CN104511096B - Beam-shaping body for neutron capture treatment - Google Patents
Beam-shaping body for neutron capture treatment Download PDFInfo
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Abstract
In order to improve the flux and quality that neutron penetrates source,One aspect of the present invention provides a kind of beam-shaping body for neutron capture treatment,Wherein,Beam-shaping body includes target,The adjacent slow body with target,It is enclosed in slow external reflector,With the thermal neutron absorber of slow body adjoining,Radiation shield and the beam outlet being arranged in beam-shaping body,Target from the incident proton beam of beam entrance with occurring nuclear reaction to produce neutron,Neutron forms neutron beam,Neutron beam limits a main shaft,Slow body will be from neutron degradation caused by target to epithermal neutron energy area,The neutron that reflector will deviate from main shaft leads back to main shaft to improve epithermal neutron intensity of beam,Clearance channel is slowly set to improve epithermal neutron flux between body and reflector,When thermal neutron absorber is used to absorb thermal neutron to avoid treatment multiple dose was caused with shallow-layer normal structure,Radiation shield is used to shield neutron and the photon of seepage to reduce the normal tissue dose in non-irradiated area.
Description
Technical field
The present invention relates to a kind of beam-shaping body, more particularly to a kind of beam-shaping body for neutron capture treatment.
Background technology
As the development of atomics, such as the radiation cure such as cobalt 60, linear accelerator, electron beam turn into cancer
One of Main Means of disease treatment.But conventional photonic or electronic therapy are limited by radioactive ray physical condition itself, are killing
While dead tumour cell, substantial amounts of normal structure in beam approach can also be damaged；Additionally, due to tumour cell to putting
The difference of radiation-sensitive degree, traditional radiation therapy is for relatively having the malignant tumour of radiation resistance（Such as：Multirow glioblast
Knurl（glioblastoma multiforme）, melanocytoma（melanoma））Treatment effect it is often bad.
In order to reduce the radiation injury of tumour surrounding normal tissue, chemotherapy（chemotherapy）In target therapy
Concept is just applied in radiation cure；And for the tumour cell of radiation resistance, also actively development has high phase at present
To biological effect（relative biological effectiveness, RBE）Radiation source, such as proton therapeutic, heavy particle
Treatment, neutron capture treatment etc..Wherein, neutron capture treatment is to combine above two concept, such as the treatment of boron neutron capture, is borrowed
Gathered by specificity of the boracic medicine in tumour cell, coordinate accurately neutron beam regulation and control, there is provided more preferable than conventional radiation
Treatment of cancer selection.
Boron neutron capture is treated（Boron Neutron Capture Therapy, BNCT）It is to utilize boracic（10B）Medicine
There is the characteristic of high capture cross section to thermal neutron, by10B(n,α) 7Li neutron captures and nuclear fission reaction produce4He and7Li two
Individual heavy burden charged particle.Referring to Figures 1 and 2, which respectively show boron neutron capture reaction schematic diagram and10B(n,α) 7Li neutrons
Nuclear equation formula is captured, 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 transfers of α particles and range are respectively 150 keV/ μm, 8 μm, and7Li
Heavy burden particle is then 175 keV/ μm, 5 μm, and the integrated range of two particle is approximately equivalent to a cell size, therefore for organism
Caused by radiation injury can be confined to cell level, be gathered in when boracic drug selectivity in tumour cell, it is appropriate to arrange in pairs or groups
Neutron penetrates source, just can reach the local purpose for killing tumour cell on the premise of not normal tissue causes too major injury.
Because the effect of boron neutron capture treatment depends on tumour cell position boracic drug concentration and hankers quantum count, therefore again
It is referred to as binary radioactive ray treatment of cancer（binary cancer therapy）；It follows that except the exploitation of boracic medicine,
Neutron penetrates source flux and the improvement of quality occupies key player in the research that boron neutron capture is treated.
The content of the invention
In order to improve the flux and quality that neutron penetrates source, one aspect of the present invention provides a kind of neutron capture that is used for and treated
Beam-shaping body, wherein, beam-shaping body include target, adjoining and target slow body, be enclosed in slow external reflection
Body, export with thermal neutron absorber, the radiation shield that is arranged in beam-shaping body and the beam of the adjoining of slow body, target with from
Nuclear reaction occurs for the incident proton beam of beam entrance to produce neutron, and neutron forms neutron beam, and neutron beam limits a master
Axle, slow body will be from neutron degradations caused by target to epithermal neutron energy area, and the neutron that reflector will deviate from main shaft leads back to main shaft
Clearance channel is set to hanker to improve epithermal neutron flux to improve epithermal neutron intensity of beam, between slow body and reflector
Multiple dose was caused when sub- absorber is used to absorb thermal neutron to avoid treatment with shallow-layer normal structure, radiation shield is used to shield
The neutron and photon of seepage are to reduce the normal tissue dose in non-irradiated area.
Beam-shaping body is further used for the treatment of accelerator boron neutron capture.
Proton accelerate (beamacceleration), target are made of metal by the treatment of accelerator boron neutron capture by accelerator, proton accelerate (beamacceleration)
To the energy for being enough to overcome target atom core coulomb repulsion, nuclear reaction occurs with target to produce neutron.
Neutron slowly to epithermal neutron energy area, and is reduced thermal neutron and fast neutron content by beam-shaping physical efficiency, in superthermal
Subzone hankers subzone and is less than 0.5eV between 0.5eV to 40keV, and fast-neutron range is more than 40keV, slow body by with
The material that fast neutron action section is big, epithermal neutron action section is small is made, and reflector is by with the strong material of neutron reflection ability
Material is made, and thermal neutron absorber is made up of the material big with thermal neutron action section.
As one kind preferably, slow body is by D2O、AlF3、FluentalTM、CaF2、Li2CO3 、MgF2And Al2O3In
At least one is made.
Further, reflector is made up of at least one of Pb or Ni, thermal neutron absorber by6Li is made, thermal neutron
Air duct is provided between absorber and beam outlet.
Radiation shield includes photon shielding and neutron shield.As one kind preferably, photon shielding is made up of Pb, neutron screen
Cover by PE（Polyethylene）It is made.
As it is a kind of preferably, slow body be arranged to comprising a bar shape and with one of bar shape adjoining it is cone-shaped
Shape or two opposite directions that are arranged to adjoin each other cone-shaped.
" cylinder " or " bar shape " described in the embodiment of the present invention refer to along the side of direction as shown to opposite side its
The structure that the overall trend of outline is basically unchanged, a wherein contour line for outline can be line segment, such as cylindrical shape
Corresponding contour line or the larger circular arc close to line segment of curvature, such as the corresponding wheel of the larger sphere body shape of curvature
Profile, the whole surface of outline can be rounding off or non-rounding off, such as in cylindrical shape or curvature
Many raised and grooves are done in the surface of larger sphere body shape.
" cone " or " cone-shaped " described in the embodiment of the present invention refer to along the side of direction as shown to opposite side its
The structure that the overall trend of outline tapers into, a wherein contour line for outline can be line segment, such as cone shape
Corresponding contour line or circular arc, such as the corresponding contour line of sphere body shape, the whole surface of outline can be round and smooth
Transition or non-rounding off, many raised and grooves have such as been done on the surface of cone shape or sphere body shape.
Brief description of the drawings
Fig. 1 is boron neutron capture reaction schematic diagram.
Fig. 2 is10B(n,α) 7Li neutron capture nuclear equation formulas.
Fig. 3 is the floor map of the beam-shaping body for being used for neutron capture treatment in first embodiment of the invention, its
In, it is provided with clearance channel between slow body and reflector.
Fig. 4 is the floor map of the beam-shaping body for being used for neutron capture treatment in second embodiment of the invention, its
In, slow body is arranged to bicone, and the clearance channel position in first embodiment is filled with slow body material.
Fig. 5 is the floor map of the beam-shaping body for being used for neutron capture treatment in third embodiment of the invention, its
In, slow body is arranged to bicone, and the clearance channel position in first embodiment is filled with reflector material.
Fig. 6 is the neutron yield rate figure of neutron energy and the double differential of neutron angle.
Fig. 7 is the floor map of the beam-shaping body for being used for neutron capture treatment in fourth embodiment of the invention, its
In, slow body is arranged to cylinder.
Fig. 8 is the floor map of the beam-shaping body for being used for neutron capture treatment in fifth embodiment of the invention, its
In, slow body is arranged to cylinder+cone.
Embodiment
A kind of application of the neutron capture treatment as means of effective treating cancer in recent years gradually increases, wherein with boron
Neutron capture treatment is most commonly seen, and the neutron of supply boron neutron capture treatment can be supplied by nuclear reactor or accelerator.This hair
By taking the treatment of accelerator boron neutron capture as an example, the basic module of accelerator boron neutron capture treatment generally includes to use bright embodiment
In to charged particle（Such as proton, deuteron）Accelerator, target and hot removal system and the beam-shaping body accelerated, wherein
Charged particle is accelerated to produce neutron with metal targets effect, it is powered according to required neutron yield rate and energy, available acceleration
Particle energy and size of current, the characteristics such as materialization of metal targets select suitable nuclear reaction, the nuclear reaction often to come into question
Have7Li(p,n)7Be and9Be(p,n)9B, both reactions are all the endothermic reaction.The energy threshold of two kinds of nuclear reactions is respectively
1.881MeV and 2.055MeV, it is theoretical due to the epithermal neutron that the preferable neutron source of boron neutron capture treatment is keV energy grades
If the upper proton bombardment lithium metal target that threshold values is only slightly taller than using energy, the neutron of relative low energy can be produced, is not necessary to too many
Slow handle can be used for clinic, but lithium metal（Li）With beryllium metal（Be）The proton-effect of two kinds of targets and threshold values energy is cut
Face is not high, to produce sufficiently large neutron flux, generally triggers nuclear reaction from the proton of higher-energy.
Preferable target should possess high neutron yield rate, caused neutron energy is distributed close to epithermal neutron energy area（Will be under
Text is described in detail）, without it is too many wear by force radiation produce, the characteristic such as cheap easily operated and high temperature resistant of safety, but actually and can not
Find and meet required nuclear reaction, target made of lithium metal is used in embodiments of the invention.But art technology
Known to personnel, the material of target can also be made up of other metal materials in addition to the above-mentioned metal material talked about.
Requirement for hot removal system is then different according to the nuclear reaction of selection, such as7Li(p,n)7Be is because of metal targets（Lithium
Metal）Fusing point and thermal conductivity coefficient it is poor, requirement to hot removal system just compared with9Be(p,n)9B is high.Adopted in embodiments of the invention
With7Li(p,n)7Be nuclear reaction.
No matter boron neutron capture treatment nuclear reaction of the neutron source from nuclear reactor or accelerator charged particle and target,
Caused is all mixed radiation field, i.e., beam contains neutron, photon of the low energy to high energy；Caught for the boron neutron of deep tumor
Treatment is obtained, in addition to epithermal neutron, remaining radiation content is more, causes the ratio of the non-selective dosage deposition of normal structure
It is bigger, therefore these can cause the radiation of unnecessary dosage to try one's best reduction.Except air beam quality factor, in knowing more about
Son dosage caused by human body is distributed, and Rapid Dose Calculation is carried out using human body head tissue prosthese in embodiments of the invention, and
It is used as the design reference of neutron beam with prosthese beam quality factor, will be described in more detail below.
International Atomic Energy Agency（IAEA）For the neutron source of clinical boron neutron capture treatment, penetrated given five air
Beam quality factor suggestion, this five suggestions can be used for more different neutron sources quality, and be provided with as select neutron produce way
Reference frame when footpath, design beam-shaping body.This five suggestion difference are as follows：
Epithermal neutron beam flux Epithermal neutron flux> 1 x 109 n/cm2s
Fast neutron pollution Fast neutron contamination< 2 x 10-13 Gy-cm2/n
Photon contamination Photon contamination< 2 x 10-13 Gy-cm2/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：Hanker subzone between 0.5eV to 40keV and be less than 0.5eV, fast-neutron range is more than in epithermal neutron energy area
40keV。
1st, epithermal neutron beam flux：
Boracic drug concentration has together decided on the clinical treatment time in neutron beam flux and tumour.If tumour boracic medicine
The enough height of concentration, the requirement for neutron beam flux can reduce；Conversely, if boracic drug concentration is low in tumour, high pass is needed
Epithermal neutron is measured to give tumour enough dosage.Requirements of the IAEA for epithermal neutron beam flux is per second every square centimeter
Epithermal neutron number be more than 109, the neutron beam under this flux can substantially control treatment for current boracic medicine
Time, short treatment time in addition to advantageous to patient's positioning and comfort level, also can more effectively utilize boracic medicine in one hour
Thing is in the intra-tumor limited holdup time.
2nd, fast neutron pollutes：
Because fast neutron can cause unnecessary normal tissue dose, therefore it is regarded as pollution, this dosage size and neutron
Energy is proportionate, therefore should be tried one's best in neutron beam design and reduce the content of fast neutron.Fast neutron pollution definition is unit
The adjoint fast neutron dosage of epithermal neutron flux, the suggestion that IAEA pollutes to fast neutron are less than 2 x 10-13 Gy-cm2/n。
3rd, photon contamination（Gamma-ray contamination）：
Gamma-rays belongs to wears radiation by force, can non-selectively cause the organized dosage deposition of institute on course of the beam, therefore
Reduce gamma-rays content be also neutron beam design exclusive requirement, gamma-ray contamination define for unit epithermal neutron flux it is adjoint
Gamma-rays dosage, suggestions of the IAEA to gamma-ray contamination are less than 2 x 10-13 Gy-cm2/n。
4th, thermal and epithermal neutron flux ratio：
Because thermal neutron decay speed is fast, penetration capacity is poor, into human body after most of energy be deposited on skin histology, remove
Outside the neutron source that the Several Epidermal Tumors such as melanocytoma need to treat by the use of thermal neutron as boron neutron capture, swollen for deep layers such as brain tumors
Knurl should reduce thermal neutron content.IAEA is less than 0.05 to the suggestion of thermal and epithermal neutron flux ratio.
5th, middle electron current and flux ratio：
Middle electron current represents the directionality of beam with flux ratio, and tropism is good before the bigger expression neutron beam of ratio, high
The neutron beam of preceding tropism can reduce because neutron dissipate caused by normal surrounding tissue dosage, also improve in addition can treat depth and
Put pose gesture elasticity.IAEA centerings electron current is more than 0.7 with flux ratio suggestion.
The dosage obtained using prosthese in tissue is distributed, and according to the dose versus depth curve of normal structure and tumour, pushes away false
Body beam quality factor.Following three parameter can be used for the comparison for carrying out different neutron beam treatment benefits.
1st, effective therapeutic depth：
Tumor dose is equal to the depth of normal structure maximum dose, the position after this depth, what tumour cell obtained
Dosage is less than normal structure maximum dose, that is, loses the advantage of boron neutron capture.What this parameter represented neutron beam penetrates energy
Power, effective therapeutic depth is bigger to represent that medicable tumor depth is deeper, unit cm.
2nd, effective therapeutic depth close rate：
That is the tumor dose rate of effective therapeutic depth, also equal to the maximum dose rate of normal structure.Because normal structure receives
Accumulated dose can give the factor of tumour accumulated dose size for influence, therefore parameter influences the length for the treatment of time, and effectively treatment is deep
The irradiation time that the bigger expression of degree close rate is given needed for tumour doses is shorter, unit cGy/mA-min.
3rd, dose therapeutically effective ratio：
From brain surface to effective therapeutic depth, the mean dose ratio of tumour and normal structure reception, it is referred to as effective
Therapeutic dose ratio；The calculating of mean dose, it can integrate to obtain by dose versus depth curve.Dose therapeutically effective ratio is bigger, represents
The treatment benefit of the neutron beam is better.
In order that beam-shaping body has in design compares foundation, in the air suggested except five IAEA beam quality because
Three plain and above-mentioned parameters, also utilize in the embodiment of the present invention and following be used to assess the good and bad ginseng of neutron beam dosage performance
Number：
1st, irradiation time≤30min（The proton current that accelerator uses is 10mA）
2nd, 30.0RBE-Gy can treat depth >=7cm
3rd, tumour maximum dose >=60.0RBE-Gy
4th, normal cerebral tissue's maximum dose≤12.5RBE-Gy
5th, skin maximum dose≤11.0RBE-Gy
Note：RBE（Relative Biological Effectiveness）For relative biological effect, due to photon, neutron
Can caused by biological effect it is different, so dosage item as above be respectively multiplied by the relative biological effect of different tissues in the hope of etc.
Imitate dosage.
In order to improve the flux and quality that neutron penetrates source, embodiments of the invention are to be directed to be used for penetrating for neutron capture treatment
The improvement that beam shaping body proposes, it is to be directed to the beam-shaping body for being used for the treatment of accelerator boron neutron capture as one kind preferably
Improvement.As shown in figure 3, the beam-shaping body 10 for being used for neutron capture treatment in first embodiment of the invention, it includes penetrating
Beam entrance 11, target 12, adjacent and target 12 slow body 13, the reflector 14 being enclosed in outside slow body 13 and slow body 13
Adjacent thermal neutron absorber 15, the radiation shield 16 being arranged in beam-shaping body 10 and beam outlet 17, target 12 with from
Nuclear reaction occurs for the incident proton beam of beam entrance 11 to produce neutron, and neutron forms neutron beam, and neutron beam limits one
Major axis X, slow body 13 will will deviate from major axis X from neutron degradation caused by target 12 to epithermal neutron energy area, reflector 14
Son leads back to major axis X to improve epithermal neutron intensity of beam, and clearance channel 18 is set between slow body 13 and reflector 14 to improve
Epithermal neutron flux, multi-agent was caused with shallow-layer normal structure when thermal neutron absorber 15 is used to absorb thermal neutron to avoid treatment
Amount, radiation shield 16 are used to shield neutron and the photon of seepage to reduce the normal tissue dose in non-irradiated area.
The treatment of accelerator boron neutron capture by accelerator by proton accelerate (beamacceleration), as a kind of preferred embodiment, target 12
It is made up of lithium metal, proton beam accelerates to the energy for being enough to overcome target atom core coulomb repulsion, occurs with target 127Li(p,
n)7Be nuclear reactions are to produce neutron.Beam-shaping body 10 can be by neutron slowly to epithermal neutron energy area, and reduces thermal neutron and fast
Neutron content, slow body 13 with the material that fast neutron action section is big, epithermal neutron action section is small by being made, as one kind
Preferred embodiment, slow body 13 is by D2O、AlF3、FluentalTM、CaF2、Li2CO3 、MgF2And Al2O3At least one of system
Into.Reflector 14 with the strong material of neutron reflection ability by being made, and as a kind of preferred embodiment, reflector 14 is by Pb or Ni
At least one of be made.Thermal neutron absorber 15 is made up of the material big with thermal neutron action section, as a kind of preferred real
Apply example, thermal neutron absorber 15 by6Li is made, and air duct 19 is provided between thermal neutron absorber 15 and beam outlet 17.Spoke
Penetrating shielding 16 includes photon shielding 161 and neutron shield 162, and as a kind of preferred embodiment, radiation shield 16 is included by lead
（Pb）Manufactured photon shields 161 and by polyethylene（PE）Manufactured neutron shield 162.
Wherein, slow body 13 is arranged to two opposite directions and adjoined each other cone-shaped, as shown in Figure 3 direction, slowly
The left side of body 13 is cone-shaped to be tapered into towards left side, and the right side of slow body 13 is the cone tapered into towards right side
Shape, both adjoin each other.As it is a kind of preferably, the left side of slow body 13 be arranged to taper into towards left side it is cone-shaped,
And right side can also be arranged to its allothimorph shape with this it is cone-shaped adjoin each other, such as bar shape.Reflector 14 closely surrounds
Around slow body 13, clearance channel 18 is provided between slow body 13 and reflector 14, what so-called clearance channel 18 referred to
It is that the empty of unused solid material covering easily allows the region that neutron beam passes through, leads to as the clearance channel 18 could be arranged to air
Road or vacuum passage.The thermal neutron absorber 15 set close to slow body 13 is by very thin one layer6Li materials are made, radiation
The shielding of the photon made of Pb 161 in shielding 16 can be set with reflector 14 be integrated, and can also be arranged to split, and spoke
The position of beam outlet 17 can be positioned adjacent to by penetrating the neutron shield 162 made of PE in shielding 16.In thermal neutron absorber
15 and beam outlet 17 between be provided with air duct 19, in this region the sustainable neutron that will deviate from major axis X lead back to major axis X with
Improve epithermal neutron intensity of beam.Prosthese B is arranged on apart from beam outlet 17 about at 1cm.It is well known to those skilled in the art, light
Son shielding 161 can be made up of other materials, as long as playing a part of shielding photon, neutron shield 162 can also be by it
He is made material, can also be arranged on other places, as long as disclosure satisfy that the condition of shielding seepage neutron.
In order to compare the difference for being provided with the beam-shaping body of clearance channel and being not provided with the beam-shaping body of clearance channel,
As shown in Figure 4 and Figure 5, which respectively show adopted by clearance channel using the second embodiment of slow body filling and by clearance channel
The 3rd embodiment filled with reflector.With reference first to Fig. 4, the beam-shaping body 20 includes beam entrance 21, target 22, adjoining
Slow body 23 with target 22, the reflector 24 being enclosed in outside slow body 23, with the thermal neutron absorber 25 of slow body 23 adjoining,
Radiation shield 26 and the beam outlet 27 being arranged in beam-shaping body 20, target 22 and the proton beam from the incidence of beam entrance 21
Generation nuclear reaction is to produce neutron, and neutron forms neutron beam, and neutron beam limits a major axis X 1, and slow body 23 will be from target
Neutron degradation caused by 22 is to epithermal neutron energy area, and reflector 24 will deviate from the neutron of major axis X 1, and to lead back to major axis X 1 superthermal to improve
Neutron beam intensity, slow body 23 be arranged to two opposite directions adjoin each other it is cone-shaped, the left side of slow body 23 be towards
Left side tapers into cone-shaped, and the right side of slow body 23 is cone-shaped to be tapered into towards right side, and both adjoin each other, heat
Multiple dose was caused with shallow-layer normal structure when neutron absorber 25 is used to absorb thermal neutron to avoid treatment, radiation shield 26 is used
In shielding seepage neutron and photon to reduce the normal tissue dose in non-irradiated area.
As one kind preferably, target 22, slow body 23, reflector 24, thermal neutron absorber 25 in second embodiment
Can be identical with first embodiment with radiation shield 26, and radiation shield therein 26 is included by lead（Pb）Manufactured photon
Shield 261 and by polyethylene（PE）Manufactured neutron shield 262, the neutron shield 262 can be arranged at beam outlet 27.
Air duct 28 is provided between thermal neutron absorber 25 and beam outlet 27.Prosthese B1 is arranged on apart from beam outlet 27 about
At 1cm.
Fig. 5 is refer to, slow body 33 of the beam-shaping body 30 including beam entrance 31, target 32, adjoining and target 32,
The reflector 34 being enclosed in outside slow body 33 and the thermal neutron absorber 35 of slow body 33 adjoining, it is arranged on beam-shaping body 30
During nuclear reaction occurs for interior radiation shield 36 and beam outlet 37, target 32 and the proton beam from the incidence of beam entrance 31 to produce
Son, neutron form neutron beam, and neutron beam limits a major axis X 2, and slow body 33 will be from neutron degradation caused by target 32 extremely
Epithermal neutron energy area, the neutron that reflector 34 will deviate from major axis X 2 lead back to major axis X 2 to improve epithermal neutron intensity of beam, slowly
Body 33 is arranged to two opposite directions and adjoins each other cone-shaped, and the left side of slow body 33 is the cone tapered into towards left side
Shape, the right side of slow body 33 is cone-shaped to be tapered into towards right side, and both adjoin each other, and thermal neutron absorber 35 is used to inhale
Caused multiple dose with shallow-layer normal structure when receiving thermal neutron to avoid treatment, radiation shield 36 be used for the neutron for shielding seepage and
Photon is to reduce the normal tissue dose in non-irradiated area.
As one kind preferably, target 32, slow body 33, reflector 34, thermal neutron absorber 35 in 3rd embodiment
Can be identical with first embodiment with radiation shield 36, and radiation shield therein 36 is included by lead（Pb）Manufactured photon
Shield 361 and by polyethylene（PE）Manufactured neutron shield 362, the neutron shield 362 can be arranged at beam outlet 37.
Air duct 38 is provided between thermal neutron absorber 35 and beam outlet 37.Prosthese B2 is arranged on apart from beam outlet 37 about
At 1cm.
MCNP softwares are used below（It is by Los Alamos National Laboratories of the U.S. (LosAlamos National
Laboratory) exploitation based on DSMC is used to calculate neutron in 3 D complex geometry, photon, powered
Particle or the common software bag for coupling neutron/photon/charged particle transport problem）Simulation to these three embodiments calculates：
Wherein, as following table one shows performance of the beam quality factor in these three embodiments in air（It is each in form
Name lexeme is same as above, will not be repeated here, similarly hereinafter）：
Table one：Beam quality factor in air
Wherein, as following table two shows that dosage shows the performance in these three embodiments：
Table two：Dosage shows
Wherein, as following table three shows the mould for assessing the good and bad parameter of neutron beam dosage performance in these three embodiments
Intend numerical value：
Table three：Assess the good and bad parameter of neutron beam dosage performance
Note：It can be learnt from three above-mentioned tables：The beam of clearance channel is provided between slow body and reflector
Shaping body, the treatment benefit of its neutron beam are best.
Due to there is the higher characteristic of Forward averaging energy from neutron caused by lithium target, as shown in fig. 6, neutron scattering angle
The average neutron energy spent between 0 ° -30 ° is about 478keV, and average neutron of the neutron scattering angle between 30 ° -180 °
Energy about only has 290keV, if can be more to neutron and the generation of slow body before making by the geometry for changing beam-shaping body
Collision, and lateral neutron can reach beam outlet through less collision, then should can reach neutron in theory slowly optimizes, and has
The raising epithermal neutron flux of efficiency.Set about below from the geometry of beam-shaping body, to evaluate different beam-shaping bodies
Influence of the geometry for epithermal neutron flux.
As shown in fig. 7, it illustrates the geometry of the beam-shaping body in fourth embodiment, the beam-shaping body 40 wraps
Include beam entrance 41, target 42, it is adjacent with the slow body 43 of target 42, the reflector 44 being enclosed in outside slow body 43, with it is slow
The thermal neutron absorber 45 of the adjoining of body 43, the radiation shield 46 being arranged in beam-shaping body 40 and beam outlet 47, target 42
With nuclear reaction occurs to produce neutron from the incident proton beam of beam entrance 41, slow body 43 will subtract from neutron caused by target 42
Speed is to epithermal neutron energy area, and the neutron that reflector 44 will deviate from is led back to improve epithermal neutron intensity of beam, and slow body 43 is set
Into bar shape, it is preferable that be arranged to cylindrical shape, when thermal neutron absorber 45 is used to absorb thermal neutron to avoid treatment and shallow-layer
Normal structure caused multiple dose, and radiation shield 46 is used to shield neutron and the photon of seepage to reduce the normal group in non-irradiated area
Dosage is knitted, air duct 48 is provided 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, the beam-shaping body 50 wraps
Include beam entrance 51, target 52, it is adjacent with the slow body 53 of target 52, the reflector 54 being enclosed in outside slow body 53, with it is slow
The thermal neutron absorber 55 of the adjoining of body 53, the radiation shield 56 being arranged in beam-shaping body 50 and beam outlet 57, target 52
With nuclear reaction occurs from the incident proton beam of beam entrance 51 to produce neutron, neutron forms neutron beam, and neutron beam limits
A piece major axis X 3, slow body 53 will will deviate from main shaft from neutron degradation caused by target 52 to epithermal neutron energy area, reflector 54
X3 neutron leads back to major axis X 3 to improve epithermal neutron intensity of beam, and slow body 53 is arranged to what two opposite directions adjoined each other
Cone-shaped, the left side of slow body 53 is bar shape, and the right side of slow body 53 is to taper into cone-shaped, Liang Zhexiang towards right side
It is mutually adjacent, caused multiple dose, spoke with shallow-layer normal structure when thermal neutron absorber 25 is used to absorb thermal neutron to avoid treatment
Shielding 26 is penetrated for shielding neutron and the photon of seepage to reduce the normal tissue dose in non-irradiated area.
As one kind preferably, target 52, slow body 53, reflector 54, thermal neutron absorber 55 in the 5th embodiment
Can be identical with first embodiment with radiation shield 56, and radiation shield therein 56 is included by lead（Pb）Manufactured photon
Shield 561 and by polyethylene（PE）Manufactured neutron shield 562, the neutron shield 562 can be arranged at beam outlet 57.
Air duct 58 is provided between thermal neutron absorber 55 and beam outlet 57.Prosthese B3 is arranged on apart from beam outlet 57 about
At 1cm.
Below using MCNP softwares to the slow of the cylinder in the slow body of bicone, fourth embodiment in second embodiment
The simulation of body and cylinder+cone in the 5th embodiment calculates：
Wherein, as following table four shows performance of the beam quality factor in these three embodiments in air：
Table four：Beam quality factor in air
Wherein, as following table five shows that dosage shows the performance in these three embodiments：
Table five：Dosage shows
Wherein, as following table six shows the mould for assessing the good and bad parameter of neutron beam dosage performance in these three embodiments
Intend numerical value：
Table six：Assess the good and bad parameter of neutron beam dosage performance
Note：It can be learnt from three above-mentioned tables：Slow body is arranged to it is at least one cone-shaped, its neutron beam
It is preferable to treat benefit.
" cylinder " or " bar shape " described in the embodiment of the present invention refer to along the side of direction as shown to opposite side its
The structure that the overall trend of outline is basically unchanged, a wherein contour line for outline can be line segment, such as cylindrical shape
Corresponding contour line or the larger circular arc close to line segment of curvature, such as the corresponding wheel of the larger sphere body shape of curvature
Profile, the whole surface of outline can be rounding off or non-rounding off, such as in cylindrical shape or curvature
Many raised and grooves are done in the surface of larger sphere body shape.
" cone " or " cone-shaped " described in the embodiment of the present invention refer to along the side of direction as shown to opposite side its
The structure that the overall trend of outline tapers into, a wherein contour line for outline can be line segment, such as cone shape
Corresponding contour line or circular arc, such as the corresponding contour line of sphere body shape, the whole surface of outline can be round and smooth
Transition or non-rounding off, many raised and grooves have such as been done on the surface of cone shape or sphere body shape.
The beam-shaping body for neutron capture treatment that the present invention discloses is not limited to interior described in above example
Structure represented by appearance and accompanying drawing.Done on the basis of the present invention to the material of wherein component, shape and position aobvious and
Easy insight changes, substitutes or changed, all within the scope of protection of present invention.
Claims (10)
- A kind of 1. beam-shaping body for neutron capture treatment, it is characterised in that：The beam-shaping body include beam entrance, Target, the slow body for being adjacent to the target, it is enclosed in the slow external reflector, hankers with what the slow body abutted Sub- absorber, the radiation shield being arranged in the beam-shaping body and beam outlet, the target with from the beam entrance Nuclear reaction occurs for incident proton beam to produce neutron, and the neutron forms neutron beam, and the neutron beam limits a master Axle, the slow body will will deviate from the master from neutron degradation caused by the target to epithermal neutron energy area, the reflector The neutron of axle leads back to the main shaft to improve epithermal neutron intensity of beam, described slowly to set gap between body and the reflector For passage to improve epithermal neutron flux, the clearance channel is that the empty of unused solid material covering easily allows what neutron beam passed through Region, multiple dose was caused with shallow-layer normal structure when the thermal neutron absorber is used to absorb thermal neutron to avoid treatment, institute Radiation shield is stated for shielding neutron and the photon of seepage to reduce the normal tissue dose in non-irradiated area.
- 2. the beam-shaping body according to claim 1 for neutron capture treatment, it is characterised in that：The beam-shaping Body is further used for the treatment of accelerator boron neutron capture.
- 3. the beam-shaping body according to claim 2 for neutron capture treatment, it is characterised in that：Accelerator boron neutron Proton accelerate (beamacceleration), the target are made of metal by capture treatment by accelerator, and the proton beam, which accelerates to, to be enough to overcome target The energy of material atomic nucleus coulomb repulsion, nuclear reaction occurs with the target to produce neutron.
- 4. the beam-shaping body according to claim 1 for neutron capture treatment, it is characterised in that：The beam-shaping Neutron slowly to epithermal neutron energy area, and is reduced thermal neutron and fast neutron content by physical efficiency, and epithermal neutron energy area arrives in 0.5eV Between 40keV, hanker subzone and be less than 0.5eV, fast-neutron range is more than 40keV, and the slow body with fast neutron by acting on The material that section is big, epithermal neutron action section is small is made, the reflector by being made with the strong material of neutron reflection ability, The thermal neutron absorber is made up of the material big with thermal neutron action section.
- 5. the beam-shaping body according to claim 4 for neutron capture treatment, it is characterised in that：The slow body by D2O、AlF3、FluentalTM、CaF2、Li2CO3、MgF2And Al2O3At least one of be made.
- 6. the beam-shaping body according to claim 4 for neutron capture treatment, it is characterised in that：The reflector by At least one of Pb or Ni are made, the thermal neutron absorber by6Li is made, and the thermal neutron absorber and the beam go out Air duct is provided between mouthful.
- 7. the beam-shaping body according to claim 1 for neutron capture treatment, it is characterised in that：The radiation shield Including photon shielding and neutron shield.
- 8. the beam-shaping body according to claim 4 for neutron capture treatment, it is characterised in that：The slow body is set It is set to and includes at least one cone-shaped shape.
- 9. the beam-shaping body according to claim 8 for neutron capture treatment, it is characterised in that：The slow body is set It is set to a cone-shaped shape comprising a bar shape and with bar shape adjoining.
- 10. the beam-shaping body according to claim 8 for neutron capture treatment, it is characterised in that：The slow body Be arranged to two opposite directions adjoin each other it is cone-shaped.
Priority Applications (24)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810009962.1A CN108325092B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
| CN201410743692.9A CN104511096B (en) | 2014-12-08 | 2014-12-08 | Beam-shaping body for neutron capture treatment |
| CN201810009982.9A CN108042930B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
| PL15164481T PL3032927T3 (en) | 2014-12-08 | 2015-04-21 | A beam shaping assembly for neutron capture therapy |
| EP16192908.8A EP3133905B1 (en) | 2014-12-08 | 2015-04-21 | A beam shaping assembly for neutron capture therapy |
| EP17206556.7A EP3316665B1 (en) | 2014-12-08 | 2015-04-21 | 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 |
| PL15164471T PL3032926T3 (en) | 2014-12-08 | 2015-04-21 | A beam shaping assembly for neutron capture therapy |
| DK15164471.3T DK3032926T3 (en) | 2014-12-08 | 2015-04-21 | RADIATING DEVICE FOR NEUTRON COLLECTION THERAPY |
| DK15164481.2T DK3032927T3 (en) | 2014-12-08 | 2015-04-21 | RADIATING DEVICE FOR NEUTRON COLLECTION THERAPY |
| EP15164481.2A EP3032927B1 (en) | 2014-12-08 | 2015-04-21 | A 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 |
| US14/705,811 US9974979B2 (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 |
| TW104122643A TWI581822B (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 |
| 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 |
|---|---|---|---|
| CN201410743692.9A CN104511096B (en) | 2014-12-08 | 2014-12-08 | Beam-shaping body for neutron capture treatment |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201810009962.1A Division CN108325092B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
| CN201810009982.9A Division CN108042930B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
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| Publication Number | Publication Date |
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| CN104511096A CN104511096A (en) | 2015-04-15 |
| CN104511096B true CN104511096B (en) | 2018-01-05 |
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| CN201410743692.9A Active CN104511096B (en) | 2014-12-08 | 2014-12-08 | Beam-shaping body for neutron capture treatment |
| CN201810009982.9A Active CN108042930B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
| CN201810009962.1A Active CN108325092B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
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| CN201810009982.9A Active CN108042930B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
| CN201810009962.1A Active CN108325092B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
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| CN106310540A (en) * | 2015-05-04 | 2017-01-11 | 南京中硼联康医疗科技有限公司 | Beam shaping body for neutron capture therapy |
| EP3254729B1 (en) | 2015-05-04 | 2019-09-04 | Neuboron Medtech Ltd. | Beam shaping body for neutron capture therapy |
| CN107921273B (en) * | 2015-05-04 | 2019-10-01 | 南京中硼联康医疗科技有限公司 | Beam-shaping body for neutron capture treatment |
| CN109568808A (en) * | 2015-09-11 | 2019-04-05 | 南京中硼联康医疗科技有限公司 | Hot-press sintering equipment and sintering process |
| CN106552321A (en) * | 2015-09-28 | 2017-04-05 | 南京中硼联康医疗科技有限公司 | Radiation detecting system and radiation line detecting method for neutron capture treatment system |
| CN109011207B (en) * | 2015-09-28 | 2020-10-16 | 南京中硼联康医疗科技有限公司 | Beam diagnostic system for neutron capture therapy system |
| EP3342458B1 (en) * | 2015-09-30 | 2019-06-05 | Neuboron Medtech Ltd. | Beam shaper for neutron capture therapy |
| CN109771845B (en) * | 2015-10-15 | 2021-07-16 | 南京中硼联康医疗科技有限公司 | Neutron retarding material |
| EP3369457B1 (en) | 2015-11-26 | 2019-11-27 | Neuboron Medtech Ltd. | Beam shaping body for neutron capture therapy |
| 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 |
| CN106938124B (en) * | 2016-01-04 | 2019-10-01 | 南京中硼联康医疗科技有限公司 | The slow material of neutron |
| CN106955427B (en) * | 2016-01-08 | 2019-10-01 | 南京中硼联康医疗科技有限公司 | Beam-shaping body for neutron capture treatment |
| EP3395404B1 (en) * | 2016-01-08 | 2020-08-19 | Neuboron Medtech Ltd. | Beam shaper for neutron capture therapy |
| CN106980136B (en) * | 2016-01-15 | 2024-02-20 | 南京中硼联康医疗科技有限公司 | Radiation detection system for neutron capture treatment system and detection method thereof |
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Also Published As
| Publication number | Publication date |
|---|---|
| CN108325092B (en) | 2020-08-07 |
| CN108042930A (en) | 2018-05-18 |
| CN104511096A (en) | 2015-04-15 |
| CN108042930B (en) | 2020-04-14 |
| CN108325092A (en) | 2018-07-27 |
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