CN204319540U - For the beam-shaping body of neutron capture treatment - Google Patents
For the beam-shaping body of neutron capture treatment Download PDFInfo
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- CN204319540U CN204319540U CN201420765424.2U CN201420765424U CN204319540U CN 204319540 U CN204319540 U CN 204319540U CN 201420765424 U CN201420765424 U CN 201420765424U CN 204319540 U CN204319540 U CN 204319540U
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Abstract
Flux and the quality in source is penetrated in order to improve neutron, an aspect of the present utility model provides a kind of beam-shaping body for neutron capture treatment, wherein, beam-shaping body comprises target, adjoin the slow body with target, be enclosed in reflector external slowly, the thermal neutron absorber adjacent with slow body, be arranged on the radiation shield in beam-shaping body and beam outlet, target and the proton beam generation nuclear reaction from the incidence of beam entrance are to produce neutron, neutron forms neutron beam, neutron beam limits a main shaft, slow body by the neutron degradation that produces from target to epithermal neutron energy district, the neutron departing from main shaft is led back to main shaft to improve epithermal neutron intensity of beam by reflector, clearance channel is set between slow body and reflector to improve epithermal neutron flux, thermal neutron absorber for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, radiation shield is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district.
Description
Technical field
This utility model relates to a kind of beam-shaping body, particularly relates to a kind of beam-shaping body for neutron capture treatment.
Background technology
Along with the development of atomics, radiation cure one of the Main Means becoming treatment of cancer such as such as cobalt 60, linear accelerator, electron beam.But conventional photonic or electronic therapy are subject to the restriction of the physical condition of lonizing radiation own, while killing tumor cell, also can normal structures a large amount of in beam approach be damaged; In addition because tumor cell is to the difference of lonizing radiation sensitivity, traditional radiation therapy is often not good for the treatment effect of the malignant tumor (as: multirow glioblastoma multiforme (glioblastoma multiforme), melanocytoma (melanoma)) compared with tool radiation resistance.
In order to reduce the radiation injury of tumor surrounding normal tissue, the target therapy concept in chemotherapy (chemotherapy) is just applied in radiation cure; And for the tumor cell of radiation resistance, also develop actively has the radiation source of high relative biological effect (relative biological effectiveness, RBE) at present, as proton therapeutic, heavy particle therapy, neutron capture treatment etc.Wherein, neutron capture treatment is in conjunction with above-mentioned two conceptions of species, as the treatment of boron neutron capture, gathers by the specificity of boracic medicine at tumor cell, coordinates neutron beam regulation and control accurately, provides and selects than the better treatment of cancer of conventional radiation.
Boron neutron capture treatment (Boron Neutron Capture Therapy, BNCT) be utilize boracic (
10b) medicine has the characteristic of high capture cross section to thermal neutron, by
10b (n, α)
7li neutron capture and karyokinesis reaction produce
4he and
7li two heavy burden charged particle.See figures.1.and.2, which respectively show boron neutron capture reaction schematic diagram and
10b (n, α)
7li neutron capture nuclear equation formula, the average energy of two charged particles is about 2.33MeV, has High Linear transfer (Linear Energy Transfer, LET), short range feature, the linear energy transfer of alpha-particle and range are respectively 150 keV/ μm, 8 μm, and
7li heavy burden particle is then 175 keV/ μm, 5 μm, the integrated range of two particle is about equivalent to a cell size, therefore the radiation injury caused for organism can be confined to cell level, when boracic drug selectivity be gathered in tumor cell, suitable neutron of arranging in pairs or groups penetrates source, just under normal tissue does not cause the prerequisite of too major injury, the object that tumor cell is killed in local can be reached.
Because the effect of boron neutron capture treatment depends on tumor cell position boracic drug level and thermal neutron quantity, therefore the binary lonizing radiation treatment of cancer that is otherwise known as (binary cancer therapy); It can thus be appreciated that, except the exploitation of boracic medicine, in the research that the neutron improvement of penetrating source flux and quality is treated at boron neutron capture, occupy key player.
Utility model content
Flux and the quality in source is penetrated in order to improve neutron, an aspect of the present utility model provides a kind of beam-shaping body for neutron capture treatment, wherein, beam-shaping body comprises target, be adjacent to the slow body of target, be enclosed in reflector external slowly, the thermal neutron absorber adjacent with slow body, be arranged on the radiation shield in beam-shaping body and beam outlet, target and the proton beam generation nuclear reaction from the incidence of beam entrance are to produce neutron, neutron forms neutron beam, neutron beam limits a main shaft, slow body by the neutron degradation that produces from target to epithermal neutron energy district, the neutron departing from main shaft is led back to main shaft to improve epithermal neutron intensity of beam by reflector, clearance channel is set between slow body and reflector to improve epithermal neutron flux, thermal neutron absorber for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, radiation shield is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district.
Beam-shaping body is further used for the treatment of accelerator boron neutron capture.
Proton beam is accelerated by accelerator by the treatment of accelerator boron neutron capture, and target is made of metal, and proton beam accelerates to the energy being enough to overcome target atom core coulomb repulsion, with target generation nuclear reaction to produce neutron.
Beam-shaping physical ability by neutron slowly to epithermal neutron energy district, and reduce thermal neutron and fast neutron content, epithermal neutron energy district is between 0.5eV to 40keV, hanker subzone and be less than 0.5eV, fast-neutron range is greater than 40keV, slow body is made by having the material that fast neutron action section is large, epithermal neutron action section is little, and reflector is made up of the material having neutron reflection ability strong, and thermal neutron absorber is made up of the material large with thermal neutron action section.
As one preferably, slow body is by D
2o, AlF
3, Fluental
tM, CaF
2, Li
2cO
3, MgF
2and Al
2o
3in at least one make.
Further, reflector is made up of at least one in Pb or Ni, thermal neutron absorber by
6li makes, and is provided with air duct between thermal neutron absorber and beam outlet.
Radiation shield comprises photon shielding and neutron shield.As one preferably, photon shielding is made up of Pb, and neutron shield is by PE(polyethylene) make.
As one preferably, slow body be arranged to comprise a bar shape and a pyramidal shape adjoining with bar shape or be arranged to that two rightabouts adjoin each other cone-shaped.
" cylinder " or " bar shape " described in this utility model embodiment refers to the structure substantially constant to the overall trend of its outline of opposite side along the side of direction as shown, a wherein contour line of outline can be line segment, as the contour line of the correspondence of cylindrical shape, also can be the circular arc close to line segment that curvature is larger, the contour line of the correspondence of sphere body shape as larger in curvature, the whole surface of outline can be rounding off, also can be non-rounding off, as done a lot of projection and groove on the surface of cylindrical shape or the larger sphere body shape of curvature.
" cone " or " cone-shaped " described in this utility model embodiment refers to the structure diminished gradually along the side of direction as shown to the overall trend of its outline of opposite side, a wherein contour line of outline can be line segment, as the contour line of the correspondence of cone shape, also can be circular arc, as the contour line of the correspondence of sphere body shape, the whole surface of outline can be rounding off, also can be non-rounding off, as done a lot of projection and groove on the surface of cone shape or sphere body shape.
Accompanying drawing explanation
Fig. 1 is boron neutron capture reaction schematic diagram.
Fig. 2 is
10b (n, α)
7li neutron capture nuclear equation formula.
Fig. 3 is the floor map of the beam-shaping body for neutron capture treatment in this utility model first embodiment, wherein, between slow body and reflector, is provided with clearance channel.
Fig. 4 is the floor map of the beam-shaping body for neutron capture treatment in this utility model second embodiment, and wherein, slow body is arranged to bicone, and the clearance channel position in the first embodiment is filled with slow body material.
Fig. 5 is the floor map of the beam-shaping body for neutron capture treatment in this utility model the 3rd embodiment, and wherein, slow body is arranged to bicone, and the clearance channel position in the first embodiment is filled with reflector material.
Fig. 6 is the neutron yield rate figure of the two differential of neutron energy and neutron angle.
Fig. 7 is the floor map of the beam-shaping body for neutron capture treatment in this utility model the 4th embodiment, and wherein, slow body is arranged to cylinder.
Fig. 8 is the floor map of the beam-shaping body for neutron capture treatment in this utility model the 5th embodiment, and wherein, slow body is arranged to cylinder+cone.
Detailed description of the invention
Neutron capture treatment increases gradually as a kind of means application in recent years of effective Therapeutic cancer, wherein common with the treatment of boron neutron capture, and the neutron of supply boron neutron capture treatment can by nuclear reactor or accelerator supply.Embodiment of the present utility model is treated for accelerator boron neutron capture, the basic module of accelerator boron neutron capture treatment generally includes accelerator, target and hot removal system for accelerating charged particle (as proton, deuteron etc.) and beam-shaping body, wherein accelerating charged particles and metal targets effect produce neutron, the characteristic such as materialization according to required neutron yield rate and energy, available accelerating charged particles energy and size of current, metal targets selects suitable nuclear reaction, and the nuclear reaction often come into question has
7li (p, n)
7be and
9be (p, n)
9b, these two kinds of reactions are all the endothermic reaction.The energy threshold of two kinds of nuclear reactions is respectively 1.881MeV and 2.055MeV, desirable neutron source due to the treatment of boron neutron capture is the epithermal neutron of keV energy grade, if use the proton bombardment lithium metal target of energy only a little higher than threshold values in theory, the neutron of relative mental retardation can be produced, slow process that must be not too many just can be used for clinical, but the proton-effect cross section of lithium metal (Li) and beryllium metal (Be) two kinds of targets and threshold values energy is not high, for producing enough large neutron flux, the proton of higher-energy is usually selected to carry out initiated core reaction.
Desirable target should possess high neutron yield rate, generation neutron energy distribution close to epithermal neutron energy district (will be described in more detail below), without wearing by force too much that radiation produces, safety is cheaply easy to operation and the characteristic such as high temperature resistant, but in fact also cannot find the nuclear reaction meeting all requirements, in embodiment of the present utility model, adopt the metal target of lithium.But well known to those skilled in the art, the material of target also can be made up of other metal materials except the above-mentioned metal material talked about.
Requirement for hot removal system is then different according to the nuclear reaction selected, as
7li (p, n)
7be because of the fusing point of metal targets (lithium metal) and thermal conductivity coefficient poor, to the requirement of hot removal system just comparatively
9be (p, n)
9b is high.Adopt in embodiment of the present utility model
7li (p, n)
7the nuclear reaction of Be.
No matter the neutron source of boron neutron capture treatment is from the nuclear reaction of nuclear reactor or accelerator charged particle and target, generation be all mixed radiation field, namely beam contains neutron, the photon of mental retardation to high energy; Boron neutron capture for deep tumor is treated, and except epithermal neutron, remaining radiation content is more, and the ratio causing the non-selective dosage of normal structure to deposit is larger, and therefore these can cause the radiation of unnecessary dosage to reduce as far as possible.Except air beam quality factor, for more understanding the dose distribution that neutron causes in human body, use human body head tissue prosthese to carry out Rapid Dose Calculation in embodiment of the present utility model, and be used as the design reference of neutron beam with prosthese beam quality factor, will be described in more detail below.
The neutron source that International Atomic Energy Agency (IAEA) treats for clinical boron neutron capture, given five air beam quality factors suggestion, these five suggestions can be used for the quality of more different neutron source, and be provided with as select neutron the way of production, design beam-shaping body time reference frame.These five suggestions are as follows respectively:
Epithermal neutron beam flux Epithermal neutron flux > 1 x 10
9n/cm
2s
Fast neutron pollutes Fast neutron contamination < 2 x 10
-13gy-cm
2/ n
Photon contamination Photon contamination < 2 x 10
-13gy-cm
2/ n
Thermal and epithermal neutron flux ratio thermal to epithermal neutron flux ratio < 0.05
Middle electron current and flux ratio epithermal neutron current to flux ratio > 0.7
Note: epithermal neutron energy district is between 0.5eV to 40keV, and hanker subzone and be less than 0.5eV, fast-neutron range is greater than 40keV.
1, epithermal neutron beam flux:
In neutron beam flux and tumor, boracic drug level determines the clinical treatment time jointly.If tumor boracic drug level is enough high, the requirement for neutron beam flux just can reduce; Otherwise, if boracic drug level is low in tumor, then need high flux epithermal neutron to give tumor enough dosage.The epithermal neutron number that IAEA is every square centimeter per second for the requirement of epithermal neutron beam flux is greater than 10
9, the neutron beam under this flux roughly can control treatment time in one hour for current boracic medicine, and short treatment time, except having superiority to patient location and comfort level, also more effectively can utilize the holdup time that boracic medicine is limited in tumor.
2, fast neutron pollutes:
Because fast neutron can cause unnecessary normal tissue dose, what therefore look is pollution, and this dosage size and neutron energy are proportionate, and therefore should reduce the content of fast neutron in neutron beam design as far as possible.Fast neutron pollutes and is defined as the adjoint fast neutron dosage of unit epithermal neutron flux, and the suggestion that IAEA pollutes fast neutron is for being less than 2 x 10
-13gy-cm
2/ n.
3, photon contamination (gamma-ray contamination):
Gamma-rays belongs to wears radiation by force, non-selectively can cause the organized dosage deposition of institute on course of the beam, therefore the exclusive requirement that gamma-rays content is also neutron beam design is reduced, gamma-ray contamination is defined as the adjoint gamma-rays dosage of unit epithermal neutron flux, IAEA to the suggestion of gamma-ray contamination for being less than 2 x 10
-13gy-cm
2/ n.
4, thermal and epithermal neutron flux ratio:
Because thermal neutron decay speed is fast, penetration capacity is poor, after entering human body, most of energy deposition is at skin histology, except the neutron source that the Several Epidermal Tumors such as melanocytoma need be treated as boron neutron capture with thermal neutron, thermal neutron content should be reduced for deep tumor such as cerebromas.IAEA advises as being less than 0.05 thermal and epithermal neutron flux ratio.
5, middle electron current and flux ratio:
Middle electron current and flux ratio represent the directivity of beam, and before ratio larger expression neutron beam, tropism is good, and before high, the neutron beam of tropism can reduce because neutron disperses the normal surrounding tissue dosage caused, and also improve in addition and can treat the degree of depth and pendulum pose gesture elasticity.IAEA centering electron current and flux ratio are advised as being greater than 0.7.
Utilize prosthese to obtain in-house dose distribution, according to the dose versus depth curve of normal structure and tumor, push away to obtain prosthese beam quality factor.Following three parameters can be used for the comparison carrying out different neutron beam treatment benefit.
1, effective therapeutic depth:
Tumor dose equals the degree of depth of normal structure maximal dose, the position after this degree of depth, and the dosage that tumor cell obtains is less than normal structure maximal dose, namely loses the advantage of boron neutron capture.This parameter represents the penetration capacity of neutron beam, and the medicable tumor depth of the larger expression of effective therapeutic depth is darker, and unit is cm.
2, effective therapeutic depth close rate:
The i.e. tumor dose rate of effective therapeutic depth, also equals the maximum dose rate of normal structure.Because normal structure reception accumulated dose is the factor that impact can give tumor accumulated dose size, the therefore length of parameter influence treatment time, the irradiation time that the larger expression of effective therapeutic depth close rate gives needed for tumor doses is shorter, and unit is cGy/mA-min.
3, dose therapeutically effective ratio:
From brain surface to effective therapeutic depth, the mean dose ratio that tumor and normal structure receive, is referred to as dose therapeutically effective ratio; The calculating of mean dose, can be obtained by dose versus depth curvilinear integral.Dose therapeutically effective ratio is larger, and the treatment benefit representing this neutron beam is better.
Have in design to make beam-shaping body and compare foundation, except beam quality factor and above-mentioned three parameters in the air of five IAEA suggestions, in this utility model embodiment, also utilize the following parameter good and bad for assessment of the performance of neutron beam dosage:
1, the proton electric current that irradiation time≤30min(accelerator uses is 10mA)
2,30.0RBE-Gy can treat the degree of depth >=7cm
3, tumor maximal dose >=60.0RBE-Gy
4, normal cerebral tissue maximal dose≤12.5RBE-Gy
5, skin maximal dose≤11.0RBE-Gy
Note: RBE(Relative Biological Effectiveness) be relative biological effect, the biological effect that can cause due to photon, neutron is different, so dosage item is as above multiplied by the relative biological effect of different tissues respectively in the hope of dose,equivalent.
Penetrate flux and the quality in source to improve neutron, embodiment of the present utility model is the improvement proposed for the beam-shaping body for the treatment of for neutron capture, as one preferably, is the improvement for the beam-shaping body for the treatment of for accelerator boron neutron capture.As shown in Figure 3, the beam-shaping body 10 for neutron capture treatment in this utility model first embodiment, it comprises beam entrance 11, target 12, adjoin the slow body 13 with target 12, be enclosed in the reflector 14 outside slow body 13, the thermal neutron absorber 15 adjacent with slow body 13, be arranged on the radiation shield 16 in beam-shaping body 10 and beam outlet 17, target 12 and the proton beam generation nuclear reaction from beam entrance 11 incidence are to produce neutron, neutron forms neutron beam, neutron beam limits a major axis X, slow body 13 by the neutron degradation that produces from target 12 to epithermal neutron energy district, the neutron departing from major axis X is led back to major axis X to improve epithermal neutron intensity of beam by reflector 14, clearance channel 18 is set between slow body 13 and reflector 14 to improve epithermal neutron flux, thermal neutron absorber 15 for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, radiation shield 16 is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district.
Proton beam is accelerated by accelerator by the treatment of accelerator boron neutron capture, and as a kind of preferred embodiment, target 12 is made up of lithium metal, and proton beam accelerates to the energy being enough to overcome target atom core coulomb repulsion, occurs with target 12
7li (p, n)
7be nuclear reaction is to produce neutron.Beam-shaping body 10 by neutron slowly to epithermal neutron energy district, and can reduce thermal neutron and fast neutron content, and slow body 13 is made by having the material that fast neutron action section is large, epithermal neutron action section is little, and as a kind of preferred embodiment, slow body 13 is by D
2o, AlF
3, Fluental
tM, CaF
2, Li
2cO
3, MgF
2and Al
2o
3in at least one make.Reflector 14 is made up of the material having neutron reflection ability strong, and as a kind of preferred embodiment, reflector 14 is made up of at least one in Pb or Ni.Thermal neutron absorber 15 is made up of the material large with thermal neutron action section, as a kind of preferred embodiment, thermal neutron absorber 15 by
6li makes, and is provided with air duct 19 between thermal neutron absorber 15 and beam outlet 17.Radiation shield 16 comprises photon shielding 161 and neutron shield 162, and as a kind of preferred embodiment, radiation shield 16 comprises the photon shielding 161 of being made up of plumbous (Pb) and the neutron shield 162 of being made up of polyethylene (PE).
Wherein, it is cone-shaped that slow body 13 is arranged to that two rightabouts adjoin each other, direction as shown in Figure 3, and the left side of slow body 13 is diminish gradually towards left side cone-shaped, the right side of slow body 13 is diminish gradually towards right side cone-shaped, and both adjoin each other.As one preferably, it is cone-shaped that the left side of slow body 13 is set to diminish gradually towards left side, and its allothimorph shape also can be arranged in right side and this cone-shapedly adjoins each other, as bar shape etc.Reflector 14 is enclosed in around slow body 13 closely, clearance channel 18 is provided with between slow body 13 and reflector 14, so-called clearance channel 18 refers to the region easily allowing neutron beam pass through of the sky do not covered with solid material, as this clearance channel 18 can be set to air duct or vacuum passage.Be close to the thermal neutron absorber 15 of slow body 13 setting by very thin one deck
6li material is made, and the photon be made up of the Pb shielding 161 in radiation shield 16 can be set to one with reflector 14, also can be arranged to split, and the neutron shield 162 of being made up of PE in radiation shield 16 can be arranged on the position of contiguous beam outlet 17.Between thermal neutron absorber 15 and beam outlet 17, be provided with air duct 19, in this region, the sustainable major axis X that led back to by the neutron departing from major axis X is to improve epithermal neutron intensity of beam.Prosthese B is arranged on distance beam outlet 17 about 1cm places.Well known to those skilled in the art, photon shielding 161 can be made up of other materials, as long as play the effect of shielding photon, neutron shield 162 also can be made up of other materials, also can be arranged on other local, as long as the condition of shielding seepage neutron can be met.
In order to compare the difference of the beam-shaping body being provided with clearance channel and the beam-shaping body not arranging clearance channel, as shown in Figure 4 and Figure 5, which respectively show the second embodiment adopting slow body to fill clearance channel and the 3rd embodiment adopting reflector to fill clearance channel.First with reference to Fig. 4, this beam-shaping body 20 comprises beam entrance 21, target 22, adjoin the slow body 23 with target 22, be enclosed in the reflector 24 outside slow body 23, the thermal neutron absorber 25 adjacent with slow body 23, be arranged on the radiation shield 26 in beam-shaping body 20 and beam outlet 27, target 22 and the proton beam generation nuclear reaction from beam entrance 21 incidence are to produce neutron, neutron forms neutron beam, neutron beam limits a major axis X 1, slow body 23 by the neutron degradation that produces from target 22 to epithermal neutron energy district, the neutron departing from major axis X 1 is led back to major axis X 1 to improve epithermal neutron intensity of beam by reflector 24, it is cone-shaped that slow body 23 is arranged to that two rightabouts adjoin each other, the left side of slow body 23 is diminish gradually towards left side cone-shaped, the right side of slow body 23 is diminish gradually towards right side cone-shaped, both adjoin each other, thermal neutron absorber 25 for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, radiation shield 26 is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district.
As one preferably, target 22 in second embodiment, slow body 23, reflector 24, thermal neutron absorber 25 and radiation shield 26 can identical with the first embodiment, and radiation shield 26 wherein comprises the photon shielding 261 of being made up of plumbous (Pb) and the neutron shield 262 of being made up of polyethylene (PE), this neutron shield 262 can be arranged on beam and export 27 places.Air duct 28 is provided with between thermal neutron absorber 25 and beam outlet 27.Prosthese B1 is arranged on distance beam outlet 27 about 1cm places.
Please refer to Fig. 5, this beam-shaping body 30 comprises beam entrance 31, target 32, adjoin the slow body 33 with target 32, be enclosed in the reflector 34 outside slow body 33, the thermal neutron absorber 35 adjacent with slow body 33, be arranged on the radiation shield 36 in beam-shaping body 30 and beam outlet 37, target 32 and the proton beam generation nuclear reaction from beam entrance 31 incidence are to produce neutron, neutron forms neutron beam, neutron beam limits a major axis X 2, slow body 33 by the neutron degradation that produces from target 32 to epithermal neutron energy district, the neutron departing from major axis X 2 is led back to major axis X 2 to improve epithermal neutron intensity of beam by reflector 34, it is cone-shaped that slow body 33 is arranged to that two rightabouts adjoin each other, the left side of slow body 33 is diminish gradually towards left side cone-shaped, the right side of slow body 33 is diminish gradually towards right side cone-shaped, both adjoin each other, thermal neutron absorber 35 for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, radiation shield 36 is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district.
As one preferably, target 32 in 3rd embodiment, slow body 33, reflector 34, thermal neutron absorber 35 and radiation shield 36 can identical with the first embodiment, and radiation shield 36 wherein comprises the photon shielding 361 of being made up of plumbous (Pb) and the neutron shield 362 of being made up of polyethylene (PE), this neutron shield 362 can be arranged on beam and export 37 places.Air duct 38 is provided with between thermal neutron absorber 35 and beam outlet 37.Prosthese B2 is arranged on distance beam outlet 37 about 1cm places.
Adopt MCNP software (being the common software bag for calculating neutron, photon, charged particle or coupling neutron/photon/charged particle transport problem in 3 D complex geometry based on DSMC developed by Los Alamos National Laboratories of the U.S. (LosAlamos National the Laboratory)) analog computation to these three kinds of embodiments below:
Wherein, as following table one shows the performance of beam quality factor in these three kinds of embodiments in air (in form, each name lexeme is same as above, does not repeat them here, lower same):
table one: beam quality factor in air
Wherein, as following table two shows the performance in dose form these three kinds of embodiments present:
table two: dosage shows
Wherein, as following table three shows the good and bad simulation value of parameter in these three kinds of embodiments of assessment neutron beam dosage performance:
table three: the parameter that the performance of assessment neutron beam dosage is good and bad
Note: can learn from above-mentioned three tables: the beam-shaping body being provided with clearance channel between slow body and reflector, the treatment benefit of its neutron beam is best.
Because the neutron produced from lithium target has the higher characteristic of Forward averaging energy, as shown in Figure 6, the average neutron energy of neutron scattering angle between 0 °-30 ° is about 478keV, and the average neutron energy of neutron scattering angle between 30 °-180 ° about only has 290keV, if can by the geometry changing beam-shaping body, forward direction neutron and slow body is made to produce more collision, and side direction neutron just can arrive beam outlet through less collision, then should reach the slow optimization of neutron in theory, efficient raising epithermal neutron flux.Set about from the geometry of beam-shaping body below, evaluate the impact of geometry for epithermal neutron flux of different beam-shaping body.
As shown in Figure 7, it illustrates the geometry of the beam-shaping body in the 4th embodiment, this beam-shaping body 40 comprises beam entrance 41, target 42, adjoin the slow body 43 with target 42, be enclosed in the reflector 44 outside slow body 43, the thermal neutron absorber 45 adjacent with slow body 43, be arranged on the radiation shield 46 in beam-shaping body 40 and beam outlet 47, target 42 and the proton beam generation nuclear reaction from beam entrance 41 incidence are to produce neutron, slow body 43 by the neutron degradation that produces from target 42 to epithermal neutron energy district, the neutron departed from leads back to improve epithermal neutron intensity of beam by reflector 44, slow body 43 is arranged to bar shape, preferably, be arranged to cylindrical shape, thermal neutron absorber 45 for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, radiation shield 46 is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district, air duct 48 is provided with between thermal neutron absorber 45 and beam outlet 47.
As shown in Figure 8, it illustrates the geometry of the beam-shaping body in the 5th embodiment, this beam-shaping body 50 comprises beam entrance 51, target 52, adjoin the slow body 53 with target 52, be enclosed in the reflector 54 outside slow body 53, the thermal neutron absorber 55 adjacent with slow body 53, be arranged on the radiation shield 56 in beam-shaping body 50 and beam outlet 57, target 52 and the proton beam generation nuclear reaction from beam entrance 51 incidence are to produce neutron, neutron forms neutron beam, neutron beam limits a major axis X 3, slow body 53 by the neutron degradation that produces from target 52 to epithermal neutron energy district, the neutron departing from major axis X 3 is led back to major axis X 3 to improve epithermal neutron intensity of beam by reflector 54, it is cone-shaped that slow body 53 is arranged to that two rightabouts adjoin each other, the left side of slow body 53 is bar shape, the right side of slow body 53 is diminish gradually towards right side cone-shaped, both adjoin each other, thermal neutron absorber 25 for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, radiation shield 26 is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district.
As one preferably, target 52 in 5th embodiment, slow body 53, reflector 54, thermal neutron absorber 55 and radiation shield 56 can identical with the first embodiment, and radiation shield 56 wherein comprises the photon shielding 561 of being made up of plumbous (Pb) and the neutron shield 562 of being made up of polyethylene (PE), this neutron shield 562 can be arranged on beam and export 57 places.Air duct 58 is provided with between thermal neutron absorber 55 and beam outlet 57.Prosthese B3 is arranged on distance beam outlet 57 about 1cm places.
Adopt MCNP software to the analog computation of the cylinder+cone in the slow body of the cylinder in the slow body of bicone in the second embodiment, the 4th embodiment and the 5th embodiment below:
Wherein, as following table four shows the performance of beam quality factor in these three kinds of embodiments in air:
table four: beam quality factor in air
Wherein, as following table five shows the performance in dose form these three kinds of embodiments present:
table five: dosage shows
Wherein, as following table six shows the good and bad simulation value of parameter in these three kinds of embodiments of assessment neutron beam dosage performance:
table six: the parameter that the performance of assessment neutron beam dosage is good and bad
Note: can learn from above-mentioned three tables: slow body is arranged at least one is cone-shaped, the treatment benefit of its neutron beam is better.
" cylinder " or " bar shape " described in this utility model embodiment refers to the structure substantially constant to the overall trend of its outline of opposite side along the side of direction as shown, a wherein contour line of outline can be line segment, as the contour line of the correspondence of cylindrical shape, also can be the circular arc close to line segment that curvature is larger, the contour line of the correspondence of sphere body shape as larger in curvature, the whole surface of outline can be rounding off, also can be non-rounding off, as done a lot of projection and groove on the surface of cylindrical shape or the larger sphere body shape of curvature.
" cone " or " cone-shaped " described in this utility model embodiment refers to the structure diminished gradually along the side of direction as shown to the overall trend of its outline of opposite side, a wherein contour line of outline can be line segment, as the contour line of the correspondence of cone shape, also can be circular arc, as the contour line of the correspondence of sphere body shape, the whole surface of outline can be rounding off, also can be non-rounding off, as done a lot of projection and groove on the surface of cone shape or sphere body shape.
The beam-shaping body for neutron capture treatment that this utility model discloses is not limited to the content described in above embodiment and the structure represented by accompanying drawing.The change apparently that basis of the present utility model is made the material of wherein component, shape and position, to substitute or amendment, all within the scope that this utility model is claimed.
Claims (10)
1. the beam-shaping body for neutron capture treatment, it is characterized in that: described beam-shaping body comprises beam entrance, target, be adjacent to the slow body of described target, be enclosed in described reflector external slowly, the thermal neutron absorber adjacent with described slow body, be arranged on the radiation shield in described beam-shaping body and beam outlet, described target and the proton beam generation nuclear reaction from the incidence of described beam entrance are to produce neutron, described neutron forms neutron beam, described neutron beam limits a main shaft, described slow body by the neutron degradation that produces from described target to epithermal neutron energy district, the neutron departing from described main shaft is led back to described main shaft to improve epithermal neutron intensity of beam by described reflector, clearance channel is set between described slow body and described reflector to improve epithermal neutron flux, described thermal neutron absorber for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, described radiation shield is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district.
2. the beam-shaping body for neutron capture treatment according to claim 1, is characterized in that: described beam-shaping body is further used for the treatment of accelerator boron neutron capture.
3. the beam-shaping body for neutron capture treatment according to claim 2, it is characterized in that: proton beam is accelerated by accelerator by the treatment of accelerator boron neutron capture, described target is made of metal, described proton beam accelerates to the energy being enough to overcome target atom core coulomb repulsion, with described target generation nuclear reaction to produce neutron.
4. the beam-shaping body for neutron capture treatment according to claim 1, it is characterized in that: described beam-shaping physical ability by neutron slowly to epithermal neutron energy district, and reduce thermal neutron and fast neutron content, described epithermal neutron energy district is between 0.5eV to 40keV, describedly hanker subzone and be less than 0.5eV, described fast-neutron range is greater than 40keV, described slow body is large by having fast neutron action section, the material that epithermal neutron action section is little is made, described reflector is made up of the material having neutron reflection ability strong, described thermal neutron absorber is made up of the material large with thermal neutron action section.
5. the beam-shaping body for neutron capture treatment according to claim 4, is characterized in that: described slow body is by D
2o, AlF
3, Fluental
tM, CaF
2, Li
2cO
3, MgF
2and Al
2o
3in at least one make.
6. according to claim 4 for neutron capture treatment beam-shaping body, it is characterized in that: described reflector is made up of at least one in Pb or Ni, described thermal neutron absorber by
6li makes, and is provided with air duct between described thermal neutron absorber and the outlet of described beam.
7. the beam-shaping body for neutron capture treatment according to claim 1, is characterized in that: described radiation shield comprises photon shielding and neutron shield.
8. the beam-shaping body for neutron capture treatment according to claim 4, is characterized in that: described slow body is arranged to comprise at least one pyramidal shape.
9. the beam-shaping body for neutron capture treatment according to claim 8, is characterized in that: described slow body is arranged to comprise a bar shape and a pyramidal shape adjacent with described bar shape.
10. the beam-shaping body for neutron capture treatment according to claim 8, is characterized in that: it is cone-shaped that described slow body is arranged to that two rightabouts adjoin each other.
Priority Applications (22)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420765424.2U CN204319540U (en) | 2014-12-08 | 2014-12-08 | For the beam-shaping body of neutron capture treatment |
| EP16192908.8A EP3133905B1 (en) | 2014-12-08 | 2015-04-21 | A beam shaping assembly for neutron capture therapy |
| EP15164481.2A EP3032927B1 (en) | 2014-12-08 | 2015-04-21 | A beam shaping assembly for neutron capture therapy |
| EP15164471.3A EP3032926B1 (en) | 2014-12-08 | 2015-04-21 | A beam shaping assembly for neutron capture therapy |
| PL15164481T PL3032927T3 (en) | 2014-12-08 | 2015-04-21 | A beam shaping assembly for neutron capture therapy |
| PL15164471T PL3032926T3 (en) | 2014-12-08 | 2015-04-21 | A beam shaping assembly for neutron capture therapy |
| DK15164481.2T DK3032927T3 (en) | 2014-12-08 | 2015-04-21 | RADIATING DEVICE FOR NEUTRON COLLECTION THERAPY |
| EP17206556.7A EP3316665B1 (en) | 2014-12-08 | 2015-04-21 | Beam shaping assembly for neutron capture therapy |
| DK15164471.3T DK3032926T3 (en) | 2014-12-08 | 2015-04-21 | RADIATING DEVICE FOR NEUTRON COLLECTION THERAPY |
| US14/705,811 US9974979B2 (en) | 2014-12-08 | 2015-05-06 | Beam shaping assembly for neutron capture therapy |
| US14/705,784 US9889320B2 (en) | 2014-12-08 | 2015-05-06 | Beam shaping assembly for neutron capture therapy |
| JP2015115129A JP6147296B2 (en) | 2014-12-08 | 2015-06-05 | Beam shaping assembly for neutron capture therapy |
| JP2015115128A JP6129899B2 (en) | 2014-12-08 | 2015-06-05 | Beam shaping assembly for neutron capture therapy |
| RU2015127438A RU2691322C2 (en) | 2014-12-08 | 2015-07-08 | Irradiator for neutron capturing therapy |
| RU2015127439A RU2695255C2 (en) | 2014-12-08 | 2015-07-08 | Radiator for neutron capturing therapy |
| TW104122641A TWI581821B (en) | 2014-12-08 | 2015-07-13 | A beam shaping assembly for neutron capture therapy |
| TW106107701A TWI640998B (en) | 2014-12-08 | 2015-07-13 | A beam shaping assembly for neutron capture therapy |
| TW104122643A TWI581822B (en) | 2014-12-08 | 2015-07-13 | A beam shaping assembly for neutron capture therapy |
| JP2017059482A JP6334768B2 (en) | 2014-12-08 | 2017-03-24 | Beam shaping assembly for neutron capture therapy |
| US15/825,690 US10124192B2 (en) | 2014-12-08 | 2017-11-29 | Beam shaping assembly for neutron capture therapy |
| JP2018083741A JP6592135B2 (en) | 2014-12-08 | 2018-04-25 | Beam shaping assembly for neutron capture therapy |
| US16/143,949 US10610704B2 (en) | 2014-12-08 | 2018-09-27 | Beam shaping assembly for neutron capture therapy |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420765424.2U CN204319540U (en) | 2014-12-08 | 2014-12-08 | For the beam-shaping body of neutron capture treatment |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN204319540U true CN204319540U (en) | 2015-05-13 |
Family
ID=53155946
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201420765424.2U Active CN204319540U (en) | 2014-12-08 | 2014-12-08 | For the beam-shaping body of neutron capture treatment |
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| Country | Link |
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| CN (1) | CN204319540U (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104511096A (en) * | 2014-12-08 | 2015-04-15 | 南京中硼联康医疗科技有限公司 | Beam shaper for neutron-capture therapy |
| CN106552322A (en) * | 2015-09-28 | 2017-04-05 | 南京中硼联康医疗科技有限公司 | For the beam diagnostic system of neutron capture treatment system |
| CN106798969A (en) * | 2015-11-26 | 2017-06-06 | 南京中硼联康医疗科技有限公司 | For the beam-shaping body of neutron capture treatment |
| TWI609709B (en) * | 2015-10-29 | 2018-01-01 | 住友重機械工業股份有限公司 | Neutron capture therapy system |
| CN110180095A (en) * | 2016-01-08 | 2019-08-30 | 南京中硼联康医疗科技有限公司 | Beam-shaping body for neutron capture treatment |
| US11224766B2 (en) * | 2016-12-23 | 2022-01-18 | Neuboron Medtech Ltd. | Neutron capture therapy system and target for particle beam generating device |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104511096A (en) * | 2014-12-08 | 2015-04-15 | 南京中硼联康医疗科技有限公司 | Beam shaper for neutron-capture therapy |
| CN104511096B (en) * | 2014-12-08 | 2018-01-05 | 南京中硼联康医疗科技有限公司 | Beam-shaping body for neutron capture treatment |
| CN106552322A (en) * | 2015-09-28 | 2017-04-05 | 南京中硼联康医疗科技有限公司 | For the beam diagnostic system of neutron capture treatment system |
| CN106552322B (en) * | 2015-09-28 | 2018-08-21 | 南京中硼联康医疗科技有限公司 | Beam diagnostic system for neutron capture treatment system |
| TWI609709B (en) * | 2015-10-29 | 2018-01-01 | 住友重機械工業股份有限公司 | Neutron capture therapy system |
| CN106798969A (en) * | 2015-11-26 | 2017-06-06 | 南京中硼联康医疗科技有限公司 | For the beam-shaping body of neutron capture treatment |
| CN106798969B (en) * | 2015-11-26 | 2023-05-16 | 南京中硼联康医疗科技有限公司 | Beam shaping body for neutron capture therapy |
| CN110180095A (en) * | 2016-01-08 | 2019-08-30 | 南京中硼联康医疗科技有限公司 | Beam-shaping body for neutron capture treatment |
| CN110180095B (en) * | 2016-01-08 | 2022-02-15 | 南京中硼联康医疗科技有限公司 | Beam shaping body for neutron capture therapy |
| US11224766B2 (en) * | 2016-12-23 | 2022-01-18 | Neuboron Medtech Ltd. | Neutron capture therapy system and target for particle beam generating device |
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