和准直器，所述准直器设置在所述射束出口后部以汇聚中子线，所述中子产生装置产生的中子线通过所述射束整形体和准直器照射向所述治疗台上的被照射体，所述被照射体和射束出口之间设置辐射屏蔽装置以屏蔽从所述射束出口出来的射束对被照射体正常组织的辐射。靶材可以有一个或多个，带电粒子线可选择地与其中一个或几个靶材作用或同时与多个靶材作用，以生成一个或多个治疗用中子束，与靶材的个数相应，射束整形体、准直器、治疗台也可以为一个或多个。
进一步地，所述中子捕获治疗系统还包括带电粒子束生成室和照射室，所述治疗台上的被照射体在所述照射室中进行中子线照射的治疗，所述带电粒子束生成室容纳所述加速器，所述混凝土壁包括所述带电粒子束生成室和照射室之间的分隔壁。分隔壁可以是将照射室和带电粒子束生成室完全隔开的；也可以是照射室和带电粒子束生成室之间的部分隔断，照射室和带电粒子束生成室是相通的。多个治疗台可以设置在同一个照射室内，也可以为每个治疗台设置一个单独的照射室。
作为一种优选地，所述射束整形体设置在所述分隔壁内并由所述分隔壁支撑，所述分隔壁上设置一容纳腔，所述射束整形体安装在所述容纳腔内，所述容纳腔在所述分隔壁的厚度方向是贯通的。
作为另一种优选地，所述中子产生装置还包括射束传输部，所述射束传输部将加速器产生的带电粒子线传输到所述靶材，所述分隔壁上设置一通孔，所述射束传输部穿过所述通孔，所述增强部至少部分设置在所述分隔壁内，所述射束整形体支撑在所述增强部上。
本发明另一方面提供了一种用于支撑射束整形体的支撑装置，所述射束整形体用于调整中子产生装置产生的中子线的射束品质，所述支撑装置包括容纳腔，所述射束整形体安装在所述容纳腔内，所述支撑装置还包括混凝土壁和至少部分设置在所述混凝土壁内的增强部。混凝土结构可以屏蔽工作过程中泄露的中子及其他辐射线，而射束整形体对变形非常敏感，要求支撑结构有足够大的刚度，混凝土内设置的增强部可以增加混凝土的刚性，提升抗拉强度，提高承载能力。
进一步地，所述增强部的材料弹性模量不低于40GPa，屈服强度不低于100MPa，极限强度不低于200MPa。
进一步地，所述增强部的材料90％(重量百分比)以上由C、H、O、N、Si、Al、Mg、Li、B、Mn、Cu、Zn、S、Ca、Ti中的至少一种元素构成。增强部的材料由与中子作用截面小或被中子活化后产生的放射性同位素半衰期短的元素构成，因中子活化衍生的放射性较小，除了合理地抑制二次辐射造成的剂量，更有利于未来的设备拆除。
进一步地，所述增强部被中子活化后产生的放射性同位素半衰期小于1年。
进一步地，所述容纳腔为所述混凝土壁上形成的通孔，所述增强部包括圆环、框架和分布筋，所述圆环围绕所述射束整形体设置，所述框架围绕所述圆环设置，所述分布筋在水平、竖直和混凝土的厚度方向以预定间距分布在混凝土内，所述分布筋至少部分穿过所述框架或与所述框架搭接，所述分布筋至少部分与所述圆环搭接，所述圆环和框架的材料为铝合金或碳纤维复合材料或玻璃纤维复合材料，所述分布筋的材料为钢或铝合金或碳纤维复合材料或玻璃纤维复合材料。圆环和框架增加了混凝土的刚性，提升了抗拉强度，分布筋可以防止混凝土开裂和提高墙体的整体性能。
进一步地，所述铝合金为铝镁合金，所述碳纤维复合材料为碳纤维树脂复合材料，所述玻璃纤维复合材料为玻璃纤维树脂复合材料，所述圆环为型材或由筋构造，所述框架为型材或由筋构造。所述框架为型材时，包括水平框架型材梁和竖值框架型材柱，所述水平框架型材梁和竖值框架型材柱通过螺栓连接或焊接。混凝土的抗压强度大，但其抗拉强度低，又在常应力作用下应变随时间缓慢增长，而铝镁合金型材的抗拉强度及抗剪强度好、刚度大，且在常应力作用下应变不随时间增长，碳纤维树脂复合材料或玻璃纤维树脂复合材料抗拉强度高，可弥补混凝土力学性能和材料特性的不足。所述框架由筋构造时，包括水平骨架和竖值 骨架，所述水平骨架包括水平纵筋与箍筋，所述竖值骨架包括竖直纵筋与箍筋。混凝土的抗压承载力好，铝镁合金筋抗拉承载能力好，在受拉力的部位配置铝镁合金筋可以弥补混凝土抗拉强度的不足，碳纤维树脂复合材料或玻璃纤维树脂复合材料抗拉强度高，配置箍筋可提高墙体的抗剪性能。
作为另一种优选地，所述增强部包括第一增强部和第二增强部，所述第一增强部设置在所述混凝土壁内，所述第二增强部至少部分伸出所述混凝土壁。
进一步地，所述第一增强部包括圆环、框架和分布筋，所述圆环围绕所述射束整形体设置，所述框架围绕所述圆环设置，所述分布筋在水平和混凝土的厚度方向以预定间距分布在混凝土内，所述分布筋至少部分穿过所述框架或与所述框架搭接，所述分布筋至少部分与所述圆环搭接，所述圆环和框架的材料为铝合金或碳纤维复合材料或玻璃纤维复合材料，所述分布筋的材料为钢或铝合金或碳纤维复合材料或玻璃纤维复合材料。圆环和框架增加了混凝土的刚性，提升了抗拉强度，分布筋可以防止混凝土开裂和提高墙体的整体性能。
进一步地，所述铝合金为铝镁合金，所述碳纤维复合材料为碳纤维树脂复合材料，所述玻璃纤维复合材料为玻璃纤维树脂复合材料，所述圆环为型材或由筋构造，所述框架由水平框架型材梁或水平骨架，所述水平骨架包括水平纵筋与箍筋。混凝土的抗压强度大，但其抗拉强度低，又在常应力作用下应变随时间缓慢增长，而铝镁合金型材的抗拉强度及抗剪强度好、刚度大，且在常应力作用下应变不随时间增长，铝镁合金筋抗拉承载能力好，碳纤维树脂复合材料或玻璃纤维树脂复合材料抗拉强度高，可弥补混凝土力学性能和材料特性的不足，配置箍筋可提高墙体的抗剪性能。
进一步地，所述第二增强部包括水平的支撑板和连接所述支撑板和第一增强部的侧板，所述容纳腔形成在所述支撑板上。
进一步地，所述支撑板面向所述第一增强部的一侧设置凸缘，所述凸缘形成所述容纳腔并对射束整形体在水平方向进行限位，所述支撑板上形成通孔，所述中子线经过所述射束整形体从所述通孔出来。
本发明再一方面提供了一种中子照射系统用建筑物，所述建筑物为容纳所述中子照射系统的混凝土结构，所述混凝土结构内设置增强部，所述增强部的材料90％(重量百分比)以上由C、H、O、N、Si、Al、Mg、Li、B、Mn、Cu、Zn、S、Ca、Ti中的至少一种元素构成。混凝土结构可以屏蔽中子照射系统工作过程中泄露的中子及其他辐射线，增强部可以增加混凝土的刚性，提升抗拉强度，提高承载能力，增强部的材料由与中子作用截面小或被中子活化后产生的放射性同位素半衰期短的元素构成，因中子活化衍生的放射性较小，除了合理地 抑制二次辐射造成的剂量，更有利于未来的设备拆除。
进一步地，所述增强部包括水平和/或竖直分布筋，所述水平和/或竖直分布筋在水平、竖直和所述混凝土结构的厚度方向以预定间距分布在所述混凝土结构内，分布筋可以防止混凝土开裂和提高墙体的整体性能。
进一步地，所述增强部的材料弹性模量不低于40GPa，屈服强度不低于100MPa，极限强度不低于200Mpa。
进一步地，所述增强部被中子活化后产生的放射性同位素半衰期小于1年。
进一步地，所述增强部的材料至少部分为铝合金或碳纤维复合材料或玻璃纤维复合材料。铝被中子活化后半衰期较短，碳纤维复合材料或玻璃纤维复合材料抗活化性能好，相比传统的钢筋混凝土结构，在有限的时间内因中子活化衍生的放射性大幅地降低。
进一步地，所述铝合金为铝镁合金，所述碳纤维复合材料为碳纤维树脂复合材料，所述玻璃纤维复合材料为玻璃纤维树脂复合材料，所述混凝土结构的混凝土为含硼重晶石混凝土。铝镁合金、碳纤维复合材料或玻璃纤维复合材料具有较优异的力学性能，含硼的混凝土具有更好的中子吸收性能，除了增强混凝土的辐射屏蔽效果，还可降低混凝土中金属材料受到的中子曝露量。
附图说明
图1为本发明实施例中的中子捕获治疗系统结构示意图；
图2为本发明第一实施例的中子捕获治疗系统的射束整形体的支撑结构示意图；
图3为图2在A-A剖面的示意图；
图4为图2在B-B剖面的示意图；
图5为图2在C-C剖面的示意图；
图6为本发明第二实施例的中子捕获治疗系统的射束整形体的支撑结构示意图；
图7为图6在D-D剖面的示意图；
图8为图6在E-E剖面的示意图；
图9为图6在F-F剖面的示意图；
图10为本发明第三实施例的中子捕获治疗系统的射束整形体的支撑结构示意图；
图11为图10在G-G剖面的示意图。
具体实施方式
下面结合附图对本发明的实施例做进一步的详细说明，以令本领域技术人员参照说明书文字能够据以实施。
如图1，本实施例中的中子照射系统优选为硼中子捕获治疗系统100，包括中子产生装置10、射束整形体20、准直器30和治疗台40。中子产生装置10包括加速器11和靶材T，加速器11对带电粒子(如质子、氘核等)进行加速，产生如质子线的带电粒子线P，带电粒子线P照射到靶材T并与靶材T作用产生中子线(中子束)N，靶材T优选为金属靶材。依据所需的中子产率与能量、可提供的加速带电粒子能量与电流大小、金属靶材的物化性等特性来挑选合适的核反应，常被讨论的核反应有 7Li(p,n) 7Be及 9Be(p,n) 9B，这两种反应皆为吸热反应。两种核反应的能量阈值分别为1.881MeV和2.055MeV，由于硼中子捕获治疗的理想中子源为keV能量等级的超热中子，理论上若使用能量仅稍高于阈值的质子轰击金属锂靶材，可产生相对低能的中子，不须太多的缓速处理便可用于临床，然而锂金属(Li)和铍金属(Be)两种靶材与阈值能量的质子作用截面不高，为产生足够大的中子通量，通常选用较高能量的质子来引发核反应。理想的靶材应具备高中子产率、产生的中子能量分布接近超热中子能区(将在下文详细描述)、无太多强穿辐射产生、安全便宜易于操作且耐高温等特性，但实际上并无法找到符合所有要求的核反应，本发明的实施例中采用锂金属制成的靶材。但是本领域技术人员熟知的，靶材T的材料也可以由锂、铍之外的金属材料制成，例如由钽(Ta)或钨(W)等形成；靶材T可以为圆板状，也可以为其他固体形状，也可以使用液状物(液体金属)。加速器11可以是直线加速器、回旋加速器、同步加速器、同步回旋加速器，中子产生装置10也可以是核反应堆而不采用加速器和靶材。无论硼中子捕获治疗的中子源来自核反应堆或加速器带电粒子与靶材的核反应，产生的实际上皆为混合辐射场，即射束包含了低能至高能的中子、光子。对于深部肿瘤的硼中子捕获治疗，除了超热中子外，其余的辐射线含量越多，造成正常组织非选择性剂量沉积的比例越大，因此这些会造成不必要剂量的辐射应尽量降低。另外，对于被照射体的正常组织来说，各种辐射线应避免过多，同样造成不必要的剂量沉积。
中子产生装置10产生的中子束N依次通过射束整形体20和准直器30照射向治疗台40上的被照射体200。射束整形体20能够调整中子产生装置10产生的中子束N的射束品质，准直器30用以汇聚中子束N，使中子束N在进行治疗的过程中具有较高的靶向性，通过调整准直器30能够调整射束的方向及射束与治疗台40上的被照射体200的位置关系，治疗台40及被照射体200的位置也可以进行调整，使射束对准被照射体200体内的肿瘤细胞M。这些调整可以人工手动操作的，也可以是通过一系列控制机构自动实现的。可以理解，本发明也可以不具有准直器，射束从射束整形体20出来后直接照射向治疗台40上的被照射体200。
射束整形体20进一步包括反射体21、缓速体22、热中子吸收体23、辐射屏蔽体24和射束出口25，中子产生装置10生成的中子由于能谱很广，除了超热中子满足治疗需要以外，需要尽可能的减少其他种类的中子及光子含量以避免对操作人员或被照射体造成伤害，因此从中 子产生装置10出来的中子需要经过缓速体22将其中的快中子能量(＞40keV)调整到超热中子能区(0.5eV-40keV)并尽可能减少热中子(＜0.5eV)，缓速体22由与快中子作用截面大、超热中子作用截面小的材料制成，作为一种优选实施例，缓速体13由D 2O、AlF 3、Fluental、CaF 2、Li 2CO 3、MgF 2和Al 2O 3中的至少一种制成；反射体21包围缓速体22，并将穿过缓速体22向四周扩散的中子反射回中子射束N以提高中子的利用率，由具有中子反射能力强的材料制成，作为一种优选实施例，反射体21由Pb或Ni中的至少一种制成；缓速体22后部有一个热中子吸收体23，由与热中子作用截面大的材料制成，作为一种优选实施例，热中子吸收体23由Li-6制成，热中子吸收体23用于吸收穿过缓速体22的热中子以减少中子束N中热中子的含量，避免治疗时与浅层正常组织造成过多剂量；辐射屏蔽体24围绕射束出口25设置在反射体后部，用于屏蔽从射束出口25以外部分渗漏的中子和光子，辐射屏蔽体24的材料包括光子屏蔽材料和中子屏蔽材料中的至少一种，作为一种优选实施例，辐射屏蔽体24的材料包括光子屏蔽材料铅(Pb)和中子屏蔽材料聚乙烯(PE)。准直器30设置在射束出口25后部，从准直器30出来的超热中子束向被照射体200照射，经浅层正常组织后被缓速为热中子到达肿瘤细胞M。可以理解，射束整形体20还可以有其他的构造，只要能够获得治疗所需超热中子束即可。
被照射体200服用或注射含硼(B-10)药物后，含硼药物选择性地聚集在肿瘤细胞M中，然后利用含硼(B-10)药物对热中子具有高捕获截面的特性，借由 10B(n,α) 7Li中子捕获及核分裂反应产生 4He和 7Li两个重荷电粒子。两荷电粒子的平均能量约为2.33MeV，具有高线性转移(Linear Energy Transfer,LET)、短射程特征，α短粒子的线性能量转移与射程分别为150keV/μm、8μm，而 7Li重荷粒子则为175keV/μm、5μm，两粒子的总射程约相当于一个细胞大小，因此对于生物体造成的辐射伤害能局限在细胞层级，便能在不对正常组织造成太大伤害的前提下，达到局部杀死肿瘤细胞的目的。
本实施例中，被照射体200和射束出口25之间还设置了辐射屏蔽装置50，屏蔽从射束出口25出来的射束对被照射体正常组织的辐射，可以理解，也可以不设置辐射屏蔽装置50。
硼中子捕获治疗系统100整体容纳在混凝土构造的建筑物中，具体来说，硼中子捕获治疗系统100还包括照射室101和带电粒子束生成室102，治疗台40上的被照射体200在照射室101中进行中子束N照射的治疗，带电粒子束生成室102容纳加速器11，射束整形体20由照射室101和带电粒子束生成室102的分隔壁103支撑。可以理解，分隔壁103可以是将照射室101和带电粒子束生成室102完全隔开的；也可以是照射室101和带电粒子束生成室102之间的部分隔断，照射室101和带电粒子束生成室102是相通的。靶材T可以有一个或多个，带电粒子线P可选择地与其中一个或几个靶材T作用或同时与多个靶材T作用，以生成一个或多个治疗用中子束N。与靶材T的个数相应，射束整形体20、准直器30、治疗台40也可以为一个或多个；多个治疗台 可以设置在同一个照射室内，也可以为每个治疗台设置一个单独的照射室。
照射室101和带电粒子束生成室102为混凝土壁W(包括分隔壁103)包围形成的空间，混凝土结构可以屏蔽硼中子捕获治疗系统100工作过程中泄露的中子及其他辐射线。混凝土壁W包括至少部分设置在混凝土内的增强部(下面详细介绍)以增加刚性，提升抗拉强度，提高承载能力，增强部的材料弹性模量不低于40GPa，屈服强度不低于100MPa，极限强度不低于200MPa；同时，增强部的材料由与中子作用截面小或被中子活化后产生的放射性同位素半衰期短(小于1年)的元素构成，具体的，增强部的材料90％(重量百分比)以上由C、H、O、N、Si、Al、Mg、Li、B、Mn、Cu、Zn、S、Ca、Ti中的至少一种构成。本实施例中，增强部的材料至少部分为铝合金、碳纤维复合材料、玻璃纤维复合材料或其组合。当选择铝合金时，可以至少部分为铝镁合金，铝被中子活化后半衰期较短，只有2.2分钟；而传统的钢筋混凝土结构，钢筋中富含的铁、钴、镍等元素被中子活化后半衰期较长，如钴60的半衰期为5.27年；采用铝镁合金在有限的时间内因中子活化衍生的放射性大幅地降低，除了合理地抑制二次辐射造成的剂量，更有利于未来的设备拆除。铝镁合金具有较优异的力学性能，可以理解，也可以选择其他铝合金。当选择碳纤维复合材料或玻璃纤维复合材料时，可以是碳纤维或玻璃纤维与树脂复合的材料，碳纤维或玻璃纤维与树脂复合材料强度高，抗活化性能好，可以理解，也可以选择其他复合材料。下面，详细介绍分隔壁103的混凝土结构，射束整形体20由分隔壁103及至少部分设置在分隔壁103内的增强部支撑。
继续参阅图2-图5，为分隔壁103的第一实施例，分隔壁103为侧壁，即照射室101和带电粒子束生成室102是水平布置的，分隔壁103上设置一容纳腔1031，射束整形体20安装在容纳腔1031内，容纳腔1031在分隔壁103的厚度方向是贯通的，本实施例中，射束整形体20整体为圆筒状，容纳腔1031相应的为圆形通孔。由于射束整形体对变形非常敏感，要求支撑结构有足够大的刚度，分隔壁103在混凝土结构内设置增强部1032。增强部1032包括围绕射束整形体20的圆环筋a和包围圆环筋a的框架筋b，框架筋b包括水平骨架b1和竖值骨架b2，水平骨架b1包括水平纵筋b11和箍筋b12，竖值骨架b2包括竖直纵筋b21和箍筋b22，水平/垂直纵筋和箍筋的数量根据实际情况决定。增强部1032还包括水平和竖直分布筋c，水平和竖直分布筋c在水平、竖直及混凝土的厚度方向以预定间距分布在整个混凝土壁内，间距根据具体情况确定，图中仅示意性地画出。水平和竖直分布筋c穿过框架筋b，与圆环筋a相交的水平和竖直分布筋c与其搭接以增加锚固性能和方便施工时对其定位；水平纵筋b11和竖直纵筋b21的端头设置锚固板d，以增强水平纵筋b11和竖直纵筋b21的粘结强度。除与圆环筋搭接的分布筋外，也可以仅在框架筋以外的区域设置分布筋，此时，保证分布筋与框架筋有一定的搭接长度，也可以不设置锚固板。圆环筋a和框架筋b的材料为铝镁合金或碳纤维树脂复合材料或玻璃纤维树脂复 合材料；分布筋的材料也为铝镁合金或碳纤维树脂复合材料或玻璃纤维树脂复合材料，由于中子在射束整形体中产生，在周边的材料被活化最严重，可以理解，分布筋也可以至少部分(如框架筋以外的部分)为钢筋以降低成本，同时分布筋的数量满足建筑构造要求即可，以降低放射性核素的产生。本领域技术人员熟知的，施工过程中，分布筋在混凝土厚度方向还可以设置拉筋(未示出)，拉筋的数量根据实际情况决定；相交的筋之间通过钢丝等固定件绑扎连接，如水平和竖直分布筋、水平/竖直分布筋和拉筋、水平/垂直纵筋和箍筋、圆环筋和水平/竖直分布筋之间。可以理解，在其他混凝土壁W不安装如射束整形体时，可以仅设置分布筋。施工时，先将其他混凝土壁的分布筋与分隔壁103的分布筋、圆环筋及框架筋等一起绑扎锚固好，然后搭设壁边缘(包括容纳腔内壁)的模板进行混凝土的浇筑，浇筑完成后将射束整形体安装在分隔壁的容纳腔内。可以理解，施工过程也可以按照本领域技术人员熟知的其他方式进行。混凝土的抗压承载力好，铝镁合金筋与钢筋抗拉承载能力好，在受拉力的部位配置铝镁合金筋与钢筋可以弥补混凝土抗拉强度的不足，配置箍筋可提高墙体的抗剪性能。分布钢筋可以防止混凝土开裂和提高墙体的整体性能。
如图6-图9，为分隔壁103＇的第二实施例，下面仅描述与第一实施例不同的地方，分隔壁103＇的增强部1032＇包括围绕射束整形体的圆环型材a＇和包围圆环型材a＇的框架型材b＇，框架型材b＇包括水平框架型材梁b1＇和竖值框架型材柱b2＇。增强部1032＇还包括水平和竖直分布筋c＇，水平和竖直分布筋c＇在水平、竖直及混凝土的厚度方向以预定间距分布在整个混凝土壁内，间距根据具体情况确定。水平框架型材梁b1＇和竖值框架型材柱b2＇采用螺栓连接，也可采用焊接等连接方式，只要保证接头的连接强度即可；水平和竖直分布筋c＇穿过铝镁合金框架型材b＇预留的孔，加强墙体的锚固性能与延性，与圆环型材a＇相交的水平和竖直分布筋c＇与其搭接以增加锚固性能和方便施工时对其定位。除与圆环型材相交的分布筋外，也可以仅在框架型材以外的区域设置分布筋，分布筋与框架型材搭接。圆环型材a＇和框架型材b＇的材料为铝镁合金或碳纤维树脂复合材料或玻璃纤维树脂复合材料；分布筋的材料也为铝镁合金或碳纤维树脂复合材料或玻璃纤维树脂复合材料，由于中子在射束整形体中产生，在周边的材料被活化最严重，可以理解，分布筋也可以至少部分(如框架型材以外的部分)为钢筋以降低成本，同时分布筋的数量满足建筑构造要求即可，以降低放射性核素的产生。本领域技术人员熟知的，施工过程中，分布筋在混凝土厚度方向还可以设置拉筋(未示出)，拉筋的数量根据实际情况决定；相交的筋之间通过钢丝等固定件绑扎连接，如水平和竖直分布筋、水平/竖直分布筋和拉筋、圆环型材和水平/竖直分布筋之间。本实施例中铝镁合金型材的截面形状为H型，可以理解，截面也可以为其他形状。施工时，先将其他混凝土壁的分布筋与分隔壁103＇的分布筋、圆环型材、框架型材等一起绑扎锚固好，然后搭设壁边缘(包 括容纳腔内壁)的模板进行混凝土的浇筑，浇筑完成后将射束整形体安装在分隔壁的容纳腔内。可以理解，施工过程也可以按照本领域技术人员熟知的其他方式进行。混凝土的抗压强度大，但其抗拉强度低，又在常应力作用下应变随时间缓慢增长，而铝镁合金型材的抗拉强度及抗剪强度好、刚度大，且在常应力作用下应变不随时间增长，可弥补混凝土力学性能和材料特性的不足。分布钢筋可以防止混凝土开裂和提高墙体的整体性能。
可以理解，分隔壁的增强部也可以是上面两个实施例的组合，如增强部可以包括围绕射束整形体的圆环筋和包围圆环筋的框架型材，或者是围绕射束整形体的圆环型材和包围圆环型材的框架筋。
如图10-11，为分隔壁103＇＇的第三实施例，该实施例中照射室和带电粒子束生成室是竖直布置，即分隔壁103＇＇为楼板(地板或天花板)，中子产生装置10＇＇还包括射束传输部12＇＇，射束传输部12＇＇将加速器11＇＇产生的带电粒子线传输到靶材，分隔壁103＇＇上设置一通孔1031＇＇，射束传输部12＇＇穿过通孔1031＇＇。分隔壁103＇＇的增强部1032＇＇包括第一增强部d和第二增强部e，第一增强部d设置在分隔壁103＇＇的混凝土内，第二增强部e至少部分伸出分隔壁103＇＇的混凝土，第二增强部e包括水平的支撑板e1和连接支撑板e1和第一增强部d的侧板e2，射束整形体20＇＇支撑在水平的支撑板e1上。本实施例中，第二增强部e为凵型的槽形结构，侧板e2为相对的2个，材料为铝镁合金或碳纤维树脂复合材料或玻璃纤维树脂复合材料，降低放射性核素的产生；考虑到结构钢强度高、塑性韧性好、材质均匀及可焊性好，也可以采用钢材；可以理解，也可以采用其他材料或其他形式的构造。支撑板e1面向第一增强部d的一侧设置凸缘e11，射束整形体20＇＇位于凸缘e11内，凸缘e11对射束整形体20＇＇在水平方向进行限位。本实施例中，射束整形体整体为圆柱形，对应地凸缘为圆环形的加强筋。支撑板e1上还形成通孔e12，中子产生装置10产生的中子束N经过射束整形体20＇＇从通孔e12出来，本实施例中，通孔e12通过在支撑板e1上切割形成。
第一增强部一方面增强楼板洞口(通孔)边缘的强度，另一方面提供射束整形体的支撑。第一增强部可以按照上述实施例中的增强部构造为包括框架筋/型材和圆环筋/型材，由于此处为楼板，框架筋或框架型材仅包括水平骨架或水平框架型材梁，竖直骨架或竖直框架型材柱由水平骨架或水平框架型材梁代替，具体构造在此不再详述，图中仅示意出两个型材梁。第一增强部构造为框架型材时，侧板e2与框架型材焊接或螺栓连接，可以理解，也可以采用其他连接方式，只要保证连接强度即可；第一增强部构造为框架筋时，侧板e2端部设置锚固板，与框架筋锚固。考虑到楼板及第一增强部竖直方向的受力，与侧板相连的水平骨架或水平框架型材梁在楼板的整个长度上延伸。增强部1032＇＇同上述实施例还包括(水平)分布筋c＇＇、拉筋(未示出)等，分布筋c＇＇在水平和混凝土的厚度方向以预定间距分布在混凝土内，施工 时，先将其他混凝土壁的分布筋与分隔壁103＇＇的分布筋、框架筋/型材和圆环筋/型材等一起绑扎锚固好，将第二增强部焊接或锚固到第一增强部，然后搭设壁边缘(包括通孔内壁)的模板进行混凝土的浇筑，浇筑完成后将射束整形体从第二增强部的没有侧板的一侧装入凸缘内，将射束传输部穿过通孔安装。可以理解，施工过程也可以按照本领域技术人员熟知的其他方式进行。
硼中子捕获治疗系统100还可以包括准备室、控制室和其他用于辅助治疗的空间，每一个照射室可以配置一个准备室，用于进行照射治疗前固定被照射体到治疗台、注射硼药、治疗计划模拟等准备工作，准备室和照射室之间设置连接通道，准备工作完成后直接将被照射体推入照射室或通过轨道由控制机构控制其自动进入照射室。控制室用于控制加速器、射束传输部、治疗台等，对整个照射过程进行控制和管理，管理人员在控制室内还可以同时监控多个照射室。
本实施例中的混凝土壁为厚度1m以上、密度3g/c.c.的含硼重晶石混凝土制壁，含硼的混凝土具有更好的中子吸收性能，除了增强混凝土的辐射屏蔽效果，还可降低混凝土中金属材料受到的中子曝露量。可以理解，也可以具有其他厚度或密度或替换为其他材料，不同部分的混凝土壁厚度、密度或材料也可以不同。可以理解，本发明还可以应用于其他类型的中子照射系统。
尽管上面对本发明说明性的具体实施方式进行了描述，以便于本技术领域的技术人员理解本发明，但应该清楚，本发明不限于具体实施方式的范围，对本技术领域的普通技术人员来讲，只要各种变化在所附的权利要求限定和确定的本发明的精神和范围内，这些变化是显而易见的，都在本发明要求保护的范围之内。

Claims (15)

  1. 一种中子捕获治疗系统，其特征在于，包括中子产生装置和射束整形体，所述中子产生装置包括加速器和靶材，所述加速器加速产生的带电粒子线与所述靶材作用产生中子线，所述射束整形体包括反射体、缓速体、热中子吸收体、辐射屏蔽体和射束出口，所述缓速体将自所述靶材产生的中子减速至超热中子能区，所述反射体包围所述缓速体并将偏离的中子导回至所述缓速体以提高超热中子射束强度，所述热中子吸收体用于吸收热中子以避免治疗时与浅层正常组织造成过多剂量，所述辐射屏蔽体围绕所述射束出口设置在所述反射体后部用于屏蔽渗漏的中子和光子以减少非照射区的正常组织剂量，所述中子捕获治疗系统还包括容纳所述中子产生装置和射束整形体的混凝土壁，所述混凝土壁和至少部分设置在所述混凝土壁内的增强部用于支撑所述射束整形体，所述增强部的材料90％(重量百分比)以上由C、H、O、N、Si、Al、Mg、Li、B、Mn、Cu、Zn、S、Ca、Ti中的至少一种元素构成。
  2. 如权利要求1所述的中子捕获治疗系统，其特征在于，所述增强部的材料弹性模量不低于40GPa，屈服强度不低于100MPa，极限强度不低于200Mpa，所述增强部被中子活化后产生的放射性同位素半衰期小于1年，所述增强部的材料至少部分为铝合金或碳纤维复合材料或玻璃纤维复合材料。
  3. 如权利要求1所述的中子捕获治疗系统，其特征在于，所述中子捕获治疗系统还包括治疗台和准直器，所述准直器设置在所述射束出口后部以汇聚中子线，所述中子产生装置产生的中子线通过所述射束整形体和准直器照射向所述治疗台上的被照射体，所述被照射体和射束出口之间设置辐射屏蔽装置以屏蔽从所述射束出口出来的射束对被照射体正常组织的辐射。
  4. 如权利要求3所述的所述中子捕获治疗系统，其特征在于，所述中子捕获治疗系统还包括带电粒子束生成室和照射室，所述治疗台上的被照射体在所述照射室中进行中子线照射的治疗，所述带电粒子束生成室容纳所述加速器，所述混凝土壁包括所述带电粒子束生成室和照射室之间的分隔壁。
  5. 如权利要求4所述的中子捕获治疗系统，其特征在于，所述射束整形体设置在所述分隔壁内并由所述分隔壁支撑，所述分隔壁上设置一容纳腔，所述射束整形体安装在所述容纳腔内，所述容纳腔在所述分隔壁的厚度方向是贯通的。
  6. 如权利要求4所述的中子捕获治疗系统，其特征在于，所述中子产生装置还 包括射束传输部，所述射束传输部将加速器产生的带电粒子线传输到所述靶材，所述分隔壁上设置一通孔，所述射束传输部穿过所述通孔，所述增强部至少部分设置在所述分隔壁内，所述射束整形体支撑在所述增强部上。
  7. 一种用于支撑射束整形体的支撑装置，所述射束整形体用于调整中子产生装置产生的中子线的射束品质，其特征在于，所述支撑装置包括容纳腔，所述射束整形体安装在所述容纳腔内，所述支撑装置还包括混凝土壁和至少部分设置在所述混凝土壁内的增强部。
  8. 如权利要求7所述的用于支撑射束整形体的支撑装置，其特征在于，所述增强部的材料弹性模量不低于40GPa，屈服强度不低于100MPa，极限强度不低于200MPa，所述增强部的材料90％(重量百分比)以上由C、H、O、N、Si、Al、Mg、Li、B、Mn、Cu、Zn、S、Ca、Ti中的至少一种元素构成，所述增强部被中子活化后产生的放射性同位素半衰期小于1年。
  9. 如权利要求7所述的用于支撑射束整形体的支撑装置，其特征在于，所述容纳腔为所述混凝土壁上形成的通孔，所述增强部包括圆环、框架和分布筋，所述圆环围绕所述射束整形体设置，所述框架围绕所述圆环设置，所述分布筋在水平、竖直和混凝土的厚度方向以预定间距分布在混凝土内，所述分布筋至少部分穿过所述框架或与所述框架搭接，所述分布筋至少部分与所述圆环搭接，所述圆环和框架的材料为铝合金或碳纤维复合材料或玻璃纤维复合材料，所述分布筋的材料为钢或铝合金或碳纤维复合材料或玻璃纤维复合材料。
  10. 如权利要求9所述的用于支撑射束整形体的支撑装置，其特征在于，所述圆环为型材或由筋构造，所述框架为型材，所述框架包括水平框架型材梁和竖值框架型材柱，所述水平框架型材梁和竖值框架型材柱通过螺栓连接或焊接。
  11. 如权利要求9所述的用于支撑射束整形体的支撑装置，其特征在于，所述圆环为型材或由筋构造，所述框架由筋构造，所述框架包括水平骨架和竖值骨架，所述水平骨架包括水平纵筋与箍筋，所述竖值骨架包括竖直纵筋与箍筋。
  12. 如权利要求7所述的用于支撑射束整形体的支撑装置，其特征在于，所述增强部包括第一增强部和第二增强部，所述第一增强部设置在所述混凝土壁 内，所述第二增强部至少部分伸出所述混凝土壁。
  13. 如权利要求12所述的用于支撑射束整形体的支撑装置，其特征在于，所述第一增强部包括圆环、框架和分布筋，所述圆环围绕所述射束整形体设置，所述框架围绕所述圆环设置，所述分布筋在水平和混凝土的厚度方向以预定间距分布在混凝土内，所述分布筋至少部分穿过所述框架或与所述框架搭接，所述分布筋至少部分与所述圆环搭接，所述圆环和框架的材料为铝合金或碳纤维复合材料或玻璃纤维复合材料，所述分布筋的材料为钢或铝合金或碳纤维复合材料或玻璃纤维复合材料，所述圆环为型材或由筋构造，所述框架由水平框架型材梁或水平骨架构造，所述水平骨架包括水平纵筋与箍筋。
  14. 如权利要求12所述的用于支撑射束整形体的支撑装置，其特征在于，所述第二增强部包括水平的支撑板和连接所述支撑板和第一增强部的侧板，所述容纳腔形成在所述支撑板上，所述支撑板面向所述第一增强部的一侧设置凸缘，所述凸缘形成所述容纳腔并对射束整形体在水平方向进行限位，所述支撑板上形成通孔，所述中子线经过所述射束整形体从所述通孔出来。
  15. 如权利要求9或13所述的用于支撑射束整形体的支撑装置，其特征在于，所述铝合金为铝镁合金，所述碳纤维复合材料为碳纤维树脂复合材料，所述玻璃纤维复合材料为玻璃纤维树脂复合材料。
PCT/CN2019/087928 2018-08-31 2019-05-22 中子捕获治疗系统 WO2020042681A1 (zh)

Priority Applications (6)

Application Number Priority Date Filing Date Title
EP22178803.7A EP4082610B1 (en) 2018-08-31 2019-05-22 Neutron capture therapy system
EP19855979.1A EP3845273B1 (en) 2018-08-31 2019-05-22 Neutron capture treatment system
JP2021520262A JP7101312B2 (ja) 2018-08-31 2019-05-22 中性子捕捉療法システム
US17/145,562 US20210146163A1 (en) 2018-08-31 2021-01-11 Neutron capture therapy system
JP2022107475A JP2022133372A (ja) 2018-08-31 2022-07-04 中性子捕捉療法システム
JP2024039529A JP2024079718A (ja) 2018-08-31 2024-03-14 中性子捕捉療法システム

Applications Claiming Priority (4)

Application Number Priority Date Filing Date Title
CN201811014166.3 2018-08-31
CN201811011377 2018-08-31
CN201811014166 2018-08-31
CN201811011377.1 2018-08-31

Related Child Applications (1)

Application Number Title Priority Date Filing Date
US17/145,562 Continuation US20210146163A1 (en) 2018-08-31 2021-01-11 Neutron capture therapy system

Publications (1)

Publication Number Publication Date
WO2020042681A1 true WO2020042681A1 (zh) 2020-03-05

Family

ID=69642671

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/CN2019/087928 WO2020042681A1 (zh) 2018-08-31 2019-05-22 中子捕获治疗系统

Country Status (4)

Country Link
US (1) US20210146163A1 (zh)
EP (2) EP4082610B1 (zh)
JP (3) JP7101312B2 (zh)
WO (1) WO2020042681A1 (zh)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP3943153A4 (en) * 2019-03-18 2022-05-04 Neuboron Therapy System Ltd. NEUTRON COLLECTION TREATMENT SYSTEM

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP7101312B2 (ja) * 2018-08-31 2022-07-14 中硼（厦▲門▼）医▲療▼器械有限公司 中性子捕捉療法システム
CA3217564A1 (en) * 2019-04-17 2020-10-22 Neuboron Therapy System Ltd. Neutron capture therapy system
CN113808772A (zh) * 2021-09-10 2021-12-17 中山大学 一种中子慢化材料
CN115120895A (zh) * 2022-08-31 2022-09-30 兰州大学 一种中子俘获辐照设备

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101529530A (zh) * 2006-10-16 2009-09-09 三菱重工业株式会社 中子减速器和中子照射方法以及危险物质检测装置
CN102695544A (zh) * 2009-10-23 2012-09-26 离子束应用公司 用于粒子治疗的包括束分析仪的机架
US9486646B2 (en) * 2014-08-29 2016-11-08 Wisconsin Alumni Research Foundation System and method for control of external beam radiation
CN106211727A (zh) * 2016-07-01 2016-12-07 中国工程物理研究院流体物理研究所 屏蔽体及屏蔽装置
CN206835439U (zh) * 2017-05-26 2018-01-02 南京中硼联康医疗科技有限公司 用于中子线产生装置的靶材及中子捕获治疗系统

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH01147399A (ja) * 1987-12-02 1989-06-09 Kuraray Co Ltd 繊維強化中性子遮蔽モルタルコンクリート
JP5996456B2 (ja) 2013-02-27 2016-09-21 住友重機械工業株式会社 中性子捕捉療法システム
JP6223882B2 (ja) * 2014-03-18 2017-11-01 住友重機械工業株式会社 中性子捕捉療法システム
JP6439092B2 (ja) * 2015-08-25 2018-12-19 住友重機械工業株式会社 中性子捕捉療法システム
JP2017176357A (ja) 2016-03-29 2017-10-05 住友重機械工業株式会社 中性子捕捉療法施設
CN106351474A (zh) * 2016-11-08 2017-01-25 北京凯佰特科技股份有限公司 医院中子照射治疗用建筑物及其照射室
RU2727576C1 (ru) * 2016-12-23 2020-07-22 Нойборон Медтех Лтд. Система нейтронозахватной терапии и мишень для устройства генерации пучка частиц
JP7101312B2 (ja) * 2018-08-31 2022-07-14 中硼（厦▲門▼）医▲療▼器械有限公司 中性子捕捉療法システム

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101529530A (zh) * 2006-10-16 2009-09-09 三菱重工业株式会社 中子减速器和中子照射方法以及危险物质检测装置
CN102695544A (zh) * 2009-10-23 2012-09-26 离子束应用公司 用于粒子治疗的包括束分析仪的机架
US9486646B2 (en) * 2014-08-29 2016-11-08 Wisconsin Alumni Research Foundation System and method for control of external beam radiation
CN106211727A (zh) * 2016-07-01 2016-12-07 中国工程物理研究院流体物理研究所 屏蔽体及屏蔽装置
CN206835439U (zh) * 2017-05-26 2018-01-02 南京中硼联康医疗科技有限公司 用于中子线产生装置的靶材及中子捕获治疗系统

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP3943153A4 (en) * 2019-03-18 2022-05-04 Neuboron Therapy System Ltd. NEUTRON COLLECTION TREATMENT SYSTEM
US11826583B2 (en) 2019-03-18 2023-11-28 Neuboron Therapy System Ltd. Neutron capture therapy system

Also Published As

Publication number Publication date
JP2021528213A (ja) 2021-10-21
US20210146163A1 (en) 2021-05-20
JP2022133372A (ja) 2022-09-13
EP3845273A4 (en) 2021-10-27
EP4082610B1 (en) 2023-09-20
EP3845273B1 (en) 2022-08-10
JP2024079718A (ja) 2024-06-11
EP4082610A1 (en) 2022-11-02
JP7101312B2 (ja) 2022-07-14
EP3845273A1 (en) 2021-07-07

Similar Documents

Publication Publication Date Title
WO2020042681A1 (zh) 中子捕获治疗系统
TWI734408B (zh) 中子捕獲治療系統
US12023524B2 (en) Neutron capture therapy system comprising a beam-shaping assembly having a moderator and a frame accommodating the moderator
US11583702B2 (en) Neutron capture therapy system
CN210728446U (zh) 中子捕获治疗系统
CN211410738U (zh) 中子捕获治疗系统
CN110870950A (zh) 中子捕获治疗系统
CN210302075U (zh) 中子捕获治疗系统及用于支撑射束整形体的支撑模块
CN219481344U (zh) 中子捕获治疗系统
RU2776333C1 (ru) Система нейтронозахватной терапии
CN110870951A (zh) 中子捕获治疗系统
RU2781650C1 (ru) Система нейтрон-захватной терапии
CN112755406A (zh) 中子捕获治疗系统及其射束整形体安装方法

Legal Events

Date Code Title Description
121 Ep: the epo has been informed by wipo that ep was designated in this application

Ref document number: 19855979

Country of ref document: EP

Kind code of ref document: A1

ENP Entry into the national phase

Ref document number: 2021520262

Country of ref document: JP

Kind code of ref document: A

NENP Non-entry into the national phase

Ref country code: DE

ENP Entry into the national phase

Ref document number: 2019855979

Country of ref document: EP

Effective date: 20210331