CN205073542U - A radiant ray detecting system for neutron capture treatment system - Google Patents
A radiant ray detecting system for neutron capture treatment system Download PDFInfo
- Publication number
- CN205073542U CN205073542U CN201520760006.9U CN201520760006U CN205073542U CN 205073542 U CN205073542 U CN 205073542U CN 201520760006 U CN201520760006 U CN 201520760006U CN 205073542 U CN205073542 U CN 205073542U
- Authority
- CN
- China
- Prior art keywords
- neutron
- radiation
- charged particle
- detection system
- neutron capture
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Abstract
The utility model provides an improve the radiant ray detecting system of the neutron beam exposure dose's of neutron capture treatment system accuracy, neutron capture treatment system includes charged particle beam, a charged particle beam entry for passing through charged particle beam, through with charged particle beam thereby the neutron production portion that the nuclear reaction produced the neutron beam taking place, a beam outlet for adjusting the neutron beam flux who produces through neutron production portion and the beam shaping body of quality with border on the body in beam shaping, wherein, neutron production portion holds at beam shaping internally, radiant ray detecting system includes the radiant ray detection device who sets up in that beam shaping is internal or beam shaping is external, radiant ray detection device is used for neutron beam that real -time detection charged particle beam spills over or the gamma -ray that generates by neutron production portion after taking place the nuclear reaction with neutron production portion.
Description
Technical field
This utility model relates to a kind of radiation detection system, particularly relates to a kind of radiation detection system for neutron capture therapy system.
Background technology
Along with the development of atomics, radiation cure one of the Main Means becoming treatment of cancer such as such as cobalt 60, linear accelerator, electron beam.But conventional photonic or electronic therapy are subject to the restriction of the physical condition of lonizing radiation own, while killing tumor cell, also can normal structures a large amount of in beam approach be damaged; In addition because tumor cell is to the difference of lonizing radiation sensitivity, traditional radiation therapy is often not good for the treatment effect of the malignant tumor (as: multirow glioblastoma multiforme (glioblastomamultiforme), melanocytoma (melanoma)) compared with tool radiation resistance.
In order to reduce the radiation injury of tumor surrounding normal tissue, the target therapy concept in chemotherapy (chemotherapy) is just applied in radiation cure; And for the tumor cell of radiation resistance, also develop actively has the radiation source of high relative biological effect (relativebiologicaleffectiveness, RBE) at present, as proton therapeutic, heavy particle therapy, neutron capture treatment etc.Wherein, neutron capture treatment is in conjunction with above-mentioned two conceptions of species, as the treatment of boron neutron capture, gathers by the specificity of boracic medicine at tumor cell, coordinates neutron beam regulation and control accurately, provides and selects than the better treatment of cancer of conventional radiation.
Boron neutron capture treatment (BoronNeutronCaptureTherapy, BNCT) be utilize boracic (
10b) medicine has the characteristic of high capture cross section to thermal neutron, by
10b (n, α)
7li neutron capture and karyokinesis reaction produce
4he and
7li two heavy burden charged particle.See figures.1.and.2, which respectively show boron neutron capture reaction schematic diagram and
10b (n, α)
7li neutron capture nuclear equation formula, the average energy of two charged particles is about 2.33MeV, has High Linear transfer (LinearEnergyTransfer, LET), short range feature, the linear energy transfer of alpha-particle and range are respectively 150keV/ μm, 8 μm, and
7li heavy burden particle is then 175keV/ μm, 5 μm, the integrated range of two particle is about equivalent to a cell size, therefore the radiation injury caused for organism can be confined to cell level, when boracic drug selectivity be gathered in tumor cell, suitable neutron of arranging in pairs or groups penetrates source, just under normal tissue does not cause the prerequisite of too major injury, the object that tumor cell is killed in local can be reached.
And the beam diagnosis and detection in neutron capture therapy system belongs to a very important problem, this directly concerns dosage in irradiation treatment and effect.Prior art has in a kind of neutron capture therapy system of announcement, such as by attaching the spun gold of neutron beam mensuration in advance to irradiated body, take off spun gold in the irradiation midway of neutron beam and measure the radiation amount of this spun gold, measuring the exposure dose of the neutron beam irradiating midway.And control (such as stopping) neutron capture therapy system, to make neutron beam with exposure dose according to schedule to expose to irradiated body according to the exposure dose of this mensuration.
But now, if such as because of certain reason, after the radiation amount measuring spun gold, the exposure dose rate of neutron beam changes to some extent, then cannot change fully corresponding with this kind, and have and make, with exposure dose according to schedule, neutron beam is exposed to irradiated body place one incident and obtain difficult anxiety.That is, in above-mentioned neutron capture therapy system, detection neutron beam exposure dose that can not be real-time.
Therefore, be necessary to propose a kind of radiation detection system for neutron capture therapy system that can improve the degree of accuracy of neutron beam exposure dose.
Utility model content
An aspect of the present utility model is to provide a kind of radiation detection system improving the degree of accuracy of the neutron beam exposure dose of neutron capture therapy system, neutron capture therapy system comprises charged particle beam, for the charged particle beam entrance by charged particle beam, through producing the neutron generating unit of neutron beam with charged particle beam generation nuclear reaction, beam-shaping body for adjusting neutron beam flux and the quality produced through neutron generating unit exports with the beam being adjacent to beam-shaping body, wherein, neutron generating unit is contained in beam-shaping body, radiation detection system comprises and is arranged in beam-shaping body or radiation checkout gear that beam-shaping is external, radiation checkout gear be used for real-time detection zone beam of charged particles through with neutron generating unit generation nuclear reaction after the gamma-rays of the neutron beam that overflowed by neutron generating unit or generation.
Radiation detection system comprises control device further, and control device sends the signal of human perception to confirm next step operation of neutron capture therapy system according to the testing result of radiation checkout gear.The signal of this human perception can be that mankind's Functional tissues such as audition, vision, sense of touch or olfactory sensation can the signal of perception, as sent the siren of the sound, alarm lamp, vibrate, one or more forms in the multi-signal such as to give out a pungent smell.
Neutron capture therapy system comprises the accelerator for being accelerated by charged particle beam further, control device comprises control part and display part, the testing result of radiation detection system is shown by display part and testing result is fed back to accelerator to confirm next step operation of accelerator by control part, and display part can be the common display device such as TV or liquid crystal display.
Radiation checkout gear is Ionization chamber or flash detection head, and radiation detection system calculates neutron beam generation intensity thus adjustment belt beam of charged particles by detection signal and controls exposure dose.
The common radiation detection system that can realize detecting in real time has ionization chamber and first two different Cleaning Principle of flash detection.When wherein neutron beam detection system detects neutron beam, adopt ionization chamber structure be substrate have He-3 proportional counter, BF
3proportional counter, division Ionization chamber, boron chamber, when detecting gamma-rays, adopt ionization chamber to be inflated type ionization chamber.And detect neutron beam and gamma-rays all can adopt flash detection head, and flash detection head then can be divided into organic and inorganic material, for detection thermal neutron purposes, and its flash detection head many interpolations Li or B contour thermal neutron capture cross section element.In brief, the neutron energy of this type of detection device detection mostly is thermal neutron, be all and lean on element and neutron is caught or the heavy burden charged particle and nuclear fission fragment of disengaging are reacted in nuclear fission, produce in ionization chamber or flash detection head and ionize (ionpair) in a large number, after these electric charges are collected, through suitable circuit conversion, just can current signal be transferred to voltage pulse signal.Through the size of analytical voltage pulse, then can tell neutron signal and γ signal easily.In high strength neutron field, as BNCT, then suitably can reduce the gas pressure of ionization chamber, can split the concentration of high neutron capture cross section element in the concentration of material or boron coating or flash detection head, just effectively can reduce its sensitivity to neutron, the situation avoiding signal saturated occurs.
As one preferably, in the present embodiment, neutron beam detection system adopts Ionization chamber.When neutron beam is by Ionization chamber, with the wall portion generation liberation of Ionization chamber internal gas molecule or Ionization chamber, generate electronics and positively charged example, this electronics and positive charge ion are called above-mentioned ion pair.Owing to there being extra electric field high pressure in Ionization chamber, therefore electronics moves towards central anode silk, and positive charge ion moves towards the cathode wall of surrounding, thus produces detectable electronic pulse signal.Make gas molecule produce an ion pair institute energy requirement and be called average free energy, this value is different according to gaseous species, as the average free of air can be about 34eV.If have neutron beam or the gamma-rays of 340keV, air can be made to produce an about 10k ion pair.
As another kind preferably, in the present embodiment, neutron beam detection system adopts flash detection head.Cucumber can release visible ray after absorbing energy, and this kind of material is called scitillating material.It utilizes free Radiation to penetrate by the electron excitation in crystal or molecule to excite state, and the fluorescence of releasing when electronics gets back to ground state is used for neutron beam monitoring after being collected.The visible ray launched after flash detection head and neutron beam effect, can utilize photomultiplier tube to be electronics by visible light transformation, then amplification of doubling, and usual electron multiplication amplification can reach 107 to 108.The electron number that anode exports is directly proportional to incident neutron beam energy, and therefore flash detection head can measure neutron beam or gamma-ray energy.
Beam-shaping body comprises reflector, surrounded by reflector and be adjacent to the slow body of neutron generating unit, the thermal neutron absorber adjoined with slow body and the radiation shield be arranged in beam-shaping body.
Accompanying drawing explanation
Fig. 1 is boron neutron capture reaction schematic diagram.
Fig. 2 is
10b (n, α)
7li neutron capture nuclear equation formula.
Fig. 3 is the floor map of the radiation detection system for neutron capture therapy system in this utility model embodiment.
Detailed description of the invention
Neutron capture treatment increases gradually as a kind of means application in recent years of effective Therapeutic cancer, wherein common with the treatment of boron neutron capture, and the neutron of supply boron neutron capture treatment can by nuclear reactor or accelerator supply.Embodiment of the present utility model is treated for accelerator boron neutron capture, the basic module of accelerator boron neutron capture treatment generally includes accelerator, target and hot removal system for accelerating charged particle (as proton, deuteron etc.) and beam-shaping body, wherein accelerating charged particles and metal targets effect produce neutron, the characteristic such as materialization according to required neutron yield rate and energy, available accelerating charged particles energy and size of current, metal targets selects suitable nuclear reaction, and the nuclear reaction often come into question has
7li (p, n)
7be and
9be (p, n)
9b, these two kinds of reactions are all the endothermic reaction.The energy threshold of two kinds of nuclear reactions is respectively 1.881MeV and 2.055MeV, desirable neutron source due to the treatment of boron neutron capture is the epithermal neutron of keV energy grade, if use the proton bombardment lithium metal target of energy only a little higher than threshold values in theory, the neutron of relative mental retardation can be produced, slow process that must be not too many just can be used for clinical, but the proton-effect cross section of lithium metal (Li) and beryllium metal (Be) two kinds of targets and threshold values energy is not high, for producing enough large neutron flux, the proton of higher-energy is usually selected to carry out initiated core reaction.
Desirable target should possess high neutron yield rate, generation neutron energy distribution close to epithermal neutron energy district (will be described in more detail below), without wearing by force too much that radiation produces, safety is cheaply easy to operation and the characteristic such as high temperature resistant, but in fact also cannot find the nuclear reaction meeting all requirements, in embodiment of the present utility model, adopt the metal target of lithium.But well known to those skilled in the art, the material of target also can be made up of other metal materials except the above-mentioned metal material talked about.
Requirement for hot removal system is then different according to the nuclear reaction selected, as
7li (p, n)
7be because of the fusing point of metal targets (lithium metal) and thermal conductivity coefficient poor, to the requirement of hot removal system just comparatively
9be (p, n)
9b is high.Adopt in embodiment of the present utility model
7li (p, n)
7the nuclear reaction of Be.
No matter the neutron source of boron neutron capture treatment is from the nuclear reaction of nuclear reactor or accelerator charged particle and target, generation be all mixed radiation field, namely beam contains neutron, the photon of mental retardation to high energy; Boron neutron capture for deep tumor is treated, and except epithermal neutron, remaining radiation content is more, and the ratio causing the non-selective dosage of normal structure to deposit is larger, and therefore these can cause the radiation of unnecessary dosage to reduce as far as possible.Except air beam quality factor, for more understanding the dose distribution that neutron causes in human body, use human body head tissue prosthese to carry out Rapid Dose Calculation in embodiment of the present utility model, and be used as the design reference of neutron beam with prosthese beam quality factor, will be described in more detail below.
The neutron source that International Atomic Energy Agency (IAEA) treats for clinical boron neutron capture, given five air beam quality factors suggestion, these five suggestions can be used for the quality of more different neutron source, and be provided with as select neutron the way of production, design beam-shaping body time reference frame.These five suggestions are as follows respectively:
Epithermal neutron beam flux Epithermalneutronflux>1x10
9n/cm
2s
Fast neutron pollutes Fastneutroncontamination<2x10
-13gy-cm
2/ n
Photon contamination Photoncontamination<2x10
-13gy-cm
2/ n
Thermal and epithermal neutron flux ratio thermaltoepithermalneutronfluxratio<0.05
Middle electron current and flux ratio epithermalneutroncurrenttofluxratio>0.7
Note: epithermal neutron energy district is between 0.5eV to 40keV, and hanker subzone and be less than 0.5eV, fast-neutron range is greater than 40keV.
1, epithermal neutron beam flux:
In neutron beam flux and tumor, boracic drug level determines the clinical treatment time jointly.If tumor boracic drug level is enough high, the requirement for neutron beam flux just can reduce; Otherwise, if boracic drug level is low in tumor, then need high flux epithermal neutron to give tumor enough dosage.The epithermal neutron number that IAEA is every square centimeter per second for the requirement of epithermal neutron beam flux is greater than 10
9, the neutron beam under this flux roughly can control treatment time in one hour for current boracic medicine, and short treatment time, except having superiority to patient location and comfort level, also more effectively can utilize the holdup time that boracic medicine is limited in tumor.
2, fast neutron pollutes:
Because fast neutron can cause unnecessary normal tissue dose, what therefore look is pollution, and this dosage size and neutron energy are proportionate, and therefore should reduce the content of fast neutron in neutron beam design as far as possible.Fast neutron pollutes and is defined as the adjoint fast neutron dosage of unit epithermal neutron flux, and the suggestion that IAEA pollutes fast neutron is for being less than 2x10
-13gy-cm
2/ n.
3, photon contamination (gamma-ray contamination):
Gamma-rays belongs to wears radiation by force, non-selectively can cause the organized dosage deposition of institute on course of the beam, therefore the exclusive requirement that gamma-rays content is also neutron beam design is reduced, gamma-ray contamination is defined as the adjoint gamma-rays dosage of unit epithermal neutron flux, IAEA to the suggestion of gamma-ray contamination for being less than 2x10
-13gy-cm
2/ n.
4, thermal and epithermal neutron flux ratio:
Because thermal neutron decay speed is fast, penetration capacity is poor, after entering human body, most of energy deposition is at skin histology, except the neutron source that the Several Epidermal Tumors such as melanocytoma need be treated as boron neutron capture with thermal neutron, thermal neutron content should be reduced for deep tumor such as cerebromas.IAEA advises as being less than 0.05 thermal and epithermal neutron flux ratio.
5, middle electron current and flux ratio:
Middle electron current and flux ratio represent the directivity of beam, and before ratio larger expression neutron beam, tropism is good, and before high, the neutron beam of tropism can reduce because neutron disperses the normal surrounding tissue dosage caused, and also improve in addition and can treat the degree of depth and pendulum pose gesture elasticity.IAEA centering electron current and flux ratio are advised as being greater than 0.7.
Utilize prosthese to obtain in-house dose distribution, according to the dose versus depth curve of normal structure and tumor, push away to obtain prosthese beam quality factor.Following three parameters can be used for the comparison carrying out different neutron beam treatment benefit.
1, effective therapeutic depth:
Tumor dose equals the degree of depth of normal structure maximal dose, the position after this degree of depth, and the dosage that tumor cell obtains is less than normal structure maximal dose, namely loses the advantage of boron neutron capture.This parameter represents the penetration capacity of neutron beam, and the medicable tumor depth of the larger expression of effective therapeutic depth is darker, and unit is cm.
2, effective therapeutic depth close rate:
The i.e. tumor dose rate of effective therapeutic depth, also equals the maximum dose rate of normal structure.Because normal structure reception accumulated dose is the factor that impact can give tumor accumulated dose size, the therefore length of parameter influence treatment time, the irradiation time that the larger expression of effective therapeutic depth close rate gives needed for tumor doses is shorter, and unit is cGy/mA-min.
3, dose therapeutically effective ratio:
From brain surface to effective therapeutic depth, the mean dose ratio that tumor and normal structure receive, is referred to as dose therapeutically effective ratio; The calculating of mean dose, can be obtained by dose versus depth curvilinear integral.Dose therapeutically effective ratio is larger, and the treatment benefit representing this neutron beam is better.
Have in design to make beam-shaping body and compare foundation, except beam quality factor and above-mentioned three parameters in the air of five IAEA suggestions, in this utility model embodiment, also utilize the following parameter good and bad for assessment of the performance of neutron beam dosage:
1, irradiation time≤30min (the proton electric current that accelerator uses is 10mA)
2,30.0RBE-Gy can treat the degree of depth >=7cm
3, tumor maximal dose >=60.0RBE-Gy
4, normal cerebral tissue maximal dose≤12.5RBE-Gy
5, skin maximal dose≤11.0RBE-Gy
Note: RBE (RelativeBiologicalEffectiveness) is relative biological effect, the biological effect that can cause due to photon, neutron is different, so dosage item is as above multiplied by the relative biological effect of different tissues respectively in the hope of dose,equivalent.
Refer to Fig. 3, an aspect of the present embodiment is to provide a kind of radiation detection system improving the degree of accuracy of the neutron beam exposure dose of neutron capture therapy system; Another aspect of the present embodiment is to provide a kind of radiation detection method improving the degree of accuracy of the neutron beam exposure dose of neutron capture therapy system.
Wherein, neutron capture therapy system comprise accelerator 10, parallel beam expand device 20, for by the charged particle beam entrance of charged particle beam P, charged particle beam P, through there is nuclear reaction with charged particle beam P thus produce neutron beam N neutron generating unit T, to export 40 and treated photograph body 50 by what export 40 places beam exposure out through beam for the beam-shaping body 30 adjusting neutron beam flux and the quality produced through neutron generating unit T, the beam that is adjacent to beam-shaping body 30.Wherein, accelerator 10 is used for accelerating to charged particle beam P, can be applicable to the accelerator accelerating type neutron capture therapy system for cyclotron or linear accelerator etc., here charged particle beam P is preferably proton beam, parallel beam expand device 20 is arranged between accelerator 10 and neutron generating unit T, charged particle beam entrance next-door neighbour neutron generating unit T is also contained in beam-shaping body 30, and between neutron generating unit T and parallel beam expand device three arrows are as shown in Figure 3 as charged particle beam entrance, neutron generating unit T is contained in beam-shaping body 30, and neutron generating unit T is here preferably lithium metal, beam-shaping body 30 comprises reflector 31, surrounded by reflector 31 and be adjacent to the slow body 32 of neutron generating unit T, the thermal neutron absorber 33 adjacent with slow body 32, be arranged on the radiation shield 34 in beam-shaping body 30, neutron generating unit T with there is nuclear reaction to produce neutron beam N from the charged particle beam P of charged particle beam entrance incidence, neutron beam limits a main shaft, slow body 32 by the neutron degradation that produces from neutron generating unit T to epithermal neutron energy district, the neutron departing from main shaft is led back to main shaft to improve epithermal neutron intensity of beam by reflector 31, thermal neutron absorber 33 for absorb thermal neutron with avoid treatment time and shallow-layer normal structure caused multiple dose, radiation shield 34 is for shielding the neutron of seepage and photon to reduce the normal tissue dose in non-irradiated district, beam outlet 40 also can be called neutron beam convergent part or collimator, and its width reducing neutron beam is to assemble neutron beam, neutron beam through beam outlet 40 injection irradiates the target site treated according to body 50.
For improving the radiation detection system of the degree of accuracy of the neutron beam exposure dose of neutron capture therapy system, comprise and be arranged on radiation checkout gear 60 in beam-shaping body 30 or outside beam-shaping body 30 and control device 70, the gamma-rays of the neutron beam that radiation checkout gear 60 is overflowed by neutron generating unit T for real-time detection zone beam of charged particles P after there is nuclear reaction with neutron generating unit T or generation.
Control device 70 sends the signal of human perception to confirm next step operation of neutron capture therapy system according to the testing result of radiation checkout gear.The signal of this human perception can be that mankind's Functional tissues such as audition, vision, sense of touch or olfactory sensation can the signal of perception, as sent the siren of the sound, alarm lamp, vibrate, one or more forms in the multi-signal such as to give out a pungent smell.
Neutron capture therapy system comprises the accelerator for being accelerated by charged particle beam further, control device 70 comprises control part 71 and display part 72, the testing result of radiation detection system is shown by display part 72 and testing result is fed back to accelerator 10 to confirm next step operation of accelerator by control part 71, and display part can be the common display device such as TV or liquid crystal display.
The common radiation detection system that can realize detecting in real time has ionization chamber and first two different Cleaning Principle of flash detection.When wherein neutron beam detection system detects neutron beam, adopt ionization chamber structure be substrate have He-3 proportional counter, BF
3proportional counter, division Ionization chamber, boron chamber, when detecting gamma-rays, adopt ionization chamber to be inflated type ionization chamber.And detect neutron beam and gamma-rays all can adopt flash detection head, and flash detection head then can be divided into organic and inorganic material, for detection thermal neutron purposes, and its flash detection head many interpolations Li or B contour thermal neutron capture cross section element.In brief, the neutron energy of this type of detection device detection mostly is thermal neutron, be all and lean on element and neutron is caught or the heavy burden charged particle and nuclear fission fragment of disengaging are reacted in nuclear fission, produce in ionization chamber or flash detection head and ionize (ionpair) in a large number, after these electric charges are collected, through suitable circuit conversion, just can current signal be transferred to voltage pulse signal.Through the size of analytical voltage pulse, then can tell neutron signal and γ signal easily.In high strength neutron field, as BNCT, then suitably can reduce the gas pressure of ionization chamber, can split the concentration of high neutron capture cross section element in the concentration of material or boron coating or flash detection head, just effectively can reduce its sensitivity to neutron, the situation avoiding signal saturated occurs.
As one preferably, in the present embodiment, neutron beam detection system adopts Ionization chamber.When neutron beam is by Ionization chamber, with the wall portion generation liberation of Ionization chamber internal gas molecule or Ionization chamber, generate electronics and positively charged example, this electronics and positive charge ion are called above-mentioned ion pair.Owing to there being extra electric field high pressure in Ionization chamber, therefore electronics moves towards central anode silk, and positive charge ion moves towards the cathode wall of surrounding, thus produces detectable electronic pulse signal.Make gas molecule produce an ion pair institute energy requirement and be called average free energy, this value is different according to gaseous species, as the average free of air can be about 34eV.If have neutron beam or the gamma-rays of 340keV, air can be made to produce an about 10k ion pair.
As another kind preferably, in the present embodiment, neutron beam detection system adopts flash detection head.Cucumber can release visible ray after absorbing energy, and this kind of material is called scitillating material.It utilizes free Radiation to penetrate by the electron excitation in crystal or molecule to excite state, and the fluorescence of releasing when electronics gets back to ground state is used for neutron beam monitoring after being collected.The visible ray launched after flash detection head and neutron beam effect, can utilize photomultiplier tube to be electronics by visible light transformation, then amplification of doubling, and usual electron multiplication amplification can reach 107 to 108.The electron number that anode exports is directly proportional to incident neutron beam energy, and therefore flash detection head can measure neutron beam or gamma-ray energy.
Radiation detection system calculates neutron beam generation intensity thus adjustment belt beam of charged particles by detection signal and controls exposure dose.
Those skilled in the art know ground, might as well in beam-shaping body no matter neutron beam detection system is arranged on, still contiguous beam-shaping body place is arranged on, as long as can be used for detecting the Strength Changes of neutron beam in beam-shaping body and the checkout gear of spatial distribution then can be selected in set position part.
Corresponding with above-mentioned radiation detection system is a kind of radiation detection method improving the degree of accuracy of the neutron beam exposure dose of neutron capture therapy system, wherein, neutron capture therapy system comprise charged particle beam, for by the charged particle beam entrance of charged particle beam, through with charged particle beam generation nuclear reaction thus produce neutron beam neutron generating unit, export for the beam-shaping body that adjusts neutron beam flux and the quality produced through neutron generating unit and the beam that is adjacent to beam-shaping body, wherein, neutron generating unit is contained in beam-shaping body; Radiation detection system comprises and is arranged in beam-shaping body or radiation checkout gear that beam-shaping is external, radiation checkout gear be used for detection zone beam of charged particles through with neutron generating unit generation nuclear reaction after the gamma-rays of the neutron beam that overflowed by neutron generating unit or generation; Detection method comprises detecting step, the real-time detection zone beam of charged particles of detecting step through with neutron generating unit generation nuclear reaction after the gamma-rays of the neutron beam that overflowed by neutron generating unit or generation.
Detection method comprises rate-determining steps further, and rate-determining steps, according to the testing result in detecting step, controls next step operation of neutron capture therapy system.
As one preferably, neutron capture therapy system comprises the accelerator for being accelerated by charged particle beam further, and rate-determining steps, according to the testing result in detecting step, controls accelerator to confirm next step operation of accelerator.
Control device comprises display part, and detection method comprises step display further, and the testing result in detecting step shows via display part by step display.
Detection method comprises reckoning step further, calculates that step is according to the testing result reckoning neutron beam generation intensity in detecting step thus adjustment belt beam of charged particles control exposure dose.
The radiation detection system for neutron capture therapy system that this utility model discloses is not limited to the content described in above embodiment and the structure represented by accompanying drawing.The change apparently that basis of the present utility model is made the material of wherein component, shape and position, to substitute or amendment, all within the scope that this utility model is claimed.
Claims (5)
1. the radiation detection system for neutron capture therapy system, it is characterized in that: described neutron capture therapy system comprises charged particle beam, for the charged particle beam entrance by described charged particle beam, through producing the neutron generating unit of neutron beam with described charged particle beam generation nuclear reaction, beam-shaping body for adjusting neutron beam flux and the quality produced through described neutron generating unit exports with the beam being adjacent to described beam-shaping body, wherein, described neutron generating unit is contained in described beam-shaping body, described radiation detection system comprises and is arranged in described beam-shaping body or radiation checkout gear that described beam-shaping is external, described radiation checkout gear be used for real-time detection zone beam of charged particles through with described neutron generating unit generation nuclear reaction after the gamma-rays of the neutron beam that overflowed by described neutron generating unit or generation.
2. the radiation detection system for neutron capture therapy system according to claim 1, it is characterized in that: described radiation detection system comprises control device further, described control device sends the signal of human perception to confirm next step operation of described neutron capture therapy system according to the testing result of described radiation checkout gear.
3. the radiation detection system for neutron capture therapy system according to claim 2, it is characterized in that: described neutron capture therapy system comprises the accelerator for being accelerated by described charged particle beam further, described control device comprises control part and display part, and the testing result of described radiation detection system is shown by described display part and testing result fed back to described accelerator to confirm next step operation of described accelerator by described control part.
4. the radiation detection system for neutron capture therapy system according to any one of claim 1-3, it is characterized in that: described radiation checkout gear is Ionization chamber or flash detection head, described radiation detection system calculates neutron beam generation intensity thus adjustment belt beam of charged particles by detection signal and controls exposure dose.
5. the radiation detection system for neutron capture therapy system according to any one of claim 1-3, is characterized in that: described beam-shaping body comprises reflector, surrounded by described reflector and be adjacent to the slow body of described neutron generating unit, the thermal neutron absorber adjoined with described slow body and the radiation shield be arranged in described beam-shaping body.
Priority Applications (8)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520760006.9U CN205073542U (en) | 2015-09-28 | 2015-09-28 | A radiant ray detecting system for neutron capture treatment system |
| EP16850180.7A EP3342459B1 (en) | 2015-09-28 | 2016-07-18 | Radiation detection system and radiation detection method for neutron capture therapy system |
| PCT/CN2016/090271 WO2017054556A1 (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 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520760006.9U CN205073542U (en) | 2015-09-28 | 2015-09-28 | A radiant ray detecting system for neutron capture treatment system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN205073542U true CN205073542U (en) | 2016-03-09 |
Family
ID=55425987
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201520760006.9U Active CN205073542U (en) | 2015-09-28 | 2015-09-28 | A radiant ray detecting system for neutron capture treatment system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN205073542U (en) |
Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2017054556A1 (en) * | 2015-09-28 | 2017-04-06 | 南京中硼联康医疗科技有限公司 | Radiation detection system and radiation detection method for neutron capture therapy system |
| CN106772542A (en) * | 2016-11-24 | 2017-05-31 | 江苏超敏仪器有限公司 | A kind of method of profile of beam dosage measurement detection |
| CN107224675A (en) * | 2016-03-25 | 2017-10-03 | 南京中硼联康医疗科技有限公司 | Boron neutron capture treatment system |
| WO2017181790A1 (en) * | 2016-04-19 | 2017-10-26 | 南京中硼联康医疗科技有限公司 | Neutron capture therapy system for eliminating amyloid β-protein plaque |
| WO2017215659A1 (en) * | 2016-06-17 | 2017-12-21 | 深圳市奥沃医学新技术发展有限公司 | Imaging collimator, treatment head, and treatment device |
| WO2018006551A1 (en) * | 2016-07-04 | 2018-01-11 | 南京中硼联康医疗科技有限公司 | Neutron therapy device |
| CN107998517A (en) * | 2016-10-31 | 2018-05-08 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
| CN108066901A (en) * | 2016-11-14 | 2018-05-25 | 南京中硼联康医疗科技有限公司 | Radiation shield device and method based on medical image |
| CN108295385A (en) * | 2017-01-11 | 2018-07-20 | 南京中硼联康医疗科技有限公司 | Neutron capture therapeutic device |
| 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 |
| JP2019519332A (en) * | 2016-07-04 | 2019-07-11 | 南京中硼▲聯▼康医▲療▼科技有限公司Ｎｅｕｂｏｒｏｎ Ｍｅｄｔｅｃｈ Ｌｔｄ． | Neutron treatment device |
| US11740370B2 (en) | 2015-09-28 | 2023-08-29 | Neuboron Medtech Ltd. | Radiation detection system and radiation detection method for neutron capture therapy system |
| TWI817367B (en) * | 2021-02-25 | 2023-10-01 | 美商西屋電器公司 | Devices and methods for delivering delta radiation using prompt neutron capture gamma radiation |
-
2015
- 2015-09-28 CN CN201520760006.9U patent/CN205073542U/en active Active
Cited By (24)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2017054556A1 (en) * | 2015-09-28 | 2017-04-06 | 南京中硼联康医疗科技有限公司 | Radiation detection system and radiation detection method for neutron capture therapy system |
| US11740370B2 (en) | 2015-09-28 | 2023-08-29 | Neuboron Medtech Ltd. | Radiation detection system and radiation detection method for neutron capture therapy system |
| CN107224675A (en) * | 2016-03-25 | 2017-10-03 | 南京中硼联康医疗科技有限公司 | Boron neutron capture treatment system |
| JP2019513493A (en) * | 2016-04-19 | 2019-05-30 | 南京中硼▲聯▼康医▲療▼科技有限公司Ｎｅｕｂｏｒｏｎ Ｍｅｄｔｅｃｈ Ｌｔｄ． | Neutron capture therapy system for removing beta amyloid deposited plaques |
| CN107303411B (en) * | 2016-04-19 | 2020-04-14 | 南京中硼联康医疗科技有限公司 | Neutron capture therapy system for eliminating β amyloid deposit plaques |
| CN107303411A (en) * | 2016-04-19 | 2017-10-31 | 南京中硼联康医疗科技有限公司 | The neutron capture treatment system of patch is deposited for eliminating amyloid beta |
| WO2017181790A1 (en) * | 2016-04-19 | 2017-10-26 | 南京中硼联康医疗科技有限公司 | Neutron capture therapy system for eliminating amyloid β-protein plaque |
| WO2017215659A1 (en) * | 2016-06-17 | 2017-12-21 | 深圳市奥沃医学新技术发展有限公司 | Imaging collimator, treatment head, and treatment device |
| JP2019519333A (en) * | 2016-07-04 | 2019-07-11 | 南京中硼▲聯▼康医▲療▼科技有限公司Ｎｅｕｂｏｒｏｎ Ｍｅｄｔｅｃｈ Ｌｔｄ． | Neutron treatment device |
| WO2018006551A1 (en) * | 2016-07-04 | 2018-01-11 | 南京中硼联康医疗科技有限公司 | Neutron therapy device |
| US10744345B2 (en) | 2016-07-04 | 2020-08-18 | Neuboron Medtech Ltd. | Neutron therapy apparatus |
| RU2707651C1 (en) * | 2016-07-04 | 2019-11-28 | Нойборон Медтех Лтд. | Apparatus for neutron therapy |
| JP2019519332A (en) * | 2016-07-04 | 2019-07-11 | 南京中硼▲聯▼康医▲療▼科技有限公司Ｎｅｕｂｏｒｏｎ Ｍｅｄｔｅｃｈ Ｌｔｄ． | Neutron treatment device |
| CN107998517A (en) * | 2016-10-31 | 2018-05-08 | 南京中硼联康医疗科技有限公司 | Neutron capture treatment system |
| CN107998517B (en) * | 2016-10-31 | 2024-04-12 | 南京中硼联康医疗科技有限公司 | Neutron capture therapy system |
| CN108066901A (en) * | 2016-11-14 | 2018-05-25 | 南京中硼联康医疗科技有限公司 | Radiation shield device and method based on medical image |
| CN108066901B (en) * | 2016-11-14 | 2024-04-12 | 南京中硼联康医疗科技有限公司 | Radiation shielding device and method based on medical image |
| CN106772542B (en) * | 2016-11-24 | 2019-04-16 | 江苏超敏科技有限公司 | A kind of method of profile of beam dosage measurement detection |
| CN106772542A (en) * | 2016-11-24 | 2017-05-31 | 江苏超敏仪器有限公司 | A kind of method of profile of beam dosage measurement detection |
| CN108295385A (en) * | 2017-01-11 | 2018-07-20 | 南京中硼联康医疗科技有限公司 | Neutron capture therapeutic device |
| CN108295385B (en) * | 2017-01-11 | 2024-04-16 | 南京中硼联康医疗科技有限公司 | Neutron capture therapeutic device |
| CN109464752B (en) * | 2017-09-07 | 2024-02-09 | 南京中硼联康医疗科技有限公司 | Neutron capture therapy 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 |
| TWI817367B (en) * | 2021-02-25 | 2023-10-01 | 美商西屋電器公司 | Devices and methods for delivering delta radiation using prompt neutron capture gamma radiation |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN205073542U (en) | A radiant ray detecting system for neutron capture treatment system | |
| CN205073541U (en) | A beam diagnostic system for neutron capture treatment system | |
| CN106552321A (en) | Radiation detecting system and radiation line detecting method for neutron capture treatment system | |
| US10926110B2 (en) | Beam diagnostic system for neutron capture therapy system | |
| EP3342459B1 (en) | Radiation detection system and radiation detection method for neutron capture therapy system | |
| EP3395407B9 (en) | Neutron capture therapy system | |
| EP3588144B1 (en) | Method for measuring radiation dose | |
| CN114534117B (en) | Neutron capture therapy device | |
| Mesbahi et al. | Effect of wedge filter and field size on photoneutron dose equivalent for an 18 MV photon beam of a medical linear accelerator | |
| WO2022002229A1 (en) | Neutron capture therapy apparatus and operation steps of monitoring system therefor | |
| Ghassoun et al. | Spatial and spectral characteristics of a compact system neutron beam designed for BNCT facility | |
| US11740370B2 (en) | Radiation detection system and radiation detection method for neutron capture therapy system | |
| Hu et al. | Accelerator based epithermal neutron source for clinical boron neutron capture therapy | |
| KR20200111267A (en) | System for direct production of therapeutic yttrium-90 for cancer treatment | |
| Kobayashi et al. | A novel BNCT irradiation system with an on-line monitor using 7Li (P, N) 7Be near threshold neutrons |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |