CN108042930A - 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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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,It is adjacent to the slow body of target,It is enclosed in slow external reflector,With the thermal neutron absorber of slow body adjoining,It is arranged on the in vivo radiation shield of beam-shaping and beam outlet,With the proton beam from the incidence of beam entrance nuclear reaction occurs for target to generate neutron,Neutron forms neutron beam,Neutron beam limits an axis,Slow body will be from the neutron degradation that target generates to epithermal neutron energy area,The neutron that reflector will deviate from axis leads back to axis to improve epithermal neutron intensity of beam,Clearance channel is slowly set to improve epithermal neutron flux between body and reflector,Thermal neutron absorber caused multiple dose to avoid when treating for absorbing thermal neutron with shallow-layer normal structure,Radiation shield is used to shield neutron and the photon of leakage 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 bodies for neutron capture treatment.
Background technology
As the development of atomics, such as the radiation cures such as cobalt 60, linear accelerator, electron beam have become cancer
One of main means of disease treatment.However conventional photonic or electronic therapy are limited be subject to radioactive ray physical condition itself, are being killed
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, the target therapy in chemotherapy (chemotherapy)
Concept is just applied in radiation cure；And for the tumour cell of radiation resistance, also actively development has high phase at present
To the radiation source of biological effect (relative biological effectiveness, RBE), as proton therapeutic, heavy particle are controlled
Treatment, neutron capture treatment etc..Wherein, neutron capture treatment is to combine above two concept, if boron neutron capture is treated, by
Boracic drug gathers in the specificity of tumour cell, and accurately neutron beam regulates and controls for cooperation, provides more better than conventional radiation
Treatment of cancer selects.
Boron neutron capture treatment (Boron Neutron Capture Therapy, BNCT) be using boracic (10B) drug
There is the characteristic of high capture cross section to thermal neutron, by10B(n,α)7Li neutron captures and nuclear fission reaction generate4He and7Li two
A 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, and there is High Linear to shift (Linear Energy
Transfer, LET), short range feature, the linear energy transfers of α particles and range are respectively 150keV/ μm, 8 μm, and7Li weights
Lotus particle is then 175keV/ μm, 5 μm, and the integrated range of two particle is approximately equivalent to a cell size, therefore is caused for organism
Radiation injury can be confined to cell level, be gathered in when boracic drug selectivity in tumour cell, appropriate neutron of arranging in pairs or groups
Source is penetrated, just can achieve the purpose that local kill 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 drug,
Occupy key player in the research that the improvement that neutron penetrates source flux and quality is treated in boron neutron capture.
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 for neutron capture treatment
Beam-shaping body, wherein, beam-shaping body includes target, is adjacent to the slow body of target, is enclosed in slow external reflection
Body, with the thermal neutron absorber of slow body adjoining, be arranged on the in vivo radiation shield of beam-shaping and beam and export, target with from
Nuclear reaction occurs for the proton beam of beam entrance incidence to generate neutron, and neutron forms neutron beam, and neutron beam limits an axis
Line, for slow body by from the neutron degradation that target generates to epithermal neutron energy area, the neutron that reflector will deviate from axis leads back to axis
To improve epithermal neutron intensity of beam, between slow body and reflector clearance channel is set to hanker to improve epithermal neutron flux
For absorbing thermal neutron to avoid multiple dose was caused during treatment with shallow-layer normal structure, radiation shield is used to shield sub- absorber
The neutron and photon of leakage 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.
The treatment of accelerator boron neutron capture is by accelerator by proton accelerate (beamacceleration), and target is made of metal, proton accelerate (beamacceleration)
To the energy for being enough to overcome target atom core coulomb repulsion, nuclear reaction occurs with target to generate 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 less than 0.5eV, fast-neutron range is more than 40keV, and slow body is by having between 0.5eV to 40keV
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 of the material big with thermal neutron action section.
As one kind preferably, slow body is by D2O、AlF3、FluentalTM、CaF2、Li2CO3、MgF2And Al2O3In extremely
Few one kind is made.
Further, reflector is made of at least one of Pb or Ni, thermal neutron absorber by6Li is made, thermal neutron
Air duct is equipped between absorber and beam outlet.
Radiation shield includes photon shielding and neutron shield.As one kind preferably, photon shielding is made of Pb, neutron screen
It covers and is made of PE (polyethylene).
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 diagram direction one side to opposite side its
The structure that the overall trend of outer profile is basically unchanged, a wherein contour line for outer profile 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 outer profile can be rounding off or non-rounding off, such as in cylindrical shape or curvature
Many protrusions and groove 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 diagram direction one side to opposite side its
The gradually smaller structure of overall trend of outer profile, a wherein contour line for outer profile 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 outer profile can be round and smooth
Transition or non-rounding off, many protrusions and groove have such as been done on the surface of cone shape or sphere body shape.
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 neutron capture treatment in first embodiment of the invention,
In, it is provided with clearance channel between slow body and reflector.
Fig. 4 is the floor map of the beam-shaping body for neutron capture treatment in second embodiment of the invention,
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 neutron capture treatment in third embodiment of the invention,
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 neutron capture treatment in fourth embodiment of the invention,
In, slow body is arranged to cylinder.
Fig. 8 is the floor map of the beam-shaping body for neutron capture treatment in fifth embodiment of the invention,
In, slow body is arranged to cylinder+cone.
Specific 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 the accelerator, target and hot removal system and beam-shaping body that are accelerated to charged particle (such as proton, deuteron), wherein
Charged particle is accelerated to generate neutron with metal targets effect, it is charged 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 being often discussed
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 can generate the neutron of opposite low energy, be not necessary to too many
Slow processing can be used for clinic, however two kinds of targets of lithium metal (Li) and beryllium metal (Be) and the proton-effect of threshold values energy are cut
Face is not high, to generate sufficiently large neutron flux, the proton of higher-energy is usually selected to trigger nuclear reaction.
Preferable target should possess high neutron yield rate, the neutron energy of generation is distributed (will be under close to epithermal neutron energy area
Text is described in detail), without wear by force too much radiation generate, the characteristics such as cheap easily operated and high temperature resistant of safety, but actually and can not
It finds and meets required nuclear reaction, target made of lithium metal is used in the embodiment of the present invention.But art technology
Known to personnel, the material of target can also be made 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 high.It is adopted in the embodiment of the present invention
With7Li(p,n)7The nuclear reaction of Be.
No matter boron neutron capture treatment nuclear reaction of the neutron source from nuclear reactor or accelerator charged particle and target,
What is generated is all mixed radiation field, i.e., beam contains neutron, photon of the low energy to high energy；It is 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 that should try one's best reduction.Except air beam quality factor, in knowing more about
Son in human body caused by dosage be distributed, carry out Rapid Dose Calculation using human body head tissue prosthese in the embodiment of the present 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) is directed to the neutron source of clinical boron neutron capture treatment, is 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 generate 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 109n/cm2s
Fast neutron pollution Fast neutron contamination<2 x 10-13Gy-cm2/n
Photon contamination Photon contamination<2 x 10-13Gy-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：Subzone is hankered less than 0.5eV, fast-neutron range is more than in epithermal neutron energy area between 0.5eV to 40keV
40keV。
1st, epithermal neutron beam flux：
Boracic drug concentration has codetermined the clinical treatment time in neutron beam flux and tumour.If tumour boracic drug
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 drug
Time, short treatment time in addition to advantageous to patient's positioning and comfort level, also can relatively efficiently use boracic medicine in one hour
Object is in the intra-tumor limited residence time.
2nd, fast neutron pollutes：
Since fast neutron can cause unnecessary normal tissue dose, it is regarded as pollution, this dosage size and neutron
Energy is proportionate, therefore should reduce the content of fast neutron to the greatest extent in neutron beam design.Fast neutron pollution definition is unit
The adjoint fast neutron dosage of epithermal neutron flux, IAEA are less than 2 x 10 to the suggestion that fast neutron pollutes-13Gy-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, IAEA are less than 2 x 10 to the suggestion of gamma-ray contamination-13Gy-cm2/n。
4th, thermal and epithermal neutron flux ratio：
Since 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 be treated by the use of thermal neutron as boron neutron capture, swell 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, in addition also improve 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 dosage 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 dosage 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 is referred to as effective
Therapeutic dose ratio；The calculating of mean dose can be integrated to obtain by dose versus depth curve.Dose therapeutically effective ratio is bigger, represents
The treatment benefit of the neutron beam is better.
Compare foundation in order to which beam-shaping body is made to have in design, in the air suggested except five IAEA beam quality because
Three plain and above-mentioned parameters are also utilized in the embodiment of the present invention following for assessing the good and bad ginseng of neutron beam dosage performance
Number：
1st, irradiation time≤30min (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) is 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, the embodiment of the present invention is to be directed to penetrating for neutron capture treatment
The improvement that beam shaping body proposes is the beam-shaping body being directed to for the treatment of accelerator boron neutron capture as one kind preferably
Improvement.As shown in figure 3, the beam-shaping body 10 for neutron capture treatment in first embodiment of the invention, including penetrating
Beam entrance 11, target 12, the slow body 13 for being adjacent to target 12, 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 generate neutron, and neutron forms neutron beam, and neutron beam limits one
Axis X, by from the neutron degradation that target 12 generates to epithermal neutron energy area, reflector 14 will deviate from axis X slow body 13
Son leads back to 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, thermal neutron absorber 15 caused multi-agent to avoid when treating for absorbing thermal neutron with shallow-layer normal structure
Amount, radiation shield 16 are used to shield neutron and the photon of leakage 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 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 generate 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 of the material big with thermal neutron action section, as a kind of preferred reality
Apply example, thermal neutron absorber 15 by6Li is made, and air duct 19 is equipped 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) photon shielding 161 and the neutron shield 162 made of polyethylene (PE) made of.
Wherein, slow body 13 is arranged to two opposite directions and adjoins each other cone-shaped, as shown in Figure 3 direction, slowly
The left side of body 13 is gradually smaller cone-shaped towards left side, and the right side of slow body 13 is towards the gradually smaller cone in right side
Shape, the two adjoin each other.As one kind preferably, the left side of slow body 13 is arranged to gradually smaller cone-shaped towards left side,
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
Be the covering of unused solid material it is empty easily allow neutron beam by region, lead to as the clearance channel 18 could be provided as 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 shield
Covering the shielding of the photon made of Pb in 16 161 can be integrated with the setting of reflector 14, can also be arranged to split, and radiate
The neutron shield 162 made of PE can be positioned adjacent to the position of beam outlet 17 in shielding 16.In thermal neutron absorber 15
Air duct 19 is provided between beam outlet 17, the sustainable neutron that will deviate from axis X leads back to axis X to carry in this region
High epithermal neutron intensity of beam.Prosthese B, which is arranged on, to be exported apart from beam at 17 about 1cm.It is well known to those skilled in the art, photon
Shielding 161 can be made of other materials, as long as playing the role of shielding photon, neutron shield 162 can also be by other
Material is made, and can also set elsewhere, as long as disclosure satisfy that the condition of shielding leakage 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, which includes beam entrance 21, target 22, adjoining
Slow body 23 in 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 21 incidence of beam entrance
Generation nuclear reaction is to generate neutron, and neutron forms neutron beam, and neutron beam limits an axis X 1, and slow body 23 will be from target
22 neutron degradations generated are to epithermal neutron energy area, and reflector 24 will deviate from the neutron of axis X 1, and to lead back to 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 is gradually smaller cone-shaped, and the right side of slow body 23 is gradually smaller cone-shaped towards right side, and the two adjoins each other, heat
Neutron absorber 25 for causing multiple dose with shallow-layer normal structure when absorbing thermal neutron to avoid treatment, use by radiation shield 26
In shielding leakage 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 in first embodiment with radiation shield 26, and radiation shield therein 26 includes the photon made of lead (Pb)
Shielding 261 and the neutron shield 262 made of polyethylene (PE), 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.
Refer to Fig. 5, the beam-shaping body 30 include beam entrance 31, target 32, the slow body 33 for being adjacent to target 32,
The reflector 34 being enclosed in outside slow body 33 and the thermal neutron absorber 35 of slow body 33 adjoining are 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 31 incidence of beam entrance to generate
Son, neutron formed neutron beam, neutron beam limit an axis X 2, slow body 33 by the neutron degradation generated from target 32 extremely
Epithermal neutron energy area, the neutron that reflector 34 will deviate from axis X 2 lead back to 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 towards the gradually smaller cone in left side
Shape, the right side of slow body 33 is gradually smaller cone-shaped towards right side, and the two adjoins 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 for shield the neutron of leakage 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 in first embodiment with radiation shield 36, and radiation shield therein 36 includes the photon made of lead (Pb)
Shielding 361 and the neutron shield 362 made of polyethylene (PE), 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.
(it is below by Los Alamos National Laboratories of the U.S. (LosAlamos National using MCNP softwares
Laboratory) exploitation based on Monte Carlo method for calculating neutron in 3 D complex geometry, photon, charged
Particle or the common software bag for coupling neutron/photon/charged particle transport problem) simulation of these three embodiments is calculated：
Wherein, as following table one shows that performance of the beam quality factor in these three embodiments is (in form respectively in air
Name lexeme is same as above, and details are not described herein, 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
| Dosage shows | Slow body filling clearance channel | Reflector fills clearance channel | Clearance channel |
| Effective therapeutic depth | 10.9 | 10.9 | 11.0 |
| Effective therapeutic depth dosage rate | 4.47 | 4.60 | 4.78 |
| Dose therapeutically effective ratio | 5.66 | 5.69 | 5.68 |
Wherein, as following table three shows mould of the good and bad parameter of assessment 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 neutron beam are best.
Since the neutron generated from lithium target has the higher characteristic of Forward averaging energy, 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 theoretically can reach neutron 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, which wraps
Include beam entrance 41, target 42, the slow body 43 for being adjacent to 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 generate neutron from the incident proton beam of beam entrance 41, slow body 43 subtracts the neutron generated from target 42
Speed is to epithermal neutron energy area, and the neutron that reflector 44 will deviate from leads 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, thermal neutron absorber 45 is for absorbing thermal neutron to avoid during treatment and shallow-layer
Normal structure caused multiple dose, and radiation shield 46 is used to shield neutron and the photon of leakage to reduce normal group of 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, which wraps
Include beam entrance 51, target 52, the slow body 53 for being adjacent to 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 generate neutron, neutron forms neutron beam, and neutron beam limits
One axis X 3, for slow body 53 by from the neutron degradation that target 52 generates to epithermal neutron energy area, reflector 54 will deviate from axis
The neutron of X3 leads back to 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 gradually smaller cone-shaped, the two phase towards right side
Mutually adjacent, thermal neutron absorber 25 caused multiple dose, spoke to avoid when treating for absorbing thermal neutron with shallow-layer normal structure
It penetrates shielding 26 and is used to shield neutron and the photon of leakage 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 in first embodiment with radiation shield 56, and radiation shield therein 56 includes the photon made of lead (Pb)
Shielding 561 and the neutron shield 562 made of polyethylene (PE), 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
| Dosage shows | Cylinder | Cylinder+cone | Bicone |
| Effective therapeutic depth | 11.8 | 10.9 | 10.9 |
| Effective therapeutic depth dosage rate | 2.95 | 4.28 | 4.47 |
| Dose therapeutically effective ratio | 5.52 | 5.66 | 5.66 |
Wherein, as following table six shows mould of the good and bad parameter of assessment neutron beam dosage performance in these three embodiments
Intend numerical value：
Table six：Assess the good and bad parameter of neutron beam dosage performance
| Parameter | Cylinder | Cylinder+cone | Bicone |
| Irradiation time (10mA) | 40.7 | 26.1 | 25.3 |
| 30.2RBE-Gy can treat depth | 8.4 | 7.6 | 7.7 |
| Tumour maximum dose | 70.9 | 67.4 | 68.5 |
| Normal cerebral tissue's maximum dose | 12.0 | 11.2 | 11.3 |
| Skin maximum dose | 11.0 | 11.0 | 11.0 |
Note：It can be learnt from three above-mentioned tables：Slow body is arranged to it is at least one cone-shaped, neutron beam
It is preferable to treat benefit.
" cylinder " or " bar shape " described in the embodiment of the present invention refer to along diagram direction one side to opposite side its
The structure that the overall trend of outer profile is basically unchanged, a wherein contour line for outer profile 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 outer profile can be rounding off or non-rounding off, such as in cylindrical shape or curvature
Many protrusions and groove 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 diagram direction one side to opposite side its
The gradually smaller structure of overall trend of outer profile, a wherein contour line for outer profile 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 outer profile can be round and smooth
Transition or non-rounding off, many protrusions and groove 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 attached drawing.On the basis of the present invention to done aobvious of the material of wherein component, shape and position and
Easy insight changes, substitutes or changes, all within the scope of protection of present invention.
Claims (10)
1. a kind of 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 are enclosed in the slow external reflector, are arranged in the beam-shaping body
Radiation shield and beam outlet, the target with from the generation nuclear reaction of the proton beam of beam entrance incidence to generate in
Son, the neutron form neutron beam, and the slow body will be from the neutron degradation that the target generates to epithermal neutron energy area, institute
Stating slow body has the first side of close beam entrance and the second side away from beam entrance, and the distance that target to beam exports is small
In the distance that first side is exported to beam, the neutron that the reflector will deviate from leads back to improve epithermal neutron beam strong
Degree, the radiation shield are used to shield neutron and the photon of leakage 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 neutron beam
An axis is limited, the slow body first equipped at least one separate beam outlet is cone-shaped, and first side is first
The one side of cone-shaped close beam entrance, the described first cone-shaped the 3rd side for further including separate beam entrance, first cone
The outer profile of body shape is tapered into along the 3rd side to the first side overall trend, and the target is located at the first side in the axial direction
Between the 3rd side.
3. the beam-shaping body according to claim 2 for neutron capture treatment, it is characterised in that：The slow body is also
Cone-shaped equipped with second with the described first cone-shaped adjoining and close to beam outlet, the second side is cone-shaped close for second
The one side of beam outlet, the described second cone-shaped the 4th side for further including separate beam outlet, the described second cone-shaped foreign steamer
Exterior feature is tapered into along the 4th side to the second side overall trend.
4. the beam-shaping body according to claim 2 for neutron capture treatment, it is characterised in that：The slow body is also
Equipped with the described first cone-shaped adjoining and close to the bar shape of beam outlet, the second side exports for bar shape close to beam
One side.
5. the beam-shaping body according to claim 1 for neutron capture treatment, it is characterised in that：The neutron beam
An axis is limited, the slow body is equipped with the bar shape of at least one separate beam outlet, and first side is leaned on for bar shape
The one side of close-range shot beam entrance, the bar shape further include the 3rd side away from beam entrance, target position in the axial direction
Between the first side and the 3rd side.
6. 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, the treatment of accelerator boron neutron capture by accelerator by proton accelerate (beamacceleration),
The target is made of metal, and the proton beam accelerates to the energy for being enough to overcome target atom core coulomb repulsion, with the target
Nuclear reaction occurs for material to generate neutron.
7. the beam-shaping body according to claim 1 for neutron capture treatment, it is characterised in that：The slow body and
The clearance channel of unused entity covering is set to improve epithermal neutron flux between the reflector.
8. the beam-shaping body according to claim 7 for neutron capture treatment, it is characterised in that：The beam-shaping
Body is additionally provided with the thermal neutron absorber with the slow body adjoining, the clearance channel by the reflector, the slow body and
The thermal neutron absorber surrounds.
9. the beam-shaping body according to claim 1 for neutron capture treatment, it is characterised in that：The neutron beam
An axis is limited, the beam entrance, slow body and beam outlet extend each along neutron beam axis.
10. the beam-shaping body according to claim 1 for neutron capture treatment, it is characterised in that：The neutron is penetrated
Beam limits an axis, and direction of first side along the axis toward the beam entrance protrudes the target, and described the
The direction that two sides are exported along the axis toward the beam protrudes the target.
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| CN201810009982.9A CN108042930B (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 |
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| CN201410743692.9A Active CN104511096B (en) | 2014-12-08 | 2014-12-08 | Beam-shaping body for neutron capture treatment |
| CN201810009962.1A Active CN108325092B (en) | 2014-12-08 | 2014-12-08 | Beam shaping body for neutron capture therapy |
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Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007242422A (en) * | 2006-03-08 | 2007-09-20 | Mitsubishi Heavy Ind Ltd | Neutron generator and neutron irradiation system |
| JP2008022920A (en) * | 2006-07-18 | 2008-02-07 | Hitachi Ltd | Medical device for boron neutron capture therapy |
| EP1895819A1 (en) * | 2006-08-29 | 2008-03-05 | Ion Beam Applications S.A. | Neutron generating device for boron neutron capture therapy |
| CN101829409A (en) * | 2009-03-13 | 2010-09-15 | 住友重机械工业株式会社 | Neutron ray rotary irradiation device |
| CN202802547U (en) * | 2012-06-15 | 2013-03-20 | 北京凯佰特科技有限公司 | Neutron beam irradiating apparatus of a hospital neutron irradiator |
| JP2014115122A (en) * | 2012-12-06 | 2014-06-26 | Mitsubishi Heavy Industries Mechatronics Systems Ltd | Neutron speed adjusting device and neutron generator |
Family Cites Families (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3534760C1 (en) * | 1985-09-28 | 1987-05-07 | Bbc Reaktor Gmbh | Device for generating thermal neutrons |
| WO2012014671A1 (en) * | 2010-07-28 | 2012-02-02 | 住友重機械工業株式会社 | Neutron ray irradiation device, and method for control of neutron ray irradiation device |
| CN202236912U (en) * | 2011-03-02 | 2012-05-30 | 长春工业大学 | Boron neutron capture treatment device based on D-T neutron emitter |
| JP5630666B2 (en) * | 2012-03-30 | 2014-11-26 | 住友重機械工業株式会社 | Neutron capture therapy collimator and neutron capture therapy device |
| JP5996470B2 (en) * | 2013-03-29 | 2016-09-21 | 住友重機械工業株式会社 | Neutron capture therapy device |
| JP6042269B2 (en) * | 2013-05-22 | 2016-12-14 | 住友重機械工業株式会社 | Neutron capture therapy device and neutron beam measurement method |
| CN204319540U (en) * | 2014-12-08 | 2015-05-13 | 南京中硼联康医疗科技有限公司 | For the beam-shaping body of neutron capture treatment |
-
2014
- 2014-12-08 CN CN201810009982.9A patent/CN108042930B/en active Active
- 2014-12-08 CN CN201410743692.9A patent/CN104511096B/en active Active
- 2014-12-08 CN CN201810009962.1A patent/CN108325092B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007242422A (en) * | 2006-03-08 | 2007-09-20 | Mitsubishi Heavy Ind Ltd | Neutron generator and neutron irradiation system |
| JP2008022920A (en) * | 2006-07-18 | 2008-02-07 | Hitachi Ltd | Medical device for boron neutron capture therapy |
| EP1895819A1 (en) * | 2006-08-29 | 2008-03-05 | Ion Beam Applications S.A. | Neutron generating device for boron neutron capture therapy |
| CN101829409A (en) * | 2009-03-13 | 2010-09-15 | 住友重机械工业株式会社 | Neutron ray rotary irradiation device |
| CN202802547U (en) * | 2012-06-15 | 2013-03-20 | 北京凯佰特科技有限公司 | Neutron beam irradiating apparatus of a hospital neutron irradiator |
| JP2014115122A (en) * | 2012-12-06 | 2014-06-26 | Mitsubishi Heavy Industries Mechatronics Systems Ltd | Neutron speed adjusting device and neutron generator |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110523007A (en) * | 2018-05-25 | 2019-12-03 | 中硼(厦门)医疗器械有限公司 | Neutron capture treatment system |
| CN110523007B (en) * | 2018-05-25 | 2024-04-19 | 中硼(厦门)医疗器械有限公司 | Neutron capture therapy system |
| CN114225232A (en) * | 2021-09-26 | 2022-03-25 | 散裂中子源科学中心 | Beam shaping body with rotary target body |
| CN115300812A (en) * | 2022-08-31 | 2022-11-08 | 兰州大学 | Neutron beam grating irradiation system |
Also Published As
| Publication number | Publication date |
|---|---|
| CN104511096A (en) | 2015-04-15 |
| CN108325092A (en) | 2018-07-27 |
| CN108325092B (en) | 2020-08-07 |
| CN108042930B (en) | 2020-04-14 |
| CN104511096B (en) | 2018-01-05 |
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Application publication date: 20180518 Assignee: China Boron (Xiamen) Medical Devices Co., Ltd. Assignor: NEUBORON MEDTECH LTD. Contract record no.: X2019320000054 Denomination of invention: Beam shaping body for neutron capture therapy License type: Common License Record date: 20190910 |
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