CN109420261A - Neutron capture treatment system - Google Patents
Neutron capture treatment system Download PDFInfo
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- CN109420261A CN109420261A CN201710760913.7A CN201710760913A CN109420261A CN 109420261 A CN109420261 A CN 109420261A CN 201710760913 A CN201710760913 A CN 201710760913A CN 109420261 A CN109420261 A CN 109420261A
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- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 10
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Classifications
-
- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
-
- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N2005/1085—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy characterised by the type of particles applied to the patient
- A61N2005/109—Neutrons
Abstract
The application provides a kind of neutron capture treatment system, including beam-shaping body, it is set to the intracorporal vacuum tube of beam-shaping and at least one cooling device, the beam-shaping body includes beam entrance, accommodate the accommodating chamber of the vacuum tube, it is adjacent to the slow body of the accommodating chamber end, it is enclosed in the slow external reflector, setting is exported in the intracorporal radiation shield of the beam-shaping and beam, the vacuum tube end is equipped with target, the cooling device is for cooling down target, nuclear reaction occurs for the target to generate neutron with the charged particle beam from the beam entrance incidence, the slow body will be from the neutron degradation that the target generates to epithermal neutron energy area, the neutron that the reflector will deviate from is back to the slow body to improve epithermal neutron intensity of beam, at least one appearance is additionally provided in the beam-shaping body It receives the receiving pipeline of the cooling device, filler is filled between the cooling device and the inner wall for accommodating pipeline.
Description
Technical field
The present invention relates to a kind of radioactive ray irradiation system more particularly to a kind of neutron capture treatment systems.
Background technique
As the radiation cures such as the development of atomics, such as cobalt 60, linear accelerator, electron beam have become cancer
One of the main means of disease treatment.However conventional photonic or electronic therapy are limited by radioactive ray physical condition itself, are being killed
While dead tumour cell, normal tissue a large amount of 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
Tumor (glioblastoma multiforme), melanocytoma (melanoma)) treatment effect it is often bad.
Target therapy in order to reduce the radiation injury of tumour surrounding normal tissue, in chemotherapy (chemotherapy)
Concept is just applied in radiation cure；And it is directed to 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 selection.
In accelerator neutron capture treatment system, by accelerator by charged particle beam acceleration, the charged particle beam
The energy for being enough to overcome the intracorporal target atom core coulomb repulsion of beam-shaping is accelerated to, nuclear reaction occurs to produce with the target
Raw neutron, therefore target will receive the high-power irradiation for accelerating charged particle beam, the temperature of target during generating neutron
Degree can be substantially increased, to influence the service life of target.
A kind of neutron capture treatment system with cooling device, generally comprises the tubulose second for inputting cooling medium
It cooling end, the tubulose third cooling end for exporting cooling medium and is connected between second, third cooling end direct with target
Contact the first cooling end for cooling down target.In this configuration, second, third cooling end of tubulose is exposed in air,
The part neutron generated on target by from around second, third cooling end pass through air in scatter to outside beam-shaping body,
To reduce the yield of effective neutron, and scattering to the neutron outside beam-shaping body will be in neutron capture treatment system
Instrument has an impact and is likely to result in radiation leaks, reduces the service life of neutron capture treatment system and there is radiation peace
Full hidden danger.
Summary of the invention
To solve the above-mentioned problems, one embodiment of the application provides a kind of neutron capture treatment system comprising penetrates
Beam shaping body is set to the intracorporal vacuum tube of beam-shaping and at least one cooling device, beam-shaping body include beam entrance,
The accommodating chamber for accommodating vacuum tube, the slow body for being adjacent to accommodating chamber end are enclosed in slow external reflector, are adjacent with slow body
The thermal neutron absorber that connects, setting are exported in the intracorporal radiation shield of beam-shaping and beam, and vacuum tube end is equipped with target, cold
But device is for cooling down target, target with from the generation nuclear reaction of the charged particle beam of beam entrance incidence to generate in
Son, neutron formed neutron beam, neutron beam limit a neutron beam axis, slow body by the neutron degradation generated from target extremely
Epithermal neutron energy area, the neutron that reflector will deviate from improve epithermal neutron intensity of beam, neutron absorption back to slow body
Body caused multi-dose for absorbing thermal neutron with shallow-layer normal tissue when treatment, radiation shield is used to shield leakage
Neutron and photon are additionally provided at least one in beam-shaping body and accommodate cooling device to reduce the normal tissue dose in non-irradiated area
Receiving pipeline, cooling device and accommodate pipeline inner wall between be filled with filler.
Compared with prior art, the technical solution that the present embodiment is recorded has the advantages that in cooling device and holds
Receive pipeline inner wall between fill filler, improve the service life of neutron capture therapeutic device, prevent neutron from revealing and enhancing
Neutron beam intensity.
Preferably, filler is to be not filled by fill out between aluminium alloy or metal, with cooling device and the inner wall of receiving pipeline
The technical solution for filling object is compared, and epithermal neutron yield can be effectively improved, and is reduced fast neutron pollution, is shortened irradiation time.
Further, pipeline is accommodated to be located at except the inner wall of the accommodating chamber.
Preferably, cooling device includes for cooling down the first cooling end of target, being located at the first cooling end two sides and difference
The second cooling end and third cooling end being connected to the first cooling end；The receiving pipeline includes between target and slow body
First receiving pipeline and positioned at first receiving pipeline two sides and respectively with first receiving pipeline be connected to second, third accommodate pipe
Road, the first, second, third cooling end are respectively received in the first, second, third receiving pipeline, and the filler is filled in
Two cooling ends and second accommodate between the inner wall and third cooling end and the inner wall of third receiving pipeline of pipeline.
Further, second, third cooling end is tubular structure, and described second, third accommodates pipeline and be arranged to along parallel
In neutron beam axis direction extend cross section be circular pipeline.
Preferably, the first cooling position contacts, second cooling end in the end of vacuum tube with the target plane
Extend and be located at the two sides up and down of vacuum tube along the direction for being parallel to neutron beam axis with third cooling end and with first
Cooling end forms Contraband type structure；Second, third accommodates pipeline and extends and be located at along the direction for being parallel to neutron beam axis
The two sides up and down of vacuum tube and with it is described first accommodate pipeline formed Contraband type structure.
Preferably, the first cooling position contacts, second cooling end in the end of vacuum tube with the target plane
Angle between third cooling end and neutron beam axis is greater than 0 ° and is less than or equal to 180 °；Second, third accommodates pipeline neutron
Angle between beam axis is greater than 0 ° and is less than or equal to 180 °.
Preferably, the second cooling end inputs cooling medium to the first cooling end, and the third cooling end is by the first cooling end
In cooling medium output.
Further, reflector protrudes slow body in the two sides of neutron beam axis, and the vacuum tube includes being reflected
The extended segment and extend the insertion section for being embedded in slow body from extended segment that body surrounds, the target are set to the end of the insertion section.
Preferably, slow body is arranged to comprising at least one cone.
" cone " described in the embodiment of the present application or " cone " refer to along diagram direction side to the other side its
A wherein contour line for the gradually smaller structure of the overall trend of outer profile, outer profile can be line segment, such as coniform body
Corresponding contour line, is also possible to circular arc, and such as the corresponding contour line of spherical surface body, the whole surface of outer profile can be round and smooth mistake
It crosses, is also possible to non-rounding off, such as done many protrusions and groove on the surface of coniform body or spherical surface body.
Detailed description of the invention
Fig. 1 is the schematic diagram of the neutron capture treatment system in the embodiment of the present application one, wherein the second of cooling device is cold
But portion and third cooling end are parallel with neutron beam axis；
Fig. 2 be in the embodiment of the present application one along Fig. 1 perpendicular to the neutron capture treatment system of neutron beam axis
Cross-sectional view；
Fig. 3 is the schematic diagram of the neutron capture treatment system in the embodiment of the present application one, wherein vacuum tube and beam-shaping
Gap between body is not filled by filler；
Fig. 4 is the partial enlargement diagram of the cooling device of the neutron capture treatment system in the embodiment of the present application one；
Fig. 5 is the schematic diagram of the neutron capture treatment system in the embodiment of the present application two, wherein the second of cooling device is cold
But portion and third cooling end are vertical with neutron beam axis；
Fig. 6 is the schematic diagram of the neutron capture treatment system in the embodiment of the present application three, wherein the second of cooling device is cold
But the angle of portion and third cooling end and neutron beam axis is greater than 90 °；
Fig. 7 is the target material structure schematic diagram in the neutron capture treatment system in the embodiment of the present application.
Specific embodiment
Neutron capture treatment as a kind of effective treating cancer means in recent years using gradually increasing, 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 Shen
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 embodiment please
It is whole in accelerator, neutron generating unit and the hot removal system and beam accelerated to charged particle (such as proton, deuteron)
Body.Wherein accelerate charged particle and the effect of metal neutron generating unit to generate neutron, according to required neutron yield rate and energy, can
The characteristics such as the acceleration charged particle energy of offer and the materialization of size of current, metal neutron generating unit are anti-to select suitable core
It answers.The nuclear reaction being often discussed has7Li(p,n)7Be and9Be(p,n)9B, both reactions are all the endothermic reaction, two kinds of nuclear reactions
Energy threshold be respectively 1.881MeV and 2.055MeV.Since the ideal neutron source of boron neutron capture treatment is keV energy etc.
The epithermal neutron of grade can produce phase if being theoretically only slightly taller than the proton bombardment lithium metal neutron generating unit of threshold values using energy
To the neutron of low energy, clinic can be used for by being not necessary to too many slow processing, however in two kinds of lithium metal (Li) and beryllium metal (Be)
Sub- generating unit and the proton-effect section of threshold values energy be not high, to generate sufficiently large neutron flux, usually selects higher-energy
Proton cause nuclear reaction.
Ideal target should have high neutron yield rate, the neutron energy of generation is distributed (will be under close to epithermal neutron energy area
Text detailed description), 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.Using target made of lithium metal in embodiments herein.But art technology
Known to personnel, the material of target can also be made of other metal materials other than 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 embodiments herein
With7Li(p,n)7The nuclear reaction of Be.It follows that being accelerated the temperature of the target of charged particle beam irradiation by same high-energy level
It will necessarily be substantially increased, to influence the service life of target.
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.The boron neutron of deep tumor is caught
Treatment is obtained, other than epithermal neutron, remaining radiation content is more, causes the ratio of the non-selective dosage deposition of normal tissue
It is bigger, therefore these radiation that will cause unnecessary dosage should reduce as far as possible.In addition to 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 embodiments herein, and
With prosthese beam quality factor as the design reference of neutron beam, will be described in more detail below.
International Atomic Energy Agency (IAEA) is directed to the neutron source of clinical boron neutron capture treatment, penetrates given five air
Beam quality factor suggestion, this five suggestions can be used for the superiority and inferiority of the different neutron sources of comparison, and be provided with as select neutron generate way
Reference frame when diameter, design beam-shaping body.This five suggestion difference are as follows:
Epithermal neutron beam flux Epithermal neutron flux > 1x 109n/cm2s
Fast neutron pollutes Fast neutron contamination < 2x 10-13Gy-cm2/n
Photon contamination Photon contamination < 2x 10-13Gy-cm2/n
Ratio < 0.05 thermal and epithermal neutron flux ratio thermal to epithermal neutron flux
Middle electron current and ratio > 0.7 flux ratio epithermal neutron current to flux
Note: subzone is hankered less than 0.5eV, fast-neutron range is greater than between 0.5eV to 40keV in epithermal neutron energy area
40keV。
1, 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, needing high pass if boracic drug concentration is low in tumour
Epithermal neutron is measured to give tumour enough dosage.Requirement of the IAEA for epithermal neutron beam flux is per second every square centimeter
Epithermal neutron number be greater than 109, the neutron beam under this flux can substantially control treatment for current boracic drug
Time, short treatment time, can also relatively effective use boracic medicine other than advantageous to patient's positioning and comfort level in one hour
Object limited residence time in tumour.
2, fast neutron pollutes:
Since fast neutron will cause unnecessary normal tissue dose, regard as pollution, this dosage size and neutron
Energy is positively correlated, 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 2x 10 to the suggestion that fast neutron pollutes-13Gy-cm2/n。
3, photon contamination (gamma-ray contamination):
Gamma-rays, which 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 2x 10 to the suggestion of gamma-ray contamination-13Gy-cm2/n。
4, 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
It is swollen for deep layers such as brain tumors outside the neutron source that the Several Epidermal Tumors such as melanocytoma need to use thermal neutron to treat as boron neutron capture
Tumor should reduce thermal neutron content.IAEA is less than 0.05 to thermal and epithermal neutron flux ratio suggestion.
5, middle electron current and flux ratio:
Middle electron current and flux ratio represent the directionality of beam, and tropism is good before the bigger expression neutron beam of ratio, high
The neutron beam of preceding tropism can reduce because neutron diverging caused by normal surrounding tissue dosage, in addition also improve can treat depth and
Put pose gesture elasticity.IAEA centering electron current and flux ratio suggestion are greater than 0.7.
In order to make the beam-shaping body of neutron capture treatment system while solving the problems, such as that target is cooling, can obtain compared with
Good neutron beam quality, referring to Fig.1-4, the embodiment of the present application one provides a kind of neutron capture treatment system 1, and neutron capture is controlled
Treatment system 1 includes beam-shaping body 10, cooling device 20 and vacuum tube 30 in beam-shaping body 10.
As depicted in figs. 1 and 2, beam-shaping body 10 include beam entrance 11, the accommodating chamber 12 for accommodating vacuum tube 30,
Receiving pipeline 13, the slow body 14 for being adjacent to 12 end of accommodating chamber for accommodating cooling device 20 surround the anti-of slow body 14
Beam 15, the thermal neutron absorber 16 adjacent with slow body 14, the radiation shield 17 and beam being arranged in beam-shaping body 10
Outlet 18.The end of vacuum tube 30 is equipped with target 31, target 31 and electrification incident and across vacuum tube 30 from beam entrance 11
Nuclear reaction occurs for the particle beams to generate neutron, and neutron forms neutron beam, and neutron beam projects from beam outlet 18 and limits one
The neutron beam axis X that the central axis of root and vacuum tube 30 essentially coincides.Slow body 14 subtracts the neutron generated from target 31
For speed to epithermal neutron energy area, reflector 15 will deviate from the neutron of neutron beam axis X back to slow body 14 to improve in superthermal
Sub-beam intensity.Reflector 15 protrudes slow body 14 in the two sides of neutron beam axis X.Thermal neutron absorber 16 is for absorbing
Multi-dose was caused with shallow-layer normal tissue when thermal neutron is to avoid treatment.Radiation shield 17 is used to shield the neutron and light of leakage
Son is to reduce the normal tissue dose in non-irradiated area.
Accelerator neutron capture treatment system by accelerator by charged particle beam acceleration, as a kind of preferred embodiment,
Target 31 is made of lithium metal, and charged particle beam accelerates to the energy for being enough to overcome target atom core coulomb repulsion, with target 31
Occur7Li(p,n)7To generate neutron, beam-shaping body 10 can be by neutron slowly to epithermal neutron energy area, and reduces for Be nuclear reaction
Thermal neutron and fast neutron content.Slow body 14 is by the material system big with fast neutron action section, epithermal neutron action section is small
At reflector 15 with the strong material of neutron reflection ability by being made, and thermal neutron absorber 16 is by big with thermal neutron action section
Material be made.As a kind of preferred embodiment, slow body 14 is by D2O、AlF3、FluentalTM、CaF2、Li2CO3、MgF2With
Al2O3At least one of be made, reflector 15 is made of at least one of Pb or Ni, thermal neutron absorber 16 by6Li system
At.
As shown in Figure 1, slow body 14 is arranged to the structure at least one cone to improve epithermal neutron flux.
In the present embodiment, slow body 14 is made of two cones.Slow body 14 has first end 141, the second end 142 and is located at
Third end 143 between first end 141 and the second end 142.First, second, third end 141,142,143 it is transversal
Face is circle, and the diameter of first end 141 and the second end 142 is less than the diameter of third end 143.141 He of first end
First cone 146 is formed between third end 143, and second cone cell is formed between third end 143 and the second end 142
Body 148." cone " or " cone " structure of slow body refers to slow body along neutron beam axis X in the embodiment of the present application
The side in direction to the other side, the gradually smaller structure of the overall trend of outer profile, outer profile wherein a contour line can
To be line segment, such as corresponding contour line of coniform body is also possible to circular arc, such as the corresponding contour line of spherical surface body, outer profile
Whole surface can be rounding off, be also possible to non-rounding off, such as done on the surface of coniform body or spherical surface body
Many protrusions and grooves.
Radiation shield 17 includes photon shielding 171 and neutron shield 172, as a kind of preferred embodiment, radiation shield 17
Including the shielding of the photon made of lead (Pb) 171 and the neutron shield 172 made of polyethylene (PE).
Accommodating chamber 12 be enclosed as the first cone 146 of reflector 15 and slow body 14 set made of cylindrical cavity.It accommodates
Chamber 12 include enclosed as reflector 15 set made of reflector accommodating chamber 121 and reflexive beam accommodating chamber 121 extend by slow body 14
Enclose slow body accommodating chamber 122 made of setting.
Accommodating pipeline 13 includes extending and being located at 12 two sides of accommodating chamber and the setting of 180 ° of interval along neutron beam axis X direction
Second, third accommodate pipeline 132,133 and be arranged in the plane vertical with neutron beam axis X and be located at target 31 and slow
First between fast body 14 accommodates pipeline 131.Second, third accommodates pipeline 132,133 and prolongs on the direction of neutron beam axis X
It extends over accommodating chamber 12 and is connected to respectively with the first receiving pipeline 131.That is, the first receiving pipeline 131 is located at accommodating chamber
12 end and it is located between target 31 and slow body 14, the second receiving pipeline 132 and third accommodate pipeline 133 and be located at appearance
Receive chamber 12 two sides and respectively with first receiving pipeline 131 be connected to so that entirely accommodate pipeline 30 be in " Contraband " type structure set
It sets.As shown in connection with fig. 3, second, third accommodate pipeline 132,133 respectively include being located at the second of the outside of reflector accommodating chamber 121,
Third reflector accommodates pipeline 1321,1331 and accommodates the extension of pipeline 1321,1331 from second, third reflector respectively and be located at
Second, third slow body in slow 122 outside of body accommodating chamber accommodates pipeline 1322,1332.In present embodiment, second, third
It accommodates pipeline 132,133 to extend along neutron beam axis X direction and be parallel to neutron beam axis X, i.e., second, third accommodates pipe
Angle between road 132,133 and neutron beam axis X is 0 °.
In the present embodiment, second, third accommodates pipeline 132,133 and is connected to accommodating chamber 12, that is, is contained in accommodating chamber 12
The outer surface part of interior vacuum tube 30 is exposed to second, third and accommodates in pipeline 132,133, in other embodiments, the
Two, third accommodates pipeline 132,133 and can not be connected to accommodating chamber 12, i.e., second, third accommodates pipeline 132,133 and accommodating chamber
It is separated between 12 by reflector 15 and slow body 14.To sum up, second, third receiving pipeline 132,133 is located at the interior of accommodating chamber 12
Except wall.In the application embodiment, second, third accommodates pipeline 132,133 and is arranged to the axis direction along vacuum tube 30
The arc shape pipeline of extension can also be replaced in other embodiments with the pipeline of rectangular, triangle or other polygons.?
In the application embodiment, it is to be spaced apart on the circumferencial direction of accommodating chamber 12 mutually solely that second, third, which accommodates pipeline 132,133,
Two vertical receiving pipelines, in other embodiments, second, third accommodates pipeline 132,133 in the circumference side of accommodating chamber 12
Connection upwards is replaced by a receiving pipeline around accommodating chamber 12.
Vacuum tube 30 includes the extended segment 32 surrounded by reflector 15 and extends the embedding of the slow body 14 of insertion from extended segment 32
Enter section 34, i.e. extended segment 32 is contained in reflector accommodating chamber 121, and insertion section 34 is contained in slow body accommodating chamber 122.Target
31 are set to the end of the insertion section 34 of vacuum tube 30.In present embodiment, 30 part of vacuum tube is embedded in slow body 14, in order to
Make the target 31 in the vacuum tube 30 of 20 pairs of cooling device insertion sections guarantee while cool down beam-shaping body 10 obtain compared with
Good neutron beam quality.
As shown in fig. 7, target 31 includes lithium target layer 311 and is used to prevent lithium target layer 311 from aoxidizing positioned at 311 side of lithium target layer
Anti oxidation layer 312.The anti oxidation layer 312 of target 31 is made of Al or stainless steel.
As shown in figure 4, cooling device 20 includes being arranged in a vertical direction and being located in front of target 31 for cooling down target 31
The first cooling end 21, extend along neutron beam axis X direction and be located at and 30 two sides of vacuum tube and be parallel to neutron beam axis X
The second cooling end 22 and third cooling end 23, the first cooling end 21 is connected between second, third cooling end 22,23.First
Cooling end 21 is accommodated in be accommodated in pipeline 131 along first perpendicular to neutron beam axis X direction arrangement, second, third is cold
But portion 22,23 is respectively received within along second, third receiving pipeline 132,133 of the direction of neutron beam axis X arrangement.The
Two cooling ends 22 input cooling medium to the first cooling end 21, and third cooling end 23 is defeated by the cooling medium in the first cooling end 21
Out.First cooling end 21 is located between target 31 and slow body 14, and the side of the first cooling end 21 is directly contacted with target 31, separately
Side is contacted with slow body 14.Second cooling end 22 and third cooling end 23 respectively include being located at 121 outside of reflector accommodating chamber
The first, second cooling section 221,231 and from the first, second cooling section 221,231 extend and be located at slow body accommodating chamber 122 outside
The third of side, the 4th cooling section 222,232.Third, the 4th cooling section 222,232 are connected to the first cooling end 21 respectively.Also
It is to say, the first cooling end 21 is located at the end of the insertion section 121 of vacuum tube 30 and is located at 31 side of target and direct with target 31
Contact, the second cooling end 22 and third cooling end 23 be located at the two sides up and down for the vacuum tube 30 being contained in accommodating chamber 12 and
It is connected to respectively with the first cooling end 21, so that entire cooling device 20 is in " Contraband " type structure setting.In present embodiment, the
One cooling end 21 and 31 plane contact of target, the second cooling end 22 and third cooling end 23 are all the tubular structures being made of copper,
And second cooling end 22 and third cooling end 23 extend along the direction of neutron beam axis X and be parallel to neutron beam axis X, i.e.,
Angle between second cooling end 22 and third cooling end 23 and neutron beam axis X is 0 °.
First cooling end 21 is including the first contact portion 211, the second contact portion 212 and is located at the first contact portion 211 and second
The cooling bath 213 passed through for cooling medium between contact portion 212.First contact portion 211 is directly contacted with target 31, and second connects
Contact portion 212 can be that directly contact can also be by air mediate contact with slow body 14.Cooling bath 213 has and the second cooling
The input slot 214 that portion 22 is connected to and the output magazine 215 being connected to third cooling end 23.First contact portion 211 is by Heat Conduction Material system
At.The upper edge of input slot 214 is located at the top of the upper edge of the second cooling end 22, and the lower edge of output magazine 215 is located at third
The lower section of the lower edge of cooling end 23.The benefit being arranged in this way is that cooling device 20 can more swimmingly input cooling water
It is cooled down in cooling bath 213 and more in time to target 31, and the cooling water after being heated also can be more smoothly from cold
But it is exported in slot 213, simultaneously, additionally it is possible to reduce the hydraulic pressure of cooling water in cooling bath 213 to a certain extent.
First contact portion 211 by Heat Conduction Material (such as material of Cu, Fe, Al good heat conductivity) or can it is thermally conductive but also suppression
System foaming material be made, the second contact portion 212 by inhibit foaming material be made, inhibit foaming material or can it is thermally conductive again
The material of foaming can be inhibited to be made of any of Fe, Ta or V.Target 31 is increased by the acceleration irradiation temperature of same high-energy level
Fever, the first contact portion 211 take heat out of by heat derives, and by the cooling medium in cooling bath 213 that circulates, thus
Target 31 is cooled down.In the present embodiment, cooling medium is water.
In the present embodiment, second, third accommodates pipeline 132,133 and second, third cooling end 22,23 and neutron beam
Angle between axis X is 0 °.In other embodiments, second, third accommodates pipeline 132,133 and second, third cooling
Angle between portion 22,23 and neutron beam axis X can also be that other are greater than 0 ° of any angle for being less than or equal to 180 °, such as
Shown in Fig. 6, second, third accommodates pipeline 132 ', 133 ' and second, third cooling end 22 ', 23 ' and neutron beam axis X ' it
Between angle be 90 °, for example shown in Fig. 7, second, third accommodates pipeline 132 ' ', 133 ' ' and second, third cooling end 22 ' ',
23 ' ' and neutron beam axis X ' ' between angle be 135 °.
As shown in figure 5, its schematic diagram for disclosing the neutron capture treatment system 1 ' in the embodiment of the present application two, wherein cold
But the second cooling end 22 ' of device 20 ' and third cooling end 23 ' and neutron beam axis X ' it is vertical, i.e., cooling device 20 ' is arranged
The target 31 ' in Embedded vacuum tube 30 ' is cooled down at " I " type structure.First in " I " type cooling device 20 ' is cold
But the first cooling end 21 of portion 21 ' and Contraband type cooling device 20 is arranged identical, the difference is that, " I " type cooling device 20 '
The second cooling end 22 ' and third cooling end 23 ' and the first cooling end 21 ' are located at and neutron beam axis X ' vertical same put down
In face, and the second cooling end 22 ' and third cooling end 23 wear out slow body along the direction vertical with neutron beam axis X respectively
14 ', i.e. the second cooling end 22 ' and third cooling end 23 ' and neutron beam axis X ' between angle be 90 ° so that entire cold
But device is arranged in rectangle, that is, above-mentioned " I " type structure.
With continued reference to Fig. 5, correspondingly, accommodating pipeline 30 ' is also set as " I " type structure, " I " type accommodates the in pipeline 30 '
One receiving pipeline 131 ' and Contraband type cooling pipe 30 first receiving pipeline 131 be arranged it is identical, the difference is that, " I " type appearance
It receives the second receiving pipeline 132 ' of pipeline 30 ' and third accommodates pipeline 133 ' and first and accommodates pipeline 131 ' and be located at and neutron beam
In axis X ' vertical same plane, and second accommodates pipeline 132 ' and third accommodates pipeline 133 ' edge and neutron beam axis respectively
Line X ' vertical direction wears out slow body 14 ', i.e., second, third accommodates pipeline 132 ', 133 ' and neutron beam axis X ' it
Between angle be 90 ° so that entirely accommodating pipeline in rectangle setting, that is, above-mentioned " I " type structure.
As shown in fig. 6, its schematic diagram for disclosing the neutron capture treatment system 1 " in the embodiment of the present application three, wherein cold
But the angle of the second cooling end 22 " of device 20 " and third cooling end 23 " and neutron beam axis X " is greater than 90 °, cooling device
First cooling end 21 of the first cooling end 21 " and Contraband type cooling device 20 in 20 ' ' be arranged it is identical, the difference is that, it is cold
But device 20 ' ' the second cooling end 22 ' ' and third cooling end 23 ' ' and neutron beam axis X ' ' between angle be 135 °.
Accommodate pipeline 30 ' ' the first receiving pipeline 131 ' the and Contraband type accommodate the first of pipeline 30 accommodate pipeline 131 be arranged it is identical, no
It is with place, accommodates pipeline 30 ' ' second accommodate pipeline 132 ' ' and third accommodates pipeline 133 ' ' and neutron beam axis X '
Between angle be 135 °.
Referring to Fig.1, shown in Fig. 3, Fig. 5 and Fig. 6, second, third cooling end 22,23；22',23'；22 ' ', 23 ' ' respectively with
Second, third accommodates pipeline 132,133；132',133'；132 ' ', between 133 ' ' inner wall there are gap, have in the gap
Filler 40；40'；40 ' ', filler 40；40'；40 ' ' it can absorb for metal or aluminium alloy etc. or the object of reflected neutron
Matter.Filler 40；40'；Reflection or scattering can 40 ' ' be entered to the neutron reflection in the gap to slow body 14 or reflector
In 15, the illuminated time is needed to increase the yield of epithermal neutron and then reduce irradiated body.On the other hand, neutron is avoided
It leaks into outside beam-shaping body 10 and adverse effect is caused to the instrument of neutron capture treatment system, improve radiogical safety.This
Apply in embodiment, the content of lead is more than or equal to 85% in metal, and the content of aluminium is more than or equal to 85% in aluminium alloy.
It is dirty to the yield of epithermal neutron, fast neutron when filler 40 is respectively air or metal or aluminium alloy in order to compare
The influence that dye amount and irradiation time generate, lists table one to table three and does detailed comparison.
Wherein, table one is shown under the aperture of different accommodating chambers, when filler is respectively air, aluminium alloy, metal
Yield (the n/cm of epithermal neutron2MA):
Table one: the yield (n/cm of epithermal neutron2mA)
Table two is shown under the aperture of different accommodating chambers, fast neutron when filler is respectively air, aluminium alloy, metal
Contaminant capacity (Gy-cm2/n):
Table two: fast neutron contaminant capacity (Gy-cm2/n)
Table three is shown under the aperture of different accommodating chambers, and filler is illuminated when being respectively air, aluminium alloy, metal
Irradiation time required for body (minute):
Table three: irradiation time required for irradiated body (Min)
From table one to table three as can be seen that when accommodating chamber aperture is identical, compared to filling air, metal or aluminium are filled
When alloy, the yield of epithermal neutron is higher, and fast neutron contaminant capacity and required irradiation time are less.
The neutron capture treatment system that the application discloses is not limited to content described in above embodiments and attached drawing institute
The structure of expression.For example, slow, body can be set to cylindrical body, cooling device can be set to several, and accommodate pipeline accordingly
With several etc..Apparently change that material and shape and position on the basis of the application to wherein component are made,
Substitution or modification, all this application claims within the scope of.
Claims (10)
1. a kind of neutron capture treatment system, it is characterised in that: the neutron capture treatment system includes beam-shaping body, setting
In the intracorporal vacuum tube of beam-shaping and at least one cooling device, the beam-shaping body includes beam entrance, described in receiving
The accommodating chamber of vacuum tube, the slow body for being adjacent to the accommodating chamber end, be enclosed in the slow external reflector, setting exists
The intracorporal radiation shield of the beam-shaping and beam outlet, the vacuum tube end are equipped with target, and the cooling device is used for
Target is cooled down, the target with from the generation nuclear reaction of the charged particle beam of beam entrance incidence to generate neutron,
The neutron forms neutron beam, and the neutron beam is exported from beam projects and limit a neutron beam axis, described slow
Fast body is by from the neutron degradation that the target generates to epithermal neutron energy area, and the neutron that the reflector will deviate from is back to described
Slow body is to improve epithermal neutron intensity of beam, and the neutron and photon that the radiation shield is used to shield leakage are to reduce non-irradiated
The normal tissue dose in area is additionally provided at least one receiving pipeline for accommodating the cooling device, institute in the beam-shaping body
It states between cooling device and the inner wall for accommodating pipeline filled with filler.
2. neutron capture treatment system according to claim 1, it is characterised in that: the filler is that metal or aluminium close
Gold.
3. neutron capture treatment system according to claim 1, it is characterised in that: the receiving pipeline is located at the receiving
Except the inner wall of chamber.
4. neutron capture treatment system according to claim 1, it is characterised in that: the cooling device includes for cooling down
First cooling end of target, the second cooling end and third that are connected to positioned at the first cooling end two sides and respectively with the first cooling end are cold
But portion；The pipeline that accommodates includes that first between target and slow body accommodates pipeline and be located at the first receiving pipeline two sides
And second, third receiving pipeline be connected to respectively with the first receiving pipeline, the first, second, third cooling end are respectively received in the
One, second, third is accommodated in pipeline, and it is cold that the filler is filled in inner wall and third that the second cooling end accommodates pipeline with second
But portion and third accommodate between the inner wall of pipeline.
5. neutron capture treatment system according to claim 4, it is characterised in that: second, third described cooling end is pipe
Shape structure, described second, third accommodate pipeline and are arranged to along the cross section for being parallel to the extension of neutron beam axis direction be circle
Pipeline.
6. neutron capture treatment system according to claim 4, it is characterised in that: first cooling position is in vacuum tube
End and contacted with the target plane, second cooling end and third cooling end are along the side for being parallel to neutron beam axis
To extend and be located at vacuum tube two sides up and down and with the first cooling end formed Contraband type structure；Second, third accommodates pipeline
Extend along the direction for being parallel to neutron beam axis and is located at the two sides up and down of vacuum tube and accommodates pipeline with described first
Form Contraband type structure.
7. neutron capture treatment system according to claim 4, it is characterised in that: first cooling position is in vacuum tube
End and contacted with the target plane, the angle between second cooling end and third cooling end and neutron beam axis
It is less than or equal to 180 ° greater than 0 °；Second, third accommodates the angle between pipeline and neutron beam axis and is less than or equal to greater than 0 °
180°。
8. neutron capture treatment system according to claim 4, it is characterised in that: second cooling end is cooling to first
Portion inputs cooling medium, and the third cooling end exports the cooling medium in the first cooling end.
9. neutron capture treatment system according to claim 1, it is characterised in that: the reflector is in neutron beam axis
Two sides protrude slow body, the vacuum tube includes the extended segment surrounded by reflector and extends from extended segment and be embedded in slow body
Insertion section, the target be set to it is described insertion section end.
10. neutron capture treatment system according to claim 1, it is characterised in that: the slow body is arranged to comprising extremely
A few cone.
Priority Applications (7)
| Application Number | Priority Date | Filing Date | Title |
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| CN201710760913.7A CN109420261B (en) | 2017-08-30 | 2017-08-30 | Neutron capture therapy system |
| TW107127844A TWI687249B (en) | 2017-08-30 | 2018-08-09 | Neutron Capture Therapy System |
| EP18851170.3A EP3643360B1 (en) | 2017-08-30 | 2018-08-16 | Neutron capture therapy system |
| JP2020509499A JP6956854B2 (en) | 2017-08-30 | 2018-08-16 | Neutron capture therapy system |
| RU2020108118A RU2745133C1 (en) | 2017-08-30 | 2018-08-16 | Neutron capture therapy system |
| PCT/CN2018/100765 WO2019042137A1 (en) | 2017-08-30 | 2018-08-16 | Neutron capture therapy system |
| US16/732,523 US11198023B2 (en) | 2017-08-30 | 2020-01-02 | Neutron capture therapy system |
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| CN201710760913.7A CN109420261B (en) | 2017-08-30 | 2017-08-30 | Neutron capture therapy system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111836448A (en) * | 2019-04-15 | 2020-10-27 | 禾荣科技股份有限公司 | Minimally invasive neutron beam generation device and minimally invasive neutron capture treatment system |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2005249638A (en) * | 2004-03-05 | 2005-09-15 | Kawasaki Heavy Ind Ltd | Passive reactor shutdown method and lead reflector used therefor |
| CN103617814A (en) * | 2013-11-08 | 2014-03-05 | 海龙核材科技（江苏）有限公司 | High-density neutron absorption plate |
| CN103946338A (en) * | 2011-11-22 | 2014-07-23 | 原子能和能源替代品委员会 | Device for neutron imagery in immersion and imaging method using said device |
| US20140264048A1 (en) * | 2013-03-15 | 2014-09-18 | Starfire Industries, Llc | Neutron radiation sensor |
| CN104511096A (en) * | 2014-12-08 | 2015-04-15 | 南京中硼联康医疗科技有限公司 | Beam shaper for neutron-capture therapy |
| US9081100B1 (en) * | 2011-10-27 | 2015-07-14 | The Curator Of The University Of Missouri | Apparatus and method for determination of one or more free neutron characteristics |
| CN106955427A (en) * | 2016-01-08 | 2017-07-18 | 南京中硼联康医疗科技有限公司 | The beam-shaping body treated for neutron capture |
| CN207856092U (en) * | 2017-08-30 | 2018-09-14 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
-
2017
- 2017-08-30 CN CN201710760913.7A patent/CN109420261B/en active Active
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2005249638A (en) * | 2004-03-05 | 2005-09-15 | Kawasaki Heavy Ind Ltd | Passive reactor shutdown method and lead reflector used therefor |
| US9081100B1 (en) * | 2011-10-27 | 2015-07-14 | The Curator Of The University Of Missouri | Apparatus and method for determination of one or more free neutron characteristics |
| CN103946338A (en) * | 2011-11-22 | 2014-07-23 | 原子能和能源替代品委员会 | Device for neutron imagery in immersion and imaging method using said device |
| US20140361179A1 (en) * | 2011-11-22 | 2014-12-11 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Device for neutron imagery in immersion and imaging method using said device |
| US20140264048A1 (en) * | 2013-03-15 | 2014-09-18 | Starfire Industries, Llc | Neutron radiation sensor |
| CN103617814A (en) * | 2013-11-08 | 2014-03-05 | 海龙核材科技（江苏）有限公司 | High-density neutron absorption plate |
| CN104511096A (en) * | 2014-12-08 | 2015-04-15 | 南京中硼联康医疗科技有限公司 | Beam shaper for neutron-capture therapy |
| CN106955427A (en) * | 2016-01-08 | 2017-07-18 | 南京中硼联康医疗科技有限公司 | The beam-shaping body treated for neutron capture |
| CN207856092U (en) * | 2017-08-30 | 2018-09-14 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
Non-Patent Citations (1)
| Title |
|---|
| 袁楠;牟浩瀚;倪狄;马帅;仲洪海;蒋阳;: "快速热压法制备B_4C/Al中子吸收材料的力学性能", 粉末冶金材料科学与工程, no. 04 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111836448A (en) * | 2019-04-15 | 2020-10-27 | 禾荣科技股份有限公司 | Minimally invasive neutron beam generation device and minimally invasive neutron capture treatment system |
| US11752360B2 (en) | 2019-04-15 | 2023-09-12 | Heron Neutron Medical Corp. | Minimally invasive neutron beam generating device and minimally invasive neutron capture therapy system |
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Application publication date: 20190305 Assignee: China boron (Xiamen) medical equipment Co.,Ltd. Assignor: NEUBORON MEDTECH LTD. Contract record no.: X2019320000054 Denomination of invention: Radiant ray detection system and radiant ray detection method for neutron capture treatment system License type: Common License Record date: 20190910 |
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