CN208355947U - Neutron capture treatment system - Google Patents
Neutron capture treatment system Download PDFInfo
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- CN208355947U CN208355947U CN201721755713.4U CN201721755713U CN208355947U CN 208355947 U CN208355947 U CN 208355947U CN 201721755713 U CN201721755713 U CN 201721755713U CN 208355947 U CN208355947 U CN 208355947U
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- Radiation-Therapy Devices (AREA)
- Particle Accelerators (AREA)
Abstract
Neutron capture treatment system provided by the present application includes the accelerator for generating charged particle beam, it reacts with charged particle beam and generates the neutron generating unit and beam-shaping body of neutron beam, beam-shaping body includes receiving portion, slow body, reflector, screening arrangement and beam outlet, receiving portion is equipped with the vacuum tube of connection accelerator, neutron generating unit is set to the end of vacuum tube, charged particle after vacuum tube accelerates accelerated device is transmitted to neutron generating unit so that nuclear reaction occurs for neutron generating unit and charged particle beam to form neutron beam, neutron generating unit moves between the first position and the second position, in first position, neutron generating unit and charged particle beam react to generate neutron, in the second position, the neutron generating unit falls off from beam-shaping body, beam-shaping body and screening arrangement make neutron generating unit from first The radiation that position moves to during the second position always in shielding to prevent revealing from neutron generating unit is irradiated to staff.
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 neutron generating unit atomic nucleus coulomb repulsion of beam-shaping is accelerated to, is sent out with the neutron generating unit
Raw nuclear reaction is to generate neutron, therefore neutron generating unit will receive high-power acceleration charged particle during generating neutron
The temperature of the irradiation of beam, neutron generating unit can be substantially increased, to influence the service life of neutron generating unit, therefore for centering
The replacement of sub- generating unit is necessary, and is bound to by the neutron generating unit of the acceleration charged particle beam irradiation of same high-energy level
There will certainly be radiation safety hidden danger when can have a large amount of radiation, therefore replace neutron generating unit.
Summary of the invention
In order to provide a kind of neutron capture treatment system for reducing radiation safety hidden danger, one embodiment of the application is provided
A kind of neutron capture treatment system includes for generating the accelerator of charged particle beam, in the generation that reacts with charged particle beam
The neutron generating unit and beam-shaping body of sub-beam, the beam-shaping body include receiving portion, are adjacent to the neutron generation
The slow body in portion is enclosed in the slow external reflector, the thermal neutron absorber adjacent with the slow body, is arranged in institute
The intracorporal radiation shield of beam-shaping, the screening arrangement adjacent to beam-shaping body and beam outlet are stated, the receiving portion is equipped with
It is connected to the vacuum tube of accelerator, the neutron generating unit is set to the end of the vacuum tube, and the vacuum tube is by accelerated device
Charged particle after acceleration is transmitted to the neutron generating unit so that nuclear reaction occurs for neutron generating unit to produce with charged particle beam
Raw neutron, the neutron form neutron beam, and the neutron beam limits a main shaft, and the slow body will be produced from the neutron
The neutron degradation that life portion generates is to epithermal neutron energy area, and the neutron that the reflector will deviate from is back to the slow body to improve
Epithermal neutron intensity of beam, the radiation shield are used to shield neutron and the photon of leakage to reduce the normal tissue in non-irradiated area
Dosage, the neutron generating unit move between the first position and the second position, in first position, the neutron generating unit and band
Electrochondria beamlet reacts to generate neutron, and in the second position, the neutron generating unit falls off from beam-shaping body, the beam
Shaping body and the screening arrangement make the neutron generating unit move to the second position from first position during always from
To prevent the radiation revealed from the neutron generating unit to be irradiated to staff in shielding.
When neutron generating unit is when in beam-shaping body, the intracorporal radiation shield of beam-shaping can be shielded to be produced from neutron
The radiation of life portion leakage is to avoid to staff's irradiation with radiation；After neutron generating unit is detached from beam-shaping body, nothing
Method shields neutron generating unit by radiation shield, is shielded at this time by screening arrangement to neutron generating unit, thus
It realizes during neutron generating unit moves to the second position from first position always in masked state, avoids neutron production
The radiation of life portion leakage is irradiated to staff.
Preferably as one kind, the vacuum tube, which includes at least, is connected to the first vacuum pipe portion of accelerator, is contained in and penetrates
Beam shaping body receiving portion simultaneously accommodates the second vacuum pipe portion of neutron generating unit and connects the first vacuum pipe portion and the second vacuum
The third vacuum pipe portion of pipe portion, the third vacuum pipe portion can be dismantled to provide the sky that neutron generating unit is moved out from receiving portion
Between, in the second position, the neutron generating unit can move out from receiving portion together with the second vacuum pipe portion and from beam-shaping
Body falls off.
Further, the screening arrangement includes bottom wall and is connected to bottom wall and the first side wall being oppositely arranged and second
Side wall, the bottom wall and two side walls form the U-shaped structure with the first opening, the second opening and third opening, and described the
One opening is open adjacent to the second vacuum pipe portion, third vacuum pipe portion across third adjacent to the first vacuum pipe portion, the second opening.
In the application, preferably it is arranged after screening arrangement outside vacuum tube as a kind of and dismantles third vacuum pipe portion again, and practical operation
In, first screening arrangement will can also be installed again after the disassembly of third vacuum pipe portion.
Further, the screening arrangement further includes the roof being oppositely arranged with bottom wall, the third side for connecting bottom wall, roof
Wall and the 4th side wall, the third side wall and the 4th side wall are oppositely arranged, and the bottom wall, roof and four side walls form screen
Space is covered, the roof can be rotated around second sidewall or the 4th side wall to the direction far from shielding space, first side
Wall and third side wall are able to rotate around bottom wall to the direction far from shielding space, so that the U-shaped structure of the screening arrangement.
When screening arrangement is between the first vacuum pipe portion and the second vacuum pipe portion, the U-shaped structure of screening arrangement；When neutron produces
When life portion is located at screening arrangement together with the second vacuum pipe portion, the screening arrangement formed shielding space with to neutron generating unit into
Row shielding.
Further, receiving portion is moved out for the ease of the neutron generating unit, the vacuum tube periphery and receiving portion
Filler is filled between inner wall, the neutron capture treatment system further includes being located in receiving portion and carrying out to neutron generating unit
Cooling cooling device, the filler are filled in the inner wall of the vacuum tube periphery and receiving portion and wrap the cooling dress
It sets, when neutron generating unit moves in screening arrangement, the cooling device and filler move to together with neutron generating unit
In screening arrangement.
Further, the filler is the material that can absorb neutron or reflected neutron.
Further, the neutron capture treatment system further includes being located in receiving portion and cooling down to neutron generating unit
Cooling device, the filler is filled in the inner wall of the vacuum tube periphery and receiving portion and wraps the cooling device.
Preferably as one kind, the cooling device includes generating facial planes with the neutron positioned at the end of vacuum tube
First cooling end of contact, the second cooling end and third being connected to positioned at the first cooling end two sides and respectively with the first cooling end are cold
But portion, second cooling end and third cooling end extend along the direction for being parallel to neutron beam axis and are located at vacuum tube
Two sides up and down and with the first cooling end formed Contraband type structure.
Further, in order to be further reduced the contact of staff with neutron generating unit, improve radiation safety, it is described in
Son capture treatment system further includes the accommodating device below the vacuum tube, and the neutron generating unit is moved to from receiving portion
The accommodating device is fallen into after in screening arrangement, the accommodating device is made of shielding material.
Further, the accommodating device includes bottom and four sides for being connected to bottom, the bottom and four
Side connects to form the accommodating space with opening, and the accommodating device is also additionally provided with two rotations for being shielded in the opening
Portion, one end connect the side of the rotation section, the other end can be rotated relative to the side connected into accommodating space, certainly
Under right state, described two rotation sections are shielded in the top for above the accommodating space and forming accommodating device；In external force
Under, the rotation section rotates to accommodating space and is contained in accommodating space；When external force is eliminated, the rotation section is restored to nature
State.
Detailed description of the invention
Fig. 1 is the schematic diagram of the first embodiment of the application neutron capture treatment system, wherein neutron generating unit
In first position；
Fig. 2 be in Fig. 1 cooling device along perpendicular to neutron beam direction of illumination cross-sectional view；
Fig. 3 is in Fig. 1 along the partial sectional view perpendicular to neutron beam direction of illumination neutron capture treatment system；
Fig. 4 is the schematic diagram that the third vacuum pipe portion of the vacuum tube in Fig. 1 is disassembled；
Fig. 5 is after the third vacuum pipe portion in Fig. 4 is disassembled, and the second vacuum pipe portion and neutron generating unit move out receiving portion
Schematic diagram, i.e. neutron generating unit is in the second position；
Fig. 6 is the schematic diagram of second of embodiment of the application neutron capture treatment system, wherein in the first vacuum tube
Screening arrangement is installed between portion and the second vacuum pipe portion；
Fig. 7 be by Fig. 6 the second vacuum pipe portion and neutron generating unit be moved to schematic diagram in screening arrangement；
Fig. 8 is by the schematic diagram under the screening arrangement disassembly for containing the second vacuum pipe portion and neutron generating unit in Fig. 6；
Fig. 9 is the stereoscopic schematic diagram of screening arrangement in Fig. 6；
Figure 10 is the schematic diagram of screening arrangement another embodiment shown in Fig. 9；
Figure 11 is the stereoscopic schematic diagram of screening arrangement shown in Figure 10；
Figure 12 is the schematic diagram of the third embodiment of the application neutron capture treatment system；
Figure 13 is that the secondary shielding portion in Figure 12 showing relative to the first shielding part to separate neutron generating unit direction is mobile
It is intended to；
Figure 14 is in Figure 12 along the partial sectional view perpendicular to neutron beam direction of illumination neutron capture treatment system；
Figure 15 is in Figure 13 along the partial sectional view perpendicular to neutron beam direction of illumination neutron capture treatment system；
Figure 16 is after secondary shielding portion shown in Figure 14 is mobile, and the first vacuum pipe portion and neutron generating unit move out accommodating space
Schematic diagram；
Figure 17 is in Figure 16 along the partial sectional view perpendicular to neutron beam direction of illumination neutron capture treatment system；
Figure 18 is the schematic diagram of accommodating device in its natural state in Figure 15；
Figure 19 be in Figure 18 accommodating device by the schematic diagram after external force.
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 value 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)
The proton-effect section of sub- generating unit and threshold energy is not high, to generate sufficiently large neutron flux, usually selects higher-energy
Proton cause nuclear reaction.
Ideal neutron generating unit should have high neutron yield rate, the neutron energy of generation is distributed close to epithermal neutron energy area
(will be described in more detail below) wears by force the characteristics such as radiation generation, the cheap easily operated and high temperature resistant of safety without too many, but actually
And it can not find and meet required nuclear reaction.Using neutron generating unit made of lithium metal in embodiments herein.But
Be it is well known to those skilled in the art, the material of neutron generating unit can also by other in addition to the above-mentioned metal material talked about it
Outer metal material is made.
Requirement for hot removal system is then different according to the nuclear reaction of selection, such as7Li(p,n)7Be is generated because of metal neutron
The fusing point and thermal conductivity coefficient in portion's (lithium metal) are poor, the requirement to hot removal system just compared with9Be(p,n)9B high.Embodiments herein
Middle use7Li(p,n)7The nuclear reaction of Be.It follows that being accelerated the neutron of charged particle beam irradiation to produce by same high-energy level
The temperature in life portion will necessarily be substantially increased, to influence the service life of neutron generating unit.
No matter the neutron source of boron neutron capture treatment is from nuclear reactor or accelerator charged particle and neutron generating unit
Nuclear reaction, generation is all mixed radiation field, i.e., beam contains neutron, photon of the low energy to high energy.For deep tumor
The treatment of boron neutron capture, other than epithermal neutron, remaining radiation content is more, causes the non-selective dosage of normal tissue heavy
Long-pending ratio is bigger, therefore these radiation that will cause unnecessary dosage should reduce as far as possible.In addition to air beam quality factor, it is
Dosage caused by knowing more about neutron in human body is distributed, and carries out dosage using human body head tissue prosthese in embodiments herein
It calculates, and will be described in more detail below with prosthese beam quality factor as the design reference of neutron beam.
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 solve the replacement problem of neutron generating unit, meanwhile, contact of the reduction staff with radiation as far as possible, this
Application provides a kind of neutron capture treatment system.
Because generation core is anti-after the main radiation of exchange target personnel is derived from charged particle beam irradiation to neutron generating unit
The radiation that should be generated illustrates to install so the application is intended to illustrate that the neutron generating unit after nuclear reaction occurs for disassembly without going
New neutron generating unit.
As shown in Figure 1, neutron capture treatment system 100 includes for generating the accelerator 200 of charged particle beam and electrification
Particle beams P, which reacts, generates the neutron generating unit 10 and beam-shaping body 20 of neutron beam N, and beam-shaping body 20 includes receiving
What appearance portion 21, the slow body 22 for being adjacent to neutron generating unit, the reflector 23 being enclosed in outside slow body 22 and slow body 22 abutted
Thermal neutron absorber 24, the radiation shield 25 being arranged in beam-shaping body 20 and beam outlet 26,21 company of containing of receiving portion
It is connected to the vacuum tube 30 of accelerator 200, neutron generating unit 10 is set to the end of vacuum tube 30 and is adjacent to slow body 22.Vacuum
Charged particle P after pipe 30 accelerates accelerated device 200 is transmitted to neutron generating unit 10, and accelerator 200 accelerates charged particle P
To being enough to overcome the energy of target atom nuclear force, occur with neutron generating unit 127Li(p,n)7Be nuclear reaction to generate neutron, in
Son forms neutron beam N, and neutron beam N limits a main shaft I.Slow body 22 subtracts the neutron generated from neutron generating unit 10
Speed is to epithermal neutron energy area.The neutron that reflector 23 will deviate from is back to slow body 22 to improve epithermal neutron intensity of beam.Heat
Multi-dose was caused with shallow-layer normal tissue when neutron absorber 24 is for absorbing thermal neutron to avoid treatment.Radiation shield 25 is used
The normal tissue dose in non-irradiated area is reduced in the neutron and photon that shield leakage.
In conjunction with Fig. 2, neutron capture treatment system 100 further includes being cooled down to neutron generating unit 10 to improve neutron generation
The cooling device 40 of portion's service life.
Cooling device 40 includes the first cooling end positioned at the end of vacuum tube 30 and with 10 plane contact of neutron generating unit
41, the second cooling end 42 and third cooling end 43 being connected to positioned at 41 two sides of the first cooling end and respectively with the first cooling end 41.
There are gaps between the periphery of vacuum tube 30 and the inner wall of receiving portion 21, and the second cooling end 42 and third cooling end 43 are in gap
Along be parallel to neutron beam axis I direction extend and be located at vacuum tube 30 two sides up and down and with 41 shape of the first cooling end
At Contraband type structure.In order to make cooling device 40 guarantee beam while cooling to the neutron generating unit 10 of 30 end of vacuum tube
Shaping body 20 obtains preferable neutron beam quality, and partial vacuum pipe 30 is embedded in slow body 22 (not shown).Second is cold
But portion 242 inputs cooling medium to the first cooling end 41, and third cooling end 43 exports the cooling medium in the first cooling end 41.
First cooling end 41 is located between neutron generating unit 10 and slow body 22, and the side of the first cooling end 41 and neutron generating unit 31 are straight
Plane contact is connect, the other side is contacted with slow body 14.
First cooling end 41 is including the first contact portion 411, the second contact portion 412 and is located at the first contact portion 411 and second
The cooling bath 413 passed through for cooling medium between contact portion 412.First contact portion 411 is directly contacted with neutron generating unit 10,
Second contact portion 412 can be that directly contact can also be by air mediate contact with slow body 22.Cooling bath 413 has and the
The input slot 414 of two cooling ends 42 connection and the output magazine 415 being connected to third cooling end 43.First contact portion 411 is by thermally conductive
Material is made.First contact portion 411 by Heat Conduction Material (such as material of Cu, Fe, Al good heat conductivity) or can it is thermally conductive but also
Inhibit foaming material be made, the second contact portion 412 by inhibit foaming material be made, inhibit foaming material or can be thermally conductive
The material of foaming can be inhibited to be made of any of Fe, Ta or V again.Neutron generating unit 10 is irradiated by the acceleration of same high-energy level
Temperature increases fever, and heat derives are passed through cooling medium of the circulation in cooling bath 413 for heat by the first contact portion 411
It takes out of, to be cooled down to neutron generating unit 10.In the present embodiment, cooling medium is water.
Please join Fig. 1 and Fig. 5, Fig. 1 is neutron generating unit in the schematic diagram of first position, Fig. 5 be neutron generating unit in
The schematic diagram when second position.Neutron generating unit 10 moves between the first position and the second position, and in first position, neutron is produced
Life portion 10 can be reacted with charged particle beam to generate neutron, and in the second position, neutron generating unit 10 is from beam-shaping body
20 fall off.
In conjunction with Fig. 3, there is gap between 30 outer wall of receiving portion 21 and vacuum tube, be filled with filler 50 in gap.Filling
Object 50 is coated on the outer wall and cooling device 40 of vacuum tube 30.Filler 50 is that metal or aluminium alloy etc. can absorb or instead
Hit the substance of son.In the embodiment of the present application, the content of lead is more than or equal to 85% in metal, and the content of aluminium is greater than in aluminium alloy
Equal to 85%.Reflection or scattering can be entered neutron reflection in gap to slow body 22 or instead by 50 one side of filler
In beam 23, the illuminated time is needed to increase the yield of epithermal neutron and then reduce irradiated body；It on the other hand can also
It avoids neutron from leaking into outside beam-shaping body 20 cause adverse effect to the instrument of neutron capture treatment system, improve radiation peace
Quan Xing.Also, when neutron generating unit 10 moves to the outside of receiving portion 21, cooling device 40 and filler 50 can be with neutrons
Generating unit 10 moves out receiving portion 21 together, to fall off from beam-shaping body 20.
As the first embodiment, Fig. 1, Fig. 4 please be join to Fig. 5, vacuum tube 30 includes being connected to the first of accelerator 200
Vacuum pipe portion 31, the second vacuum pipe portion 32 for being contained in receiving portion 21 and the first vacuum pipe portion 31 of connection and the second vacuum pipe portion
32 third vacuum pipe portion 33.One end of second vacuum pipe portion 32 is adjacent to slow body 22, the other end extend receiving portion 21 and
It is connect with third vacuum pipe portion 33, neutron generating unit 10 is set to the end of the second vacuum pipe portion 32 and is adjacent to slow body 22.The
Three vacuum pipe portions 33 can be under the first vacuum pipe portion 31 and the disassembly of the second vacuum pipe portion 32 so that the overall length of vacuum tube 30
It shortens, to provide neutron generating unit 10 along the space that the opposite direction that neutron beam N irradiates is moved out from receiving portion 21.When
After three vacuum pipe portions 33 are dismantled between the first vacuum pipe portion 31 and the second vacuum pipe portion 32, the second vacuum pipe portion 32 can be in
The opposite direction of sub-beam N irradiation is moved out from receiving portion 21, to fall off from beam-shaping body 20.
In the embodiment, it is because of the second vacuum tube of disassembly why vacuum tube 30 can fall off from beam-shaping body 20
First vacuum pipe portion 31 has the opposite direction along neutron beam N irradiation to move out the space of receiving portion 21 behind portion 32, that is, passes through
The entire length for changing vacuum tube 30, which reserves neutron generating unit 10, allows bit space.As other for changing vacuum tube overall length
Embodiment (can also will such as be located at and penetrate by way of being arranged to vacuum tube to shrink along neutron beam direction of illumination
The external partial vacuum pipe of beam shaping is set as telescopic bellows, and when bellows compression, the overall length of vacuum tube becomes
Short, neutron generating unit moves out beam-shaping body along the opposite direction that neutron beam irradiates with vacuum tube), herein just no longer in detail
Explanation.
Fig. 6 to Fig. 8 is the schematic diagram of second of embodiment of the application neutron capture treatment system, in order to further
Radiation is reduced to the security risk of staff, neutron capture treatment system 100 further includes screening arrangement 60.
In conjunction with Fig. 9, screening arrangement 60 include bottom wall 61, the roof 62 being oppositely arranged with bottom wall 61 and connect bottom wall 61,
The first side wall 63, second sidewall 64, third side wall 65 and the 4th side wall 66 of roof 62.The first side wall 63 and third side wall 65
It is oppositely arranged, second sidewall 64 and the 4th side wall 66 are oppositely arranged, and bottom wall 61, roof 62 and four side walls connect to form shielding
Space 67.Roof 62 can be rotated around second sidewall 64 or the 4th side wall 66 to the direction far from or close to shielding space 67,
The first side wall 63 and third side wall 65 are able to rotate around bottom wall 61 to the direction far from or close to shielding space 67.Roof
62, the rotation of the first side wall 63 and third side wall 65 is by being mounted on bottom wall 61, the first side wall 63 and third side wall 65
Rotating member 68 realize.When roof 62, the first side wall 63 and third side wall 65 around rotating member 68 to far from shielding space 67
When direction rotates, the U-shaped structure of screening arrangement 60, for facilitating staff by the first vacuum pipe portion 31 to beam-shaping body 20
Outer movement and make neutron generating unit 10 movement in shielding space 67.
Certainly, as the another embodiment (in conjunction with Figure 10 and 11) of above-mentioned screening arrangement 60, shown screening arrangement 60
The two side walls (64,66) that can also only include bottom wall 61 and be connected to bottom wall 61 and be oppositely arranged.Bottom wall 61 and two side walls
The third opening 621 that there is be oppositely arranged first the 631, second opening 651 of opening and be oppositely arranged with bottom wall 61 is formed, i.e.,
Bottom wall 61 and two side walls form U-shaped structure, and U-shaped structure has shielding space 67.First opening 631 is adjacent to the first vacuum tube
Portion 31, the second opening 651 are adjacent to the second vacuum pipe portion 32, and third vacuum pipe portion is open across third, and third opening 621 is used
The second vacuum pipe portion 31 is moved to shielding space 67 in staff.In the application embodiment, the screening arrangement 60 is set
In the periphery of vacuum tube 30, when needing replacing neutron generating unit, third vacuum pipe portion, mobile second vacuum of staff are dismantled
Pipe portion 32 is up to neutron generating unit 10, filling part 50 and cooling device 40 are moved and received together with the second vacuum pipe portion 32
It is dissolved in the shielding space 67 of screening arrangement 60, then screening arrangement 60 is removed from the first vacuum pipe portion 31, then rotate respectively
Roof 60, the first side wall 63 and third side wall 65 are covered in roof 60, the first side wall 63 and third side wall 65 respectively
Shielding space 67 is to shield the radiation in shielding space 67 comprehensively.After 60 pairs of generation nuclear reactions of screening arrangement
The radiation that neutron generating unit 10 retains is blocked, to reduce radiation to the security risk of staff.Certainly, in reality
In the operating process of border, can also after third vacuum pipe portion 33 is dismantled, the first vacuum pipe portion 31 and the second vacuum pipe portion 32 it
Between be arranged screening arrangement 60.
Screening arrangement 60 setting can by first opening 631 and first vacuum pipe portion 31 connection (abutting), second
The connection (abutting) of opening 651 and the second vacuum pipe portion 32 (beam-shaping body 20) realizes, can also be additional by being arranged
Structure is supported in 30 periphery of vacuum tube to realize.
Because staff is to stand more to change jobs to neutron generating unit in the side of beam-shaping body, working
When personnel's the second vacuum pipe portion of movement, the bottom wall and side wall of shielding part can be carried out the radiation retained in neutron generating unit
Shielding, after neutron generating unit is displaced into shielding space jointly with the second vacuum pipe portion, rotation roof, the first side wall and third
Side wall surrounds shielding space all by shielding material, to further decrease the radiation safety hidden danger of staff.Certainly, U
The screening arrangement 60 of type structure also shields the radioactive ray for being possible to radiation worker enough, to reduce the radiation peace of staff
Full hidden danger.
Figure 12 to 17 show the schematic diagram of the third embodiment of the application neutron capture treatment system.Neutron capture
Treatment system 100 ' further includes the shielding part for being adjacent to slow body 22, and shielding part is coated on the periphery of receiving portion 21.Shielding part packet
Include the first shielding part 71 and secondary shielding portion 72, secondary shielding portion 72 can be with respect to the first shielding part 71 to far from vacuum tube 30
Direction moves and falls neutron generating unit 10 from receiving portion 2.Vacuum tube 30 includes at least and is connected to the first of accelerator 200
Vacuum pipe portion 31 ' and the second vacuum pipe portion 32 ' for being connected to the first vacuum pipe portion 31 ' and being contained in receiving portion 21.When
One vacuum pipe portion 31 ' is from after the disengaging of the second vacuum pipe portion 32 ', and secondary shielding portion 72 is moved to the direction far from neutron generating unit 10
It moves to the first vacuum pipe portion 31 ' when can fall from receiving portion 21, neutron generating unit 10 is common with the second vacuum pipe portion 32 '
Receiving portion 21 is moved out, and is fallen off from beam-shaping body 20.Filling part, cooling device also with neutron generating unit 10 together from
It falls off in beam-shaping body 20.
In order to reduce radiation to the security risk of staff, neutron capture treatment system can also include such as embodiment party
Screening arrangement 60 in formula two, also may include the accommodating device 80 positioned at the lower section of vacuum tube 30, and neutron generating unit 10 is from receiving
Accommodating device 80 is fallen into portion 21, accommodating device 80 is made of shielding material.
In conjunction with Figure 18 to Figure 19, accommodating device 80 includes bottom 81, the top 82 being oppositely arranged with bottom 81 and connect
In four sides 83 of bottom 81 and top 82, bottom 81, top 82 and four connections of side 83, which are formed, has accommodating space 84
Accommodating device 80.The top 82 of accommodating device 80 is additionally provided with an opening, and there are two the rotation sections being oppositely arranged for opening masking
85, one end of each rotation section 85 is connected to top 82, and the other end can be rotated relative to top into accommodating space 84.Certainly
Under right state, two rotation sections 85 are located at 84 top of accommodating space and are shielded in opening；Under external force, rotation section 85 to
It is rotated in accommodating space 84 and is contained in accommodating space 84；When external force is eliminated, rotation section 85 is restored to nature.Rotation section
85 movement can be such that rotating member 85 moves around shaft member (not shown) into accommodating space 84 by the way that shaft member is arranged at top 82
Or the opening of 84 top of accommodating space is covered in realize, it just no longer illustrates herein.
Certainly, the accommodating device in third embodiment can also be set in first embodiment and second embodiment,
To further avoid the probability that staff directly contacts with radiation.
The neutron capture treatment system accelerates charged particle beam P by accelerator, as a kind of preferred embodiment, in
Sub- generating unit 31 is made of lithium metal, and charged particle beam accelerates to the energy for being enough to overcome neutron generating unit atomic nucleus coulomb repulsion
Amount occurs with neutron generating unit 317Li(p,n)7To generate neutron, beam-shaping body 20 can be by neutron slowly to super for Be nuclear reaction
Hanker subzone, and reduces thermal neutron and fast neutron content.As shown in figure 3, neutron generating unit 10 includes lithium target layer 101 and is located at
The anti oxidation layer 102 that 10 side of lithium target layer is used to prevent lithium target layer 101 from aoxidizing.The anti oxidation layer 102 of neutron generating unit 10 is by Al
Or stainless steel is made.
Slow body 22 is made of the material big with fast neutron action section, epithermal neutron action section is small, reflector 23
By being made with the strong material of neutron reflection ability, thermal neutron absorber 24 is made of the material big with thermal neutron action section.
As a kind of preferred embodiment, slow body 22 is by D2O、AlF3、FluentalTM、CaF2、Li2CO3、MgF2And Al2O3In at least
One kind is made, and reflector 23 is made of at least one of Pb or Ni, thermal neutron absorber 24 by6Li is made.
Radiation shield 25 includes photon shielding 251 and neutron shield 252, as a kind of preferred embodiment, radiation shield 25
Including the shielding of the photon made of lead (Pb) 251 and the neutron shield 252 made of polyethylene (PE).
For the ease of being illustrated to the application, identical label indicates identical element in the application.
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 for generating band electrochondria
The accelerator of beamlet, reacting with charged particle beam generates the neutron generating unit and beam-shaping body of neutron beam, described
Beam-shaping body include receiving portion, the slow body for being adjacent to the neutron generating unit, be enclosed in the slow external reflector,
Adjacent thermal neutron absorber, setting are in the intracorporal radiation shield of the beam-shaping, whole adjacent to beam with the slow body
The screening arrangement and beam of body export, and the receiving portion is equipped with the vacuum tube for being connected to accelerator, and the neutron generating unit is set
In the end of the vacuum tube, the vacuum tube by accelerated device accelerate after charged particle be transmitted to the neutron generating unit with
Make neutron generating unit and charged particle beam that nuclear reaction occur to generate neutron, the neutron forms neutron beam, and the neutron is penetrated
Beam limit a main shaft, the slow body by the neutron degradation generated from the neutron generating unit to epithermal neutron energy area, it is described
The neutron that reflector will deviate from improves epithermal neutron intensity of beam back to the slow body, and the radiation shield is for shielding
The neutron and photon of leakage are to reduce the normal tissue dose in non-irradiated area, and the neutron generating unit is in first position and second
It is moved between setting, in first position, the neutron generating unit and charged particle beam react to generate neutron, in second
It sets, the neutron generating unit falls off from beam-shaping body, and the beam-shaping body and the screening arrangement produce the neutron
Life portion is in shielding always to prevent from revealing from the neutron generating unit during moving to the second position from first position
Radiation be irradiated to staff.
2. neutron capture treatment system according to claim 1, it is characterised in that: the vacuum tube is included at least and is connected to
First vacuum pipe portion of accelerator, the second vacuum pipe portion for being contained in beam-shaping body receiving portion and accommodating neutron generating unit with
And the third vacuum pipe portion of connection the first vacuum pipe portion and the second vacuum pipe portion, the third vacuum pipe portion can be dismantled to provide
The space that neutron generating unit is moved out from receiving portion, in the second position, the neutron generating unit can be with the second vacuum pipe portion one
It falls off with being moved out from receiving portion from beam-shaping body.
3. neutron capture treatment system according to claim 2, it is characterised in that: the screening arrangement include bottom wall and
The first side wall and second sidewall for being connected to bottom wall and being oppositely arranged, the bottom wall and two side walls, which are formed, has first to be open,
The U-shaped structure of second opening and third opening, first opening is adjacent to the first vacuum pipe portion, and the second opening is adjacent to the
Two vacuum pipe portions, third vacuum pipe portion are open across third.
4. neutron capture treatment system according to claim 3, it is characterised in that: the screening arrangement further includes and bottom wall
The roof that is oppositely arranged, connection bottom wall, roof third side wall and the 4th side wall, the third side wall and the 4th side wall are opposite
Setting, the bottom wall, roof and four side walls form shielding space, and the roof can be around second sidewall or the 4th side wall
It is rotated to the direction far from shielding space, the first side wall and third side wall are able to around bottom wall to far from shielding space
Direction rotation, so that the U-shaped structure of the screening arrangement.
5. neutron capture treatment system according to claim 4, it is characterised in that: when screening arrangement is located at the first vacuum tube
When between portion and the second vacuum pipe portion, the U-shaped structure of screening arrangement；When neutron generating unit together with the second vacuum pipe portion position
When screening arrangement, the screening arrangement forms shielding space to shield to neutron generating unit.
6. neutron capture treatment system according to claim 1, it is characterised in that: the vacuum tube periphery and receiving portion
Filler is filled between inner wall, the neutron capture treatment system further includes being located in receiving portion and carrying out to neutron generating unit
Cooling cooling device, the filler are filled in the inner wall of the vacuum tube periphery and receiving portion and wrap the cooling dress
It sets, when neutron generating unit moves in screening arrangement, the cooling device and filler move to together with neutron generating unit
In screening arrangement.
7. neutron capture treatment system according to claim 6, it is characterised in that: the filler is that can absorb neutron
Or the material of reflected neutron.
8. neutron capture treatment system according to claim 6, it is characterised in that: the cooling device includes being located at vacuum
The end of pipe and with the first cooling end of the neutron generating unit plane contact, be located at the first cooling end two sides and respectively with first
The second cooling end and third cooling end of cooling end connection, second cooling end and third cooling end edge are parallel to neutron beam
The direction of axis extends and is located at the two sides up and down of vacuum tube and forms Contraband type structure with the first cooling end.
9. neutron capture treatment system according to claim 1, it is characterised in that: the neutron capture treatment system is also wrapped
The accommodating device being located at below the vacuum tube is included, the neutron generating unit falls into institute after moving in screening arrangement from receiving portion
Accommodating device is stated, the accommodating device is made of shielding material.
10. neutron capture treatment system according to claim 9, it is characterised in that: the accommodating device include bottom with
And four sides of bottom are connected to, the bottom and four sides connect to form the accommodating space with opening, the accommodating
Device is also additionally provided with two rotation sections for being shielded in the opening, and one end connect the side of the rotation section, the other end being capable of phase
The side connected is rotated into accommodating space, in its natural state, it is empty that described two rotation sections are shielded in the accommodating
Between top and form the top of accommodating device；Under external force, the rotation section rotates to accommodating space and is contained in accommodating
Space；When external force is eliminated, the rotation section is restored to nature.
Priority Applications (7)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201721755713.4U CN208355947U (en) | 2017-12-15 | 2017-12-15 | Neutron capture treatment system |
| PCT/CN2018/100963 WO2019114308A1 (en) | 2017-12-15 | 2018-08-17 | Neutron capture therapy system |
| RU2020114997A RU2739171C1 (en) | 2017-12-15 | 2018-08-17 | Neutron capture therapy system |
| EP18887579.3A EP3685883B1 (en) | 2017-12-15 | 2018-08-17 | Neutron capture therapy system |
| JP2019559284A JP7357545B2 (en) | 2017-12-15 | 2018-08-17 | Neutron capture therapy system |
| US16/839,188 US11813483B2 (en) | 2017-12-15 | 2020-04-03 | Neutron capture therapy system |
| JP2023007754A JP2023041757A (en) | 2017-12-15 | 2023-01-23 | Neutron capture therapy system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201721755713.4U CN208355947U (en) | 2017-12-15 | 2017-12-15 | Neutron capture treatment system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN208355947U true CN208355947U (en) | 2019-01-11 |
Family
ID=64913818
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201721755713.4U Withdrawn - After Issue CN208355947U (en) | 2017-12-15 | 2017-12-15 | Neutron capture treatment system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN208355947U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109925610A (en) * | 2017-12-15 | 2019-06-25 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
| TWI759146B (en) * | 2020-03-18 | 2022-03-21 | 中國商中硼（廈門）醫療器械有限公司 | Neutron Capture Therapy System |
| WO2024067111A1 (en) * | 2022-09-30 | 2024-04-04 | 中硼(厦门)医疗器械有限公司 | Neutron capture therapy system |
-
2017
- 2017-12-15 CN CN201721755713.4U patent/CN208355947U/en not_active Withdrawn - After Issue
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109925610A (en) * | 2017-12-15 | 2019-06-25 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
| CN109925610B (en) * | 2017-12-15 | 2024-03-22 | 南京中硼联康医疗科技有限公司 | Neutron capture therapy system |
| TWI759146B (en) * | 2020-03-18 | 2022-03-21 | 中國商中硼（廈門）醫療器械有限公司 | Neutron Capture Therapy System |
| WO2024067111A1 (en) * | 2022-09-30 | 2024-04-04 | 中硼(厦门)医疗器械有限公司 | Neutron capture therapy system |
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