CN106552321A - Radiation detecting system and radiation line detecting method for neutron capture treatment system - Google Patents
Radiation detecting system and radiation line detecting method for neutron capture treatment system Download PDFInfo
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Abstract
It is an aspect of the invention to provide a kind of radiation detecting system of the degree of accuracy of the neutron beam exposure dose for improving neutron capture treatment system, neutron capture treatment system includes charged particle beam, for by the charged particle beam entrance of charged particle beam, there is nuclear reaction so as to produce the neutron generating unit of neutron beam with charged particle beam in Jing, for adjusting the neutron beam flux of Jing neutrons generating unit generation with the beam-shaping body of quality and being adjacent to the beam outlet of beam-shaping body, wherein, neutron generating unit is contained in beam-shaping body, radiation detecting system includes the radiation line detector being arranged in beam-shaping body or beam-shaping is external, neutron beam or the gamma-rays of generation that radiation line detector is overflowed by neutron generating unit Jing after there is nuclear reaction with neutron generating unit for real-time detection charged particle beam.It is another aspect of the invention to provide a kind of radiation line detecting method of the degree of accuracy of the neutron beam exposure dose for improving neutron capture treatment system.
Description
Technical field
The present invention relates to a kind of radiation detecting system, more particularly to a kind of radiation detection system for neutron capture treatment system
System；The invention further relates to a kind of radiation line detecting method, more particularly to a kind of radiation detection for neutron capture treatment system
Method.
Background technology
With the development of atomics, such as radiation cure such as cobalt 60, linear accelerator, electron beam has become cancer and has controlled
One of Main Means for the treatment of.But conventional photonic or electronic therapy are limited by lonizing radiation physical condition itself, tumor is being killed
While cell, also substantial amounts of normal structure in beam approach can be damaged；It is sensitive to lonizing radiation additionally, due to tumor cell
The difference of degree, traditional radiation therapy is for the malignant tumor for relatively having radiation resistance (such as：Multirow glioblastoma multiforme
(glioblastoma multiforme), melanocytoma (melanoma)) treatment effect it is often not good.
In order to reduce the radiation injury of tumor surrounding normal tissue, the target therapy concept in chemotherapy (chemotherapy)
Just it is applied in radiation cure；And be directed to the tumor cell of radiation resistance, at present also actively development with high Relative biological
The radiation source of effect (relative biological effectiveness, RBE), such as proton therapeutic, heavy particle therapy,
Neutron capture treatment etc..Wherein, neutron capture treatment is the such as boron neutron capture treatment with reference to above two concept, by containing
Boron medicine gathers in the specificity of tumor cell, coordinates accurately neutron beam regulation and control, there is provided than the more preferable cancer of conventional radiation
Therapeutic choice.
Boron neutron capture treatment (Boron Neutron Capture Therapy, BNCT) be using boracic (10B) medicine is to warm
Neutron has the characteristic of high capture cross section, by10B(n,α)7Li neutron captures and karyokinesiss reaction are produced4He and7Two heavy burdens of Li
Charged particle.See figures.1.and.2, which respectively show boron neutron capture reaction schematic diagram and10B(n,α)7Li neutron capture cores are anti-
Answer the average energy of equation, two charged particles to be about 2.33MeV, with High Linear transfer (Linear Energy Transfer,
LET), short range feature, linear energy transfer and the range of alpha-particle are respectively 150keV/ μm, 8 μm, and7Li heavy burden grains
Sub then be 175keV/ μm, 5 μm, the integrated range of two particle is approximately equivalent to a cell size, therefore for organism is caused
Radiation injury can be confined to cell level, be gathered in when boracic drug selectivity in tumor cell, and appropriate neutron of arranging in pairs or groups penetrates source,
Just the purpose that tumor cell is killed in local can be reached on the premise of not normal tissue causes too major injury.
And the beam detection and diagnosis in neutron capture treatment system belongs to a critically important problem, this is directly concerned in irradiation
The dosage and effect for the treatment of.During prior art has a kind of neutron capture treatment system of announcement, such as by advance to illuminated consideration
The spun gold that attached middle school's beamlet is determined, removes spun gold in the irradiation midway of neutron beam and determines the radiation amount of the spun gold, determine photograph
Hit the exposure dose of the neutron beam on way.And control (such as stopping etc.) neutron capture to control according to the exposure dose of the measure
Treatment system, exposes to irradiated body to make neutron beam with exposure dose according to schedule.
But now, if after the radiationization amount for determining spun gold, the exposure dose rate of neutron beam has become for example because of certain reason
It is dynamic, then cannot change fully corresponding with this kind, and having makes neutron beam is exposed to irradiated body with exposure dose according to schedule
Locate an incident and obtain difficult anxiety.That is, in above-mentioned neutron capture treatment system, it is impossible to detection neutron beam irradiation in real time
Dosage.
Therefore, it is necessary to propose a kind of spoke for neutron capture treatment system of the degree of accuracy that can improve neutron beam exposure dose
Ray detection system and radiation line detecting method.
The content of the invention
One aspect of the present invention is to provide a kind of spoke of the degree of accuracy of the neutron beam exposure dose for improving neutron capture treatment system
Ray detection system, neutron capture treatment system include charged particle beam, for by the charged particle beam entrance of charged particle beam,
There is nuclear reaction so as to produce the neutron generating unit of neutron beam, for adjusting in the generation of Jing neutrons generating unit with charged particle beam in Jing
The beam-shaping body of sub-beam flux and quality and it is adjacent to the beam of beam-shaping body and exports, wherein, neutron generating unit is contained in
In beam-shaping body, radiation detecting system includes the radiation detection dress being arranged in beam-shaping body or beam-shaping is external
Put, radiation line detector is used for real-time detection charged particle beam and is overflow by neutron generating unit Jing after there is nuclear reaction with neutron generating unit
The neutron beam for going out or the gamma-rays of generation.
Radiation detecting system further includes control device, and control device sends people according to the testing result of radiation line detector
The signal that class is perceived is confirming the next step operation of neutron capture treatment system.The signal of this human perception can be audition, regard
Feel, the signal that mankind's Functional tissue such as tactile or olfactory sensation can be perceived, such as send the siren of the sound, alarm lamp, vibration, send out
One or more form gone out in the multi-signals such as pungent abnormal smells from the patient.
Neutron capture treatment system further included for by the accelerator of charged particle accelerate (beamacceleration), control device include control unit and
The testing result of radiation detecting system is shown by display part and feeds back to testing result and added by display part, control unit
To confirm the next step operation of accelerator, display part can be the common display device such as TV or liquid crystal display to fast device.
Radiation line detector is Ionization chamber or flash detection head, and radiation detecting system is by detection signal reckoning neutron beam generation
Intensity is so as to adjusting charged particle beam and control exposure dose.
The common radiation detecting system of achievable real-time detection has ionization chamber and flash detection first two different Cleaning Principle.Wherein
During neutron beam detecting system detection neutron beam, ionization cell structure is adopted to have He-3 proportional counters, BF for substrate3Proportional counter
Device, division Ionization chamber, boron chamber, during detection gamma-rays, adopt ionization chamber for inflated type ionization chamber.And detect neutron beam and
Gamma-rays can adopt flash detection head, flash detection head then be divided into organic and inorganic material, for detection thermal neutron is used
On the way, add the high thermal neutron capture cross section elements such as Li or B its flash detection head more.In brief, in such detection device detection
Sub- energy mostly is thermal neutron, is all the dependence element heavy burden charged particle disengaged with neutron generation capture or nuclear fission reaction and core splits
Become fragment, produce in ionization chamber or flash detection head and ionize to (ion pair), after these electric charges are collected, Jing Guoshi in a large number
When circuit conversion, just current signal can be switched to voltage pulse signal.Through the size of analysis voltage pulse, then can be easily
Tell neutron signal and γ signals.In high intensity neutron field, such as BNCT then can suitably reduce the gas of ionization chamber
Pressure, the concentration that can split high neutron capture cross section element in the concentration or flash detection head of material or boron coating, just effectively can reduce
Its sensitivity to neutron, it is to avoid the situation of signal saturation occurs.
As one kind preferably, in the present embodiment, neutron beam detecting system adopts Ionization chamber.When neutron beam passes through Ionization chamber, with
There is liberation in the wall portion of Ionization chamber internal gas molecule or Ionization chamber, generate electronics and positively charged example, this electronics and
Positive charge ion is referred to as above-mentioned ion pair.As there is extra electric field high pressure free interior, therefore electronics is moved towards central anode silk,
Positive charge ion is moved towards the cathode wall of surrounding, thus produces detectable electronic pulse signal.Gas molecule is made to produce an ion
It is referred to as average free energy to required energy, the value is different according to gaseous species, such as the average free of air can about 34eV.If having
The neutron beam or gamma-rays of 340keV, can make air produce about 10k ion pair.
As another kind preferably, in the present embodiment, neutron beam detecting system adopts flash detection head.Cucumber energy absorption it
After can release visible ray, this kind of material is referred to as scitillating material.It is penetrated the electron excitation in crystal or molecule extremely using free Radiation
Sharp state, and monitor for making neutron beam after the fluorescence released when electronics returns to ground state is collected.Flash detection head is made with neutron beam
With rear launched visible ray, using photomultiplier tube it will be seen that light is converted into electronics, then amplification of doubling, usual electron multiplication
Amplification is up to 107 to 108.The electron number of anode output is directly proportional to the neutron beam energy of incidence, therefore flash detection head energy
Measurement neutron beam or gamma-ray energy.
The slow body and slow body that beam-shaping body includes reflector, surrounded and be adjacent to neutron generating unit by reflector is adjacent
Thermal neutron absorber and the radiation shield being arranged in beam-shaping body.
Another aspect of the present invention is to provide a kind of degree of accuracy of the neutron beam exposure dose for improving neutron capture treatment system
Radiation line detecting method, wherein, neutron capture treatment system includes charged particle beam, the band electrochondria for passing through charged particle beam
There is nuclear reaction so as to produce the neutron generating unit of neutron beam, for adjusting the generation of Jing neutrons in beamlet entrance, Jing and charged particle beam
The beam-shaping body of neutron beam flux and quality that portion produces and the beam outlet of beam-shaping body is adjacent to, wherein, neutron product
Life portion is contained in beam-shaping body；Radiation detecting system includes the spoke being arranged in beam-shaping body or beam-shaping is external
Ray detecting apparatus, radiation line detector are used to detect that charged particle beam is produced by neutron Jing after with the generation nuclear reaction of neutron generating unit
Neutron beam or the gamma-rays of generation that life portion overflows；Detection method includes detecting step, detecting step real-time detection charged particle
Neutron beam or the gamma-rays of generation that Shu Jingyu neutrons generating unit is overflowed by neutron generating unit after there is nuclear reaction.
Detection method further includes rate-determining steps, and rate-determining steps control neutron capture according to the testing result in detecting step
The next step operation for the treatment of system.
As one kind preferably, neutron capture treatment system is further included for by the accelerator of charged particle accelerate (beamacceleration), controlling
Step controls accelerator to confirm the next step operation of accelerator according to the testing result in detecting step.
Control device includes display part, and detection method further includes step display, and step display is by the detection in detecting step
As a result show via display part.
Detection method further includes to calculate step according to the testing result in detecting step, reckoning step calculates that neutron beam occurs
Intensity is so as to adjusting charged particle beam and control exposure dose.
Description of the drawings
Fig. 1 is boron neutron capture reaction schematic diagram.
Fig. 2 is10B(n,α)7Li neutron capture nuclear equation formulas.
Fig. 3 is the floor map of the radiation detecting system for neutron capture treatment system in the embodiment of the present invention.
Specific embodiment
Neutron capture treats the application as a kind of means of effective treating cancer in recent years gradually to be increased, wherein being caught with boron neutron
Obtain and treat most commonly seen, the neutron for supplying the treatment of boron neutron capture can be supplied by nuclear reactor or accelerator.The enforcement of the present invention
By taking the treatment of accelerator boron neutron capture as an example, the basic module of accelerator boron neutron capture treatment is generally included for band electrochondria example
Accelerator, target and hot removal system and beam-shaping body that sub (such as proton, deuteron etc.) is accelerated, wherein accelerating powered
The effect of particle and metal targets produces neutron, according to required neutron yield rate and energy, available acceleration charged particle energy with
Selecting suitable nuclear reaction, the nuclear reaction for often coming into question has the characteristics such as size of current, the materialization of metal targets7Li(p,n)7Be
And9Be(p,n)9B, both reactions are all the endothermic reaction.The energy threshold of two kinds of nuclear reactions is respectively 1.881MeV and 2.055MeV,
Due to the epithermal neutron that the preferable neutron source of boron neutron capture treatment is keV energy grades, if being only slightly taller than using energy in theory
The proton bombardment lithium metal target of threshold values, can produce the neutron of relative mental retardation, be not necessary to too many slow process and just can be used for clinic,
But two kinds of targets of lithium metal (Li) and beryllium metal (Be) are not high with the proton-effect section of threshold values energy, it is that generation is sufficiently large
Neutron flux, generally from higher-energy proton causing nuclear reaction.
Preferably target should possess high neutron yield rate, the neutron energy distribution of generation is close to epithermal neutron energy area (will in detail below
Description), without wear by force too much radiation produce, the characteristic such as cheap easily operated and high temperature resistant of safety, but actually and cannot find and meet
The nuclear reaction for being required, adopts target made by lithium metal in embodiments of the invention.But it is well known to those skilled in the art,
The material of target can also be made up of other metal materials in addition to the above-mentioned metal material talked about.
Requirement for hot removal system is then different according to the nuclear reaction for selecting, such as7Li(p,n)7Be is because of metal targets (lithium metal)
Fusing point and thermal conductivity coefficient it is poor, the requirement to hot removal system just compared with9Be(p,n)9B is high.Adopt in embodiments of the invention7Li(p,n)7The nuclear reaction of Be.
No matter nuclear reaction of the neutron source of boron neutron capture treatment from nuclear reactor or accelerator charged particle and target, generation
It is all mixed radiation field, i.e. beam and contains the neutron of mental retardation to high energy, photon；For the boron neutron capture of deep tumor is treated,
In addition to epithermal neutron, remaining radiation content is more, causes the ratio of the non-selective dosage deposition of normal structure bigger, because
This these the radiation of unnecessary dosage can be caused to reduce as far as possible.Except air beam quality factor, to know more about neutron in human body
In the dose distribution that causes, used in embodiments of the invention, human body head tissue prosthesis carry out Rapid Dose Calculation, and with prosthese beam
Quality factor is used as the design reference of neutron beam, will be described in more detail below.
The neutron source that International Atomic Energy Agency (IAEA) is treated for clinical boron neutron capture, given five air beam product
Quality factor advises that this five suggestions can be used for the quality of the different neutron sources of comparison, and is provided with as selecting neutron the way of production, set
Reference frame during meter 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
Thermal and epithermal neutron flux ratio thermal to epithermal neutron flux ratio<0.05
Middle electron current and flux ratio epithermal neutron current to flux ratio>0.7
Note：Epithermal neutron energy area hankers subzone less than 0.5eV between 0.5eV to 40keV, and fast-neutron range is more than 40keV.
1st, epithermal neutron beam flux：
In neutron beam flux and tumor, boracic drug level has together decided on the clinical treatment time.If tumor boracic medicine is dense
The enough height of degree, for the requirement of neutron beam flux just can be reduced；If conversely, boracic drug level is low in tumor, needing height
Flux epithermal neutron is giving tumor enough dosage.IAEA is per second per square for the requirement of epithermal neutron beam flux
Centimetre epithermal neutron number be more than 109, the neutron beam under this flux substantially can be controlled for current boracic medicine
Treatment time, short treatment time, also can be compared with effectively utilizes in addition to positioning to patient and comfort level is advantageous in one hour
Boracic medicine is in the intra-tumor limited holdup time.
2nd, fast neutron pollution：
As fast neutron can cause unnecessary normal tissue dose, therefore it is regarded as pollution, this dosage size and neutron energy
Amount is proportionate, therefore should reduce the content of fast neutron in neutron beam design as far as possible.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。
3rd, photon contamination (gamma-ray contamination)：
Gamma-rays belong to, and can non-selectively cause the organized dosage deposition of institute on course of the beam, therefore drop
Low gamma-rays content is also the exclusive requirement of neutron beam design, and gamma-ray contamination definition is that unit epithermal neutron flux is adjoint
Gamma-rays dosage, suggestions of the IAEA to gamma-ray contamination is less than 2x 10-13Gy-cm2/n。
4th, thermal and epithermal neutron flux ratio：
As thermal neutron decay speed is fast, penetration capacity is poor, into after human body, most of energy deposition is removed in skin histology
The Several Epidermal Tumors such as melanocytoma need to be used outside the neutron source that thermal neutron is treated as boron neutron capture, for deep layers such as cerebromas
Tumor should reduce thermal neutron content.IAEA is less than 0.05 to the suggestion of thermal and epithermal neutron flux ratio.
5th, middle electron current and flux ratio：
Middle electron current represents the directivity of beam with flux ratio, and before the bigger expression neutron beam of ratio, tropism is good, Gao Qian
The neutron beam of tropism can be reduced because of the neutron normal surrounding tissue dosage that causes of diverging, also improve in addition can treat depth and
Pendulum pose gesture elasticity.IAEA centerings electron current is more than 0.7 with flux ratio suggestion.
Using prosthese organized in dose distribution, according to the dose versus depth curve of normal structure and tumor, push away to obtain prosthese beam
Quality factor.Following three parameter can be used to carry out the comparison that different neutron beams treat benefit.
1st, effective therapeutic depth：
Tumor dose is equal to the depth of normal structure maximal dose, the position after this depth, the dosage that tumor cell is obtained
Less than normal structure maximal dose, that is, lose the advantage of boron neutron capture.This parameter represents the penetration capacity of neutron beam,
Effective therapeutic depth is bigger to represent that medicable tumor depth is deeper, and unit is cm.
2nd, effective therapeutic depth close rate：
That is the tumor dose rate of effective therapeutic depth, also equal to the maximum dose rate of normal structure.Because normal structure receives total agent
Measure to affect to give the factor of tumor accumulated dose size, therefore parameter affects the length for the treatment of time, effective therapeutic depth
Close rate is bigger to represent that the irradiation time given needed for tumor doses is shorter, and unit is cGy/mA-min.
3rd, dose therapeutically effective ratio：
From brain surface to effective therapeutic depth, the mean dose ratio that tumor and normal structure are received, referred to as effectively treatment
Dose ratio；The calculating of mean dose, can be obtained by dose versus depth curve integration.Dose therapeutically effective ratio is bigger, represents
The treatment benefit of the neutron beam is better.
In order that beam-shaping body has in design compares foundation, except beam quality factor in the air of five IAEA suggestions and upper
Three parameters stated, also utilize the following parameter good and bad for assessing the performance of neutron beam dosage in the embodiment of the present invention：
1st, irradiation time≤30min (proton current that accelerator is used is 10mA)
2nd, 30.0RBE-Gy can treat depth >=7cm
3rd, tumor maximal dose >=60.0RBE-Gy
4th, normal cerebral tissue's maximal dose≤12.5RBE-Gy
5th, skin maximal dose≤11.0RBE-Gy
Note：RBE (Relative Biological Effectiveness) is relative biological effect, due to photon, neutron meeting
The biological effect that causes is different, thus dosage item as above be respectively multiplied by the relative biological effect of different tissues in the hope of etc.
Effect dosage.
Fig. 3 is referred to, the one side of the present embodiment is to provide a kind of neutron beam irradiation agent for improving neutron capture treatment system
The radiation detecting system of the degree of accuracy of amount；The other side of the present embodiment is to provide a kind of raising neutron capture treatment system
Neutron beam exposure dose degree of accuracy radiation line detecting method.
Wherein, neutron capture treatment system includes accelerator 10, expands device 20, the band electrochondria for passing through charged particle beam P
Beamlet entrance, charged particle beam P, Jing and charged particle beam P there is nuclear reaction so as to produce neutron beam N neutron generating unit T,
For adjusting the neutron beam flux of Jing neutrons generating unit T generation and the beam-shaping body 30 of quality, being adjacent to beam-shaping body 30
Beam outlet 40 and treated according to body 50 by beam exposure out at Jing beams outlet 40.Wherein, accelerator 10 is used for giving
Charged particle beam P accelerates, and can be suited to speed up type neutron capture treatment system for cyclotron or linear accelerator etc.
Accelerator；Here charged particle beam P is preferably proton beam；Expand device 20 and be arranged on accelerator 10 and neutron generating unit
Between T；Charged particle beam entrance is close to neutron generating unit T and is contained in beam-shaping body 30, as shown in Figure 3 in neutron
Generating unit T and three arrows between device are expanded as charged particle beam entrance；Neutron generating unit T is contained in beam-shaping body
In 30, neutron generating unit T here is preferably lithium metal；Beam-shaping body 30 includes reflector 31, is surrounded by reflector 31
And be adjacent to the slow body 32 of neutron generating unit T, and the adjacent thermal neutron absorber 33 of slow body 32, be arranged on beam-shaping
There is nuclear reaction with from the incident charged particle beam P of charged particle beam entrance in the radiation shield 34 in body 30, neutron generating unit T
To produce neutron beam N, neutron beam limits a main shaft, and slow body 32 is by the neutron degradation produced from neutron generating unit T to superthermal
Neutron energy range, reflector 31 will deviate from the neutron of main shaft and lead back to main shaft to improve epithermal neutron intensity of beam, thermal neutron absorber
33 are used to absorb thermal neutron to avoid causing multiple dose, radiation shield 34 to be used to shield seepage during treatment with shallow-layer normal structure
Neutron and photon reducing the normal tissue dose in non-irradiated area；Beam outlet 40 also referred to as neutron beam convergent part or collimation
Device, which reduces the width of neutron beam so that neutron beam to be assembled；The neutron beam that Jing beams outlet 40 is projected irradiates the mesh treated according to body 50
Mark position.
For improving the radiation detecting system of the degree of accuracy of the neutron beam exposure dose of neutron capture treatment system, including being arranged on
Radiation line detector 60 and control device 70 in beam-shaping body 30 or outside beam-shaping body 30, radiation detection dress
Putting 60 is used for the neutron that real-time detection charged particle beam P is overflowed by neutron generating unit T Jing after with the generation nuclear reaction of neutron generating unit T
Beam or the gamma-rays of generation.
Control device 70 is treated with confirming neutron capture according to the signal that the testing result of radiation line detector sends human perception
The next step operation of system.The signal of this human perception can be mankind's Functional tissue energy such as audition, vision, tactile or olfactory sensation
Enough signals for perceiving, the one kind in multi-signal such as such as send the siren of the sound, alarm lamp, vibrate, give out a pungent smell
Or various ways.
Neutron capture treatment system is further included for by the accelerator of charged particle accelerate (beamacceleration), control device 70 includes control unit
71 and display part 72, the testing result of radiation detecting system is shown by display part 72 and will detection by control unit 71
As a result accelerator 10 is fed back to confirm the next step operation of accelerator, display part can be common for TV or liquid crystal display etc.
Display device.
The common radiation detecting system of achievable real-time detection has ionization chamber and flash detection first two different Cleaning Principle.Wherein
During neutron beam detecting system detection neutron beam, ionization cell structure is adopted to have He-3 proportional counters, BF for substrate3Proportional counter
Device, division Ionization chamber, boron chamber, during detection gamma-rays, adopt ionization chamber for inflated type ionization chamber.And detect neutron beam and
Gamma-rays can adopt flash detection head, flash detection head then be divided into organic and inorganic material, for detection thermal neutron is used
On the way, add the high thermal neutron capture cross section elements such as Li or B its flash detection head more.In brief, in such detection device detection
Sub- energy mostly is thermal neutron, is all the dependence element heavy burden charged particle disengaged with neutron generation capture or nuclear fission reaction and core splits
Become fragment, produce in ionization chamber or flash detection head and ionize to (ion pair), after these electric charges are collected, Jing Guoshi in a large number
When circuit conversion, just current signal can be switched to voltage pulse signal.Through the size of analysis voltage pulse, then can be easily
Tell neutron signal and γ signals.In high intensity neutron field, such as BNCT then can suitably reduce the gas of ionization chamber
Pressure, the concentration that can split high neutron capture cross section element in the concentration or flash detection head of material or boron coating, just effectively can reduce
Its sensitivity to neutron, it is to avoid the situation of signal saturation occurs.
As one kind preferably, in the present embodiment, neutron beam detecting system adopts Ionization chamber.When neutron beam passes through Ionization chamber, with
There is liberation in the wall portion of Ionization chamber internal gas molecule or Ionization chamber, generate electronics and positively charged example, this electronics and
Positive charge ion is referred to as above-mentioned ion pair.As there is extra electric field high pressure free interior, therefore electronics is moved towards central anode silk,
Positive charge ion is moved towards the cathode wall of surrounding, thus produces detectable electronic pulse signal.Gas molecule is made to produce an ion
It is referred to as average free energy to required energy, the value is different according to gaseous species, such as the average free of air can about 34eV.If having
The neutron beam or gamma-rays of 340keV, can make air produce about 10k ion pair.
As another kind preferably, in the present embodiment, neutron beam detecting system adopts flash detection head.Cucumber energy absorption it
After can release visible ray, this kind of material is referred to as scitillating material.It is penetrated the electron excitation in crystal or molecule extremely using free Radiation
Sharp state, and monitor for making neutron beam after the fluorescence released when electronics returns to ground state is collected.Flash detection head is made with neutron beam
With rear launched visible ray, using photomultiplier tube it will be seen that light is converted into electronics, then amplification of doubling, usual electron multiplication
Amplification is up to 107 to 108.The electron number of anode output is directly proportional to the neutron beam energy of incidence, therefore flash detection head energy
Measurement neutron beam or gamma-ray energy.
By detection signal, radiation detecting system calculates that neutron beam occurs intensity so as to adjusting charged particle beam and controlling exposure dose.
Those skilled in the art know ground, no matter neutron beam detecting system is arranged in beam-shaping body, are also provided in neighbour
At nearly beam-shaping body, if can be used for detecting in place of set seated position the Strength Changes of the neutron beam in beam-shaping body and
The detection means of spatial distribution can then be selected.
Corresponding with above-mentioned radiation detecting system is a kind of degree of accuracy of the neutron beam exposure dose for improving neutron capture treatment system
Radiation line detecting method, wherein, neutron capture treatment system includes charged particle beam, for powered by charged particle beam
There is nuclear reaction so as to produce the neutron generating unit of neutron beam, for adjusting Jing neutrons product in particle beam entrance, Jing and charged particle beam
The beam-shaping body of neutron beam flux and quality that life portion produces and it is adjacent to the beam of beam-shaping body and exports, wherein, neutron
Generating unit is contained in beam-shaping body；Radiation detecting system includes being arranged in beam-shaping body or beam-shaping is external
Radiation line detector, radiation line detector are used to detect charged particle beam Jing after with the generation nuclear reaction of neutron generating unit by neutron
Neutron beam or the gamma-rays of generation that generating unit is overflowed；Detection method includes detecting step, detecting step real-time detection band electrochondria
Neutron beam or the gamma-rays of generation that beamlet is overflowed by neutron generating unit Jing after there is nuclear reaction with neutron generating unit.
Detection method further includes rate-determining steps, and rate-determining steps control neutron capture according to the testing result in detecting step
The next step operation for the treatment of system.
As one kind preferably, neutron capture treatment system is further included for by the accelerator of charged particle accelerate (beamacceleration), controlling
Step controls accelerator to confirm the next step operation of accelerator according to the testing result in detecting step.
Control device includes display part, and detection method further includes step display, and step display is by the detection in detecting step
As a result show via display part.
Detection method further includes to calculate step according to the testing result in detecting step, reckoning step calculates that neutron beam occurs
Intensity is so as to adjusting charged particle beam and control exposure dose.
The radiation detecting system for neutron capture treatment system that the present invention is disclosed is not limited in described in above example
Structure represented by appearance and accompanying drawing.It is aobvious and easy that material, shape and position on the basis of the present invention to wherein component is done
Insight changes, substitutes or changes, all within the scope of protection of present invention.
Claims (10)
1. a kind of radiation detecting system for neutron capture treatment system, it is characterised in that：The neutron capture treatment system includes
Charged particle beam, the charged particle beam entrance for passing through the charged particle beam, Jing are anti-with charged particle beam generation core
Should be so as to produce the neutron generating unit of neutron beam, for adjusting neutron beam flux and the quality that neutron generating unit described in Jing is produced
Beam-shaping body and be adjacent to the beam outlet of the beam-shaping body, wherein, the neutron generating unit is contained in described penetrating
In beam shaping body, the radiation detecting system includes being arranged in the beam-shaping body or the beam-shaping is external
Radiation line detector, the radiation line detector are occurred with the neutron generating unit for real-time detection charged particle beam Jing
The neutron beam overflowed by the neutron generating unit after nuclear reaction or the gamma-rays of generation.
2. the radiation detecting system for neutron capture treatment system according to claim 1, it is characterised in that：The radiation
Line detecting system further includes control device, and the control device is sent according to the testing result of the radiation line detector
The signal of human perception is confirming the next step operation of the neutron capture treatment system.
3. the radiation detecting system for neutron capture treatment system according to claim 2, it is characterised in that：The neutron
Capture treatment system is further included for by the accelerator of the charged particle accelerate (beamacceleration), the control device includes control unit
And display part, the control unit by the testing result of the radiation detecting system shown by the display part and will
Testing result feeds back to the accelerator to confirm the next step operation of the accelerator.
4. the radiation detecting system for neutron capture treatment system according to any one of claim 1-3, it is characterised in that：
For Ionization chamber or flash detection head, the radiation detecting system calculates neutron by detection signal to the line detector that radiates
Shu Fasheng intensity is so as to adjusting charged particle beam and control exposure dose.
5. the radiation detecting system for neutron capture treatment system according to any one of claim 1-3, it is characterised in that：
The beam-shaping body includes reflector, is surrounded and be adjacent to slow body and the institute of the neutron generating unit by the reflector
State the adjacent thermal neutron absorber of slow body and the radiation shield being arranged in the beam-shaping body.
6. a kind of radiation line detecting method for neutron capture treatment system, it is characterised in that：The neutron capture treatment system includes
Charged particle beam, the charged particle beam entrance for passing through the charged particle beam, Jing are anti-with charged particle beam generation core
Should be so as to produce the neutron generating unit of neutron beam, for adjusting neutron beam flux and the quality that neutron generating unit described in Jing is produced
Beam-shaping body and be adjacent to the beam outlet of the beam-shaping body, wherein, the neutron generating unit is contained in described penetrating
In beam shaping body；Radiation detecting system includes the radiation being arranged in the beam-shaping body or the beam-shaping is external
Line detector, the radiation line detector are used to detect charged particle beam Jing after with neutron generating unit generation nuclear reaction
The neutron beam overflowed by the neutron generating unit or the gamma-rays of generation；The detection method includes detecting step, the inspection
Survey what step real-time detection charged particle beam was overflowed by the neutron generating unit Jing after with neutron generating unit generation nuclear reaction
Neutron beam or the gamma-rays of generation.
7. the radiation line detecting method for neutron capture treatment system according to claim 6, it is characterised in that：The detection
Method includes rate-determining steps, and the rate-determining steps control the neutron capture according to the testing result in the detecting step
The next step operation for the treatment of system.
8. the radiation line detecting method for neutron capture treatment system according to claim 7, it is characterised in that：The neutron
Capture treatment system is further included for by the accelerator of the charged particle accelerate (beamacceleration), the rate-determining steps are according to described
Testing result in detecting step, controls the accelerator to confirm the next step operation of the accelerator.
9. the radiation line detecting method for neutron capture treatment system according to any one of claim 6-8, it is characterised in that：
The control device includes display part, and the detection method includes step display, and the step display will be in the detecting step
In testing result show via the display part.
10. the radiation line detecting method for neutron capture treatment system according to any one of claim 6-8, its feature
It is：The detection method includes calculating step that the reckoning step is pushed away according to the testing result in the detecting step
Calculate neutron beam and intensity occurs so as to adjusting charged particle beam and controlling exposure dose.
Priority Applications (8)
| Application Number | Priority Date | Filing Date | Title |
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| CN201510629532.6A CN106552321A (en) | 2015-09-28 | 2015-09-28 | Radiation detecting system and radiation line detecting method for neutron capture treatment system |
| PCT/CN2016/090271 WO2017054556A1 (en) | 2015-09-28 | 2016-07-18 | Radiation detection system and radiation detection method for neutron capture therapy system |
| EP16850180.7A EP3342459B1 (en) | 2015-09-28 | 2016-07-18 | Radiation detection system and radiation detection method for neutron capture therapy system |
| JP2018515882A JP2018529437A (en) | 2015-09-28 | 2016-07-18 | Radiation detection system and radiation detection method for neutron capture therapy system |
| US15/913,008 US20180250528A1 (en) | 2015-09-28 | 2018-03-06 | Radiation detection system and radiation detection method for neutron capture therapy system |
| JP2020160326A JP2021006266A (en) | 2015-09-28 | 2020-09-25 | Radiation detection system and radiation detection method for neutron capture therapy system |
| US17/516,775 US11740370B2 (en) | 2015-09-28 | 2021-11-02 | Radiation detection system and radiation detection method for neutron capture therapy system |
| JP2022134601A JP2022169717A (en) | 2015-09-28 | 2022-08-26 | Neutron capture therapy system and radiation detection method for neutron capture therapy system |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
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Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102905761A (en) * | 2010-07-15 | 2013-01-30 | 三菱电机株式会社 | Particle beam irradiation apparatus and particle beam therapy apparatus provided with same |
| WO2014156245A1 (en) * | 2013-03-29 | 2014-10-02 | 住友重機械工業株式会社 | Neutron capture therapy device |
| 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 |
-
2015
- 2015-09-28 CN CN201510629532.6A patent/CN106552321A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102905761A (en) * | 2010-07-15 | 2013-01-30 | 三菱电机株式会社 | Particle beam irradiation apparatus and particle beam therapy apparatus provided with same |
| WO2014156245A1 (en) * | 2013-03-29 | 2014-10-02 | 住友重機械工業株式会社 | Neutron capture therapy device |
| 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 |
Cited By (21)
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|---|---|---|---|---|
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| CN108853751A (en) * | 2017-05-12 | 2018-11-23 | 南京中硼联康医疗科技有限公司 | Photon emits detection device and the boron neutron capture treatment system with it |
| CN110709133A (en) * | 2017-07-21 | 2020-01-17 | 瓦里安医疗系统粒子疗法有限责任公司 | Particle beam monitoring system and method |
| US11458336B2 (en) | 2017-08-24 | 2022-10-04 | Neuboron Medtech Ltd. | Neutron capture therapy system comprising a beam shaping assembly configured to shape a neutron beam |
| TWI683683B (en) * | 2017-08-24 | 2020-02-01 | 中國商南京中硼聯康醫療科技有限公司 | Neutron capture therapy system |
| CN109464750A (en) * | 2017-09-07 | 2019-03-15 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
| CN109464749A (en) * | 2017-09-07 | 2019-03-15 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
| CN109464752A (en) * | 2017-09-07 | 2019-03-15 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
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| CN109464750B (en) * | 2017-09-07 | 2024-01-12 | 南京中硼联康医疗科技有限公司 | Neutron capture therapy system |
| CN109464751A (en) * | 2017-09-07 | 2019-03-15 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
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