CN106980136A - 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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Classifications
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/1048—Monitoring, verifying, controlling systems and methods
- A61N5/1064—Monitoring, verifying, controlling systems and methods for adjusting radiation treatment in response to monitoring
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
- G01T3/06—Measuring neutron radiation with scintillation detectors
-
- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/103—Treatment planning systems
-
- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/1048—Monitoring, verifying, controlling systems and methods
- A61N5/1071—Monitoring, verifying, controlling systems and methods for verifying the dose delivered by the treatment plan
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N2005/1085—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy characterised by the type of particles applied to the patient
- A61N2005/109—Neutrons
Abstract
One aspect of the present invention is to provide a kind of accuracy of neutron beam exposure dose for improving neutron capture treatment system and can find the radiation detecting system for neutron capture treatment system of trouble location in time, wherein, neutron capture treatment system includes charged particle beam, for the charged particle beam entrance by charged particle beam, through occurring nuclear reaction with charged particle beam so as to produce the neutron generating unit of neutron beam, exported for the beam-shaping body for adjusting the neutron beam flux produced through neutron generating unit and quality and the beam for being adjacent to beam-shaping body, wherein, radiation detecting system includes radiation line detector, radiation line detector is used for the gamma-rays sent out in wink after detection is irradiated through neutron beam in real time.It is another aspect of the invention to provide it is a kind of improve neutron capture treatment system neutron beam exposure dose accuracy and the radiation line detecting method for neutron capture treatment system of trouble location can be found in time.
Description
Technical field
The present invention relates to a kind of radiation detecting system, more particularly to a kind of radiation for neutron capture treatment system
Detecting system；The invention further relates to one kind radiation line detecting method, more particularly to a kind of spoke for neutron capture treatment system
Ray detection method.
Background technology
With the development of atomics, the radiation cure such as cobalt 60, linear accelerator, electron beam turns into cancer
One of Main Means of disease treatment.But conventional photonic or electronic therapy are limited by radioactive ray physical condition itself, are being killed
While dead tumour cell, substantial amounts of normal structure in beam approach can also be damaged；Additionally, due to tumour cell to putting
The difference of radiation-sensitive degree, traditional radiation therapy is for relatively having the malignant tumour of radiation resistance (such as：Multirow glioblast
Knurl (glioblastoma multiforme), melanocytoma (melanoma)) treatment effect it is often not good.
In order to reduce the radiation injury of tumour surrounding normal tissue, the target therapy in chemotherapy (chemotherapy)
Concept is just applied in radiation cure；And for the tumour cell of radiation resistance, also actively development has high phase at present
To biological effect (relative biological effectiveness, RBE) radiation source, such as proton therapeutic, heavy particle is controlled
Treatment, neutron capture treatment etc..Wherein, neutron capture treatment is to combine above two concept, and such as boron neutron capture is treated, by
Boracic medicine gathers in the specificity of tumour cell, and coordinating accurately neutron beam regulation and control, there is provided more more preferable than conventional radiation
Treatment of cancer is selected.
Boron neutron capture treatment (Boron Neutron Capture Therapy, BNCT) be using boracic (10B) medicine
There is the characteristic of high capture cross section to thermal neutron, by10B(n,α)7Li neutron captures and nuclear fission reaction are produced4He and7Li two
Individual heavy burden charged particle.Referring to Figures 1 and 2, which respectively show boron neutron capture reaction schematic diagram and10B(n,α)7Li neutrons
Nuclear equation formula is captured, the average energy of two charged particles is about 2.33MeV, (Linear Energy are shifted with High Linear
Transfer, LET), short range feature, the linear energy transfers of α particles and range are respectively 150keV/ μm, 8 μm, and7Li weights
Lotus particle is then 175keV/ μm, 5 μm, and the integrated range of two particle is approximately equivalent to a cell size, therefore is caused for organism
Radiation injury can be confined to cell level, be gathered in when boracic drug selectivity in tumour cell, the appropriate neutron of arranging in pairs or groups
Source is penetrated, just the local purpose for killing tumour cell 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 belong to a critically important problem, this is directly concerned
In the dosage and effect of irradiation treatment.Prior art has in a kind of neutron capture treatment system of announcement, such as by advance to quilt
Irradiation body attaches the spun gold of neutron beam measure, removes spun gold in the irradiation midway of neutron beam and determines the radiation of the spun gold
Amount, to determine the exposure dose for the neutron beam for irradiating midway.And controlled (for example to stop according to the exposure dose of the measure
Deng) neutron capture treatment system, expose to irradiated body to make neutron beam with exposure dose according to schedule.
But now, if for example because of certain reason determine spun gold radiationization amount after neutron beam exposure dose rate
It has been changed that, then can not change fully corresponding with this kind, and having makes to expose to neutron beam with exposure dose according to schedule
An incident obtains difficult anxiety at irradiated body.That is, in above-mentioned neutron capture treatment system, it is impossible to detect spoke in real time
The exposure dose of ray.In addition, once having detection device to break down, out of order source can not be soon judged at all, because
Taken time and effort during this malfunction elimination.
Therefore, it is necessary to propose a kind of accuracy that can improve irradiation with radiation dosage and failure can be found in time
The radiation detecting system and its detection method for neutron capture treatment system at position.
The content of the invention
One aspect of the present invention is to provide a kind of essence for the neutron beam exposure dose for improving neutron capture treatment system
Exactness and the radiation detecting system for neutron capture treatment system that trouble location can be found in time, wherein, neutron
Capture treatment system include charged particle beam, for the charged particle beam entrance by charged particle beam, through with charged particle beam
Occur nuclear reaction so as to produce neutron beam neutron generating unit, for adjust through neutron generating unit produce neutron beam flux with
The beam-shaping body of quality and the beam outlet for being adjacent to beam-shaping body, wherein, radiation detecting system is examined including radiation
Device is surveyed, radiation line detector is used for the gamma-rays sent out in wink after detection is irradiated through neutron beam in real time.
So-called " gamma-rays that wink is sent out after being irradiated through neutron beam " refers to that with other elements neutron capture core occurs for neutron beam
The gamma-rays produced during reaction, other elements are not limited to the element of boron -10, and neutron capture occurs as known in the art for other elements
Gamma-ray element can be produced during nuclear reaction also central in this definition.In the embodiment of the present invention, " wink is sent out after being irradiated through neutron beam
Gamma-rays " is that with the element of boron -10 gamma-rays produced when boron neutron capture reacts occurs for neutron beam.
Radiation detecting system further comprises control device, and control device is according to the testing result for radiating line detector
The signal of human perception is sent to confirm the next step operation of neutron capture treatment system.The signal of this human perception can be
The signal that the mankind such as the sense of hearing, vision, tactile or smell Functional tissue can be perceived, such as sends the siren of the sound, alarm lamp, shakes
One or more forms in multi-signal such as move, give out a pungent smell.
Neutron capture treatment system further comprises for by the accelerator of charged particle accelerate (beamacceleration), control device to include control
Portion processed and display part, control unit are shown the testing result of radiation detecting system by display part and by testing result
Accelerator is fed back to confirm the next step operation of accelerator, and display part can be the common displays such as TV or liquid crystal display
Equipment.
Line detector is radiated to detect gamma-ray Ionization chamber or flash detection head, radiation detecting system passes through detection
To γ signals extrapolate boron concentration value.
The common radiation detecting system that can be achieved to detect in real time has ionisation chamber and first two difference detection of flash detection former
Reason.When wherein detecting gamma-rays, a kind of mode can use ionisation chamber for inflatable ionisation chamber；Another way can be using sudden strain of a muscle
Bright detecting head.
As one kind preferably, the boron concentration value is calculated using formula A and drawn：
Wherein, boron concentration value when B (t) is time t, unit is ppm, and time t unit is s, and k is tested definite value, GC
(t) the γ countings that the interval γ tales of preset energy subtract background presence are detected when for time t；The k is pushed away using formula B
Draw：
Wherein, B (t0) it is time t0When boron concentration value, unit is ppm, time t0Unit be s, GC (t0) it is time t0
When detect the interval γ tales of preset energy and subtract the γ of background presence and count, the B (t0) calculated using formula C
Go out：
B(t0)=BBlood(t0)×RT/N(formula C)
Wherein, BBlood(t0) it is time t0When the blood that calculates of meter in boron concentration value, unit is ppm；RT/NAccording to
The ratio of the boron concentration in boron concentration and normal structure in the tumour that PET or experimental data or theoretical foundation can be known.
In order to accurately judge which detection means or monitoring device break down, when following detected value and standard value hair
During raw larger difference, it may be said that bright corresponding detection means or monitoring device there occurs exception.
Tumor dose rate D during time tT(t) calculated and drawn using formula D：
DT(t)=DB(t)+Dn(t)+Dγ(t) (formula D)
Wherein, DT(t) unit is w-Gy/s；DB(t) boron close rate when for time t, unit is w-Gy/s；Dn(t) it is
Neutron dose rate during time t, unit is w-Gy/s；Dγ(t) photon doses rate when for time t, unit is w-Gy/s, described
DB(t) calculated and drawn using formula E：
The Dn(t) calculated and drawn using formula F：
The Dγ(t) calculated and drawn using formula G：
Wherein, DB,ref、Dn,ref、Dγ,nbcap,refAnd Dγ,bcap,refBoron close rate is given respectively in treatment planning systems
The light that reference value or given reference value by correction, the given reference value of neutron dose rate, the reaction of non-boron neutron capture are produced
The given reference value for the photon doses rate that given reference value and boron the neutron capture reaction of sub- close rate are produced, unit is w-
Gy/s；Sn(t) reading of the neutron beam intensity of neutron monitoring device when for time t, unit is examined for counting or by radiation
Survey the selectable reading of device；Sn,refPenetrated for the set-point of neutron beam intensity in treatment planning systems or by the neutron of correction
The set-point of beam intensity；BBlood(t) it is the boron concentration value in the blood sample sample of measurement in t, unit is ppm；BBlood, refFor treatment
The set-point of boron concentration or the set-point for the boron concentration for passing through correction in planning system, unit is ppm；f(BBlood(t),BBlood, ref) be
A set of function for drawing is precalculated by treatment plan to correct the non-linear relation between boron concentration and tumor dose.
Beam-shaping body includes reflector, is surrounded by reflector and be adjacent to the slow body of neutron generating unit and slow body
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 neutron beam exposure dose for improving neutron capture treatment system
Accuracy and the radiation line detecting method for neutron capture treatment system that trouble location can be found in time, wherein, in
Son capture treatment system include charged particle beam, for the charged particle beam entrance by charged particle beam, through with charged particle
Shu Fasheng nuclear reactions are so as to produce the neutron generating unit of neutron beam, for adjusting the neutron beam flux produced through neutron generating unit
Exported with the beam-shaping body of quality and the beam for being adjacent to beam-shaping body, wherein, neutron generating unit is contained in beam-shaping
In vivo；Radiation detecting system includes radiation line detector, and detection method includes detecting step, and detecting step includes passing through spoke
Ray detecting apparatus detects the gamma-rays sent out in wink after neutron beam irradiation in real time.
Detection method further comprises rate-determining steps, and rate-determining steps are according to the testing result in detecting step, in control
The next step operation of son capture treatment system.
As it is a kind of preferably, neutron capture treatment system further comprises for by the acceleration of charged particle accelerate (beamacceleration)
Device, rate-determining steps control 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 comprises step display, and step display will be in detecting step
Testing result shown via display part.
Detection method further comprises reckoning step, calculates that step extrapolates boron according to the testing result in detecting step
Concentration value.
As one kind preferably, the boron concentration value is calculated using formula A and drawn：
Wherein, boron concentration value when B (t) is time t, unit is ppm, and time t unit is s, and k is tested definite value, GC
(t) the γ countings that the interval γ tales of preset energy subtract background presence are detected when for time t；The k is pushed away using formula B
Draw：
Wherein, B (t0) it is time t0When boron concentration value, unit is ppm, time t0Unit be s, GC (t0) it is time t0
When detect the interval γ tales of preset energy and subtract the γ of background presence and count, the B (t0) calculated using formula C
Go out：
B(t0)=BBlood(t0)×RT/N(formula C)
Wherein, BBlood(t0) it is time t0When the blood that calculates of meter in boron concentration value, unit is ppm；RT/NAccording to
The ratio of the boron concentration in boron concentration and normal structure in the tumour that PET or experimental data or theoretical foundation can be known.
In order to accurately judge which detection means or monitoring device break down, when following detected value and standard value hair
During raw larger difference, it may be said that bright corresponding detection means or monitoring device there occurs exception.
Tumor dose rate D during time tT(t) calculated and drawn using formula D：
DT(t)=DB(t)+Dn(t)+Dγ(t) (formula D)
Wherein, DT(t) unit is w-Gy/s；DB(t) boron close rate when for time t, unit is w-Gy/s；Dn(t) it is
Neutron dose rate during time t, unit is w-Gy/s；Dγ(t) photon doses rate when for time t, unit is w-Gy/s, described
DB(t) calculated and drawn using formula E：
The Dn(t) calculated and drawn using formula F：
The Dγ(t) calculated and drawn using formula G：
Wherein, DB,ref、Dn,ref、Dγ,nbcap,refAnd Dγ,bcap,refBoron close rate is given respectively in treatment planning systems
The light that reference value or given reference value by correction, the given reference value of neutron dose rate, the reaction of non-boron neutron capture are produced
The given reference value for the photon doses rate that given reference value and boron the neutron capture reaction of sub- close rate are produced, unit is w-
Gy/s；Sn(t) reading of the neutron beam intensity of neutron monitoring device when for time t, unit is examined for counting or by radiation
Survey the selectable reading of device；Sn,refPenetrated for the set-point of neutron beam intensity in treatment planning systems or by the neutron of correction
The set-point of beam intensity；BBlood(t) it is the boron concentration value in the blood sample sample of measurement in t, unit is ppm；BBlood, refFor treatment
The set-point of boron concentration or the set-point for the boron concentration for passing through correction in planning system, unit is ppm；f(BBlood(t),BBlood, ref) be
A set of function for drawing is precalculated by treatment plan to correct the non-linear relation between boron concentration and tumor dose.
Preferably, tumor dose rate during time t can also be calculated by following formula H：
Wherein, SB(t) reading of radiation line detector when for time t, unit detects dress for counting or by radiation
Put selectable reading, SB(t) extrapolated by following formula I；C is to calculate an obtained calculated value by formula J：
Wherein, NNB,refFor the reference value of the number of times that the reaction of boron neutron capture occurs in treatment plan；kBGTo be repaiied to background
Just；σ is the detection efficiency of radiation line detector；Sn(t0) it is time t0When neutron monitoring device neutron beam intensity
Reading, unit is for counting or by the selectable reading of radiation line detector；BBlood(t0) for measurement blood sample sample in t0When
Boron concentration value, unit is ppm；f(BBlood(t0),BBlood, ref) dense to correct boron to precalculate a set of function for drawing by treatment plan
Non-linear relation between degree and tumor dose；SB(t0) be the radiation line detector set initial stage in irradiation reading, it is single
Position is for counting or by the selectable reading of radiation line detector.
Brief description of the drawings
Fig. 1 is boron neutron capture reaction schematic diagram.
Fig. 2 is10B(n,α)7Li neutron capture nuclear equation formulas.
Fig. 3 is the floor map of the beam diagnostic system for neutron capture treatment system in the embodiment of the present invention.
Fig. 4 is the box that the beam diagnostic system for neutron capture treatment system in the embodiment of the present invention is run
Figure.
Fig. 5 is the floor map of another embodiment of the first neutron beam monitoring device in beam diagnostic system.
Fig. 6 is the gamma-ray radiation detection system for being used to send out in wink after detection is irradiated through neutron beam in beam diagnostic system
The floor map of system.
Fig. 7 is the function relation figure between boron concentration and tumor dose in the embodiment of the present invention.
Embodiment
Neutron capture treatment gradually increases as a kind of application of means of effective treating cancer in recent years, wherein with boron
Neutron capture treatment is most commonly seen, and the neutron of supply boron neutron capture treatment can be supplied by nuclear reactor or accelerator.This hair
Bright embodiment is by taking the treatment of accelerator boron neutron capture as an example, and the basic module of accelerator boron neutron capture treatment generally includes to use
In the accelerator, target accelerated to charged particle (such as proton, deuteron) and hot removal system and beam-shaping body, wherein
Charged particle is accelerated to produce neutron with metal targets effect, it is powered according to required neutron yield rate and energy, available acceleration
The characteristics such as particle energy and size of current, the materialization of metal targets select suitable nuclear reaction, the nuclear reaction often come into question
Have7Li(p,n)7Be and9Be(p,n)9B, both reactions are all the endothermic reaction.The energy threshold of two kinds of nuclear reactions is respectively
1.881MeV and 2.055MeV, it is theoretical due to the epithermal neutron that the preferable neutron source that boron neutron capture is treated is keV energy grades
If the upper proton bombardment lithium metal target that threshold values is only slightly taller than using energy, the neutron of relative low energy can be produced, is not necessary to too many
Slow processing just can be used for clinic, but the proton-effect of two kinds of targets of lithium metal (Li) and beryllium metal (Be) and threshold values energy is cut
Face is not high, to produce sufficiently large neutron flux, generally triggers nuclear reaction from the proton of higher-energy.
Preferable target should possess high neutron yield rate, the neutron energy produced distribution (will be under close to epithermal neutron energy area
Text is described in detail), without it is too many wear by force radiation produce, the characteristic such as cheap easily operated and high temperature resistant of safety, but actually and can not
Find the target for meeting and being made in required nuclear reaction, embodiments of the invention of lithium metal.But art technology
Known to personnel, 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 of selection, such as7Li(p,n)7Be is because of metal targets (lithium
Metal) fusing point and thermal conductivity coefficient it is poor, requirement to hot removal system just compared with9Be(p,n)9B is high.Adopted in embodiments of the invention
With7Li(p,n)7Be nuclear reaction.
No matter boron neutron capture treatment nuclear reaction of the neutron source from nuclear reactor or accelerator charged particle and target,
What is produced is all mixed radiation field, i.e., beam contains neutron, photon of the low energy to high energy；Caught for the boron neutron of deep tumor
Treatment is obtained, in addition to epithermal neutron, remaining radiation content is more, cause the ratio of the non-selective dosage deposition of normal structure
It is bigger, therefore these can cause the radiation of unnecessary dosage to try one's best reduction.Except air beam quality factor, in knowing more about
Rapid Dose Calculation is carried out using human body head tissue prosthese in the dosage distribution that son is caused in human body, embodiments of the invention, and
It is used as the design reference of neutron beam with prosthese beam quality factor, will be described in more detail below.
International Atomic Energy Agency (IAEA) is directed to the neutron source of clinical boron neutron capture treatment, is penetrated given five air
Beam quality factor advises that this five suggestions can be used for the quality of relatively different neutron sources, and is provided with producing way as selecting neutron
Reference frame when footpath, design beam-shaping body.This five suggestion difference are as follows：
Epithermal neutron beam flux Epithermal neutron flux>1x 109n/cm2s
Fast neutron pollution 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：Subzone is hankered less than 0.5eV, fast-neutron range is more than in epithermal neutron energy area between 0.5eV to 40keV
40keV。
1st, epithermal neutron beam flux：
Boracic drug concentration has together decided on the clinical treatment time in neutron beam flux and tumour.If tumour boracic medicine
The enough height of concentration, the requirement for neutron beam flux just can be reduced；If conversely, boracic drug concentration is low in tumour, needing high pass
Epithermal neutron is measured to give the dosage that tumour is enough.IAEA is per second every square centimeter for the requirement of epithermal neutron beam flux
Epithermal neutron number be more than 109, the neutron beam under this flux can substantially control treatment for current boracic medicine
Time, short treatment time in addition to advantageous to patient's positioning and comfort level, also can more effectively utilize boracic medicine in one hour
Thing is in the intra-tumor limited holdup time.
2nd, fast neutron pollutes：
Because fast neutron can cause unnecessary normal tissue dose, therefore it is regarded as pollution, this dosage size and neutron
Energy is proportionate, thus neutron beam design on should try one's best reduction fast neutron content.Fast neutron pollution definition is unit
The adjoint fast neutron dosage of epithermal neutron flux, the suggestion that IAEA pollutes to fast neutron is less than 2x 10-13Gy-cm2/n。
3rd, photon contamination (gamma-ray contamination)：
Gamma-rays belongs to wears radiation by force, can non-selectively cause the organized dosage deposition of institute on course of the beam, therefore
Reduction 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, suggestions of the IAEA to gamma-ray contamination is less than 2x 10-13Gy-cm2/n。
4th, thermal and epithermal neutron flux ratio：
Because 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 be treated as boron neutron capture with thermal neutron
Knurl should reduce thermal neutron content.IAEA is less than 0.05 to the suggestion of thermal and epithermal neutron flux ratio.
5th, middle electron current and flux ratio：
Middle electron current represents the directionality of beam with flux ratio, and ratio is bigger to represent that tropism is good before neutron beam, high
The neutron beam of preceding tropism can reduce because neutron dissipate caused by normal surrounding tissue dosage, also improve in addition can treat depth and
Put pose gesture elasticity.IAEA centerings electron current is more than 0.7 with flux ratio suggestion.
The dosage distribution in tissue is obtained using prosthese, according to the dose versus depth curve of normal structure and tumour, pushes away false
Body beam quality factor.Following three parameter can be used for carrying out the comparison that different neutron beams treat benefit.
1st, effective therapeutic depth：
Tumor dose is equal to the depth of normal structure maximum dose, the position after this depth, what tumour cell was obtained
Dosage is less than normal structure maximum dose, that is, loses the advantage of boron neutron capture.What this parameter represented neutron beam penetrates energy
Power, effective therapeutic depth is bigger to represent that medicable tumor depth is deeper, 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 is received
Accumulated dose can give the factor of tumour accumulated dose size for influence, therefore parameter influences the length for the treatment of time, and effectively treatment is deep
Irradiation time needed for tumour doses are given in the bigger expression of degree close rate 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 tumour and normal structure are received is referred to as effective
Therapeutic 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 in the air of five IAEA suggestions beam quality because
Also the following ginseng for being used to assess neutron beam dosage performance quality is utilized in three plain and above-mentioned parameters, the embodiment of the present invention
Number：
1st, irradiation time≤30min (proton current that accelerator is used is 10mA)
2nd, 30.0RBE-Gy can treat depth >=7cm
3rd, tumour maximum dose >=60.0RBE-Gy
4th, normal cerebral tissue's maximum dose≤12.5RBE-Gy
5th, skin maximum dose≤11.0RBE-Gy
Note：RBE (Relative Biological Effectiveness) is relative biological effect, due to photon, neutron
It can cause
Biological effect is different, thus dosage item as above be respectively multiplied by the relative biological effect of different tissues in the hope of etc.
Imitate dosage.
Fig. 3 and Fig. 4 are referred to, one aspect of the present invention is the neutron beam irradiation agent for improving neutron capture treatment system
The accuracy and a kind of beam diagnostic system that can be used in neutron capture treatment system of offer of amount are to carry out fault diagnosis, one
A kind of beam diagnostic system for neutron capture treatment system is provided in individual technical scheme.
Wherein, neutron capture treatment system includes accelerator 10, expands device 20, for the band by charged particle beam P
Charged particle beam entrance, charged particle beam P, through occurring nuclear reaction with charged particle beam P so as to producing neutron beam N neutron generating unit
T, for adjust through neutron generating unit T produce neutron beam flux and quality beam-shaping body 30, be adjacent to beam-shaping
The beam of body 30 exports 40, the body to be shone 50 of the beam exposure come out at 40 is exported through beam and for cooling medium to be placed in
Neutron generating unit T sentences cooling neutron generating unit T cooling device 60.Wherein, accelerator 10 is used for adding to charged particle beam P
Speed, can be suited to speed up the accelerator of type neutron capture treatment system for cyclotron or linear accelerator etc.；This
In charged particle beam P be preferably proton beam；Device 20 is expanded to be arranged between accelerator 10 and neutron generating unit T；Band electrochondria
Beamlet 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 to expand
Three arrows between device are used as charged particle beam entrance；Neutron generating unit T is contained in beam-shaping body 30, here in
Sub- generating unit T is preferably lithium metal；Beam-shaping body 30 includes reflector 31, is surrounded by reflector 31 and be adjacent to neutron generation
Portion T slow body 32, the thermal neutron absorber 33 abutted with slow body 32, the radiation shield being arranged in beam-shaping body 30
34, neutron generating unit T from the incident charged particle beam P generation nuclear reactions of charged particle beam entrance with producing 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 epithermal neutron energy area, and reflector 31 will
The neutron for deviateing main shaft leads back to main shaft to improve epithermal neutron intensity of beam, and thermal neutron absorber 33 is used to absorb thermal neutron to keep away
Multiple dose was caused when exempting from treatment with shallow-layer normal structure, the neutron and photon that radiation shield 34 is used to shield seepage are non-to reduce
The normal tissue dose of irradiated region；Beam outlet 40 also referred to as neutron beam convergent part or collimater, it reduces neutron beam
Width is so that neutron beam to be assembled；The target site that 40 neutron beams projected irradiate body 50 to be shone is exported through beam.
Wherein, beam diagnostic system includes charged particle beam diagnostic device and neutron beam diagnostic device, beam diagnostic system
For diagnose simultaneously neutron capture treatment system and/or beam diagnostic system whether failure.Beam diagnostic system is by examining simultaneously
Charged particle beam and neutron beam are surveyed, to improve the accuracy of neutron beam exposure dose.In addition, beam diagnostic system pass through it is a series of
Testing result judging that it is abnormal which device in neutron capture treatment system and/or component are produced, or judge to penetrate
Whether the detection means itself in beam diagnostic system is abnormal.It can so accomplish to shoot the arrow at the target, improve neutron beam exposure dose
Accuracy, maintenance time and cost are greatly reduced again.
Charged particle beam diagnostic device further comprises entering the band electrochondria located before charged particle beam entrance for detecting
Beamlet P intensity and the first current sensing means 100 of stability and the band electrochondria acted on for detection warp and neutron generating unit T
Beamlet P intensity and the second current sensing means 200 of changing condition；Beam diagnostic system further comprises being used to detect cooling
The temperature of device 60 is so as to learn that cooling device 60 and neutron generating unit T produces the temperature-detecting device 300 of neutron beam N situations；In
Beamlet diagnostic device further comprise for detect the neutron beam N in beam-shaping body 30 Strength Changes and spatial distribution, bury
The first neutron beam monitoring device 400 in beam-shaping body 30 and for detecting that the neutron beam N's at beam outlet 40 is strong
Degree change and spatial distribution, the second neutron beam monitoring device 500 being embedded at beam outlet 40；Beam diagnostic system is further
Including for diagnosing the displacement detector 600 whether displacement of body 50 to be shone moves.As one kind preferably, the first neutron beam prison
Survey device 400 and be provided with two neutron beam monitoring components, i.e. the first neutron beam monitoring component 401 and second neutron beam monitoring component
402；Second neutron beam monitoring device 500 is provided with two neutron beams monitoring components, i.e. the 3rd neutron beam monitoring component 501 and the
Four neutron beams monitor component 502；Displacement detector 600 is provided with two displacement detecting components, i.e. the first displacement detecting component
601 and second displacement detection means 602.
Though the first neutron beam monitoring device 400, the second neutron beam monitoring device 500 and displacement detecting are filled in the present embodiment
To put 600 and be provided with two respective monitoring/detection means, but those skilled in the art know ground, these monitor/detect structure
The number of part can be set as needed, such as can also be 4,6 or 8.As long as neutron beam monitoring component is buried
(or neighbouring beam outlet) can be used in detecting in (or neighbouring beam-shaping body) and/or beam outlet in beam-shaping body
The Strength Changes and spatial distribution of beamlet, then this neutron beam monitoring component can be selected；As long as displacement detecting component is set
Treating to be used for detecting displacement body change to be shone according to (or neighbouring body to be shone) in vivo, then this displacement detecting component can be selected
With.In addition, the position that these monitorings/detection means are placed does not have strict limitation, as long as the position placed can be played respectively
Self-corresponding detection function.
It is such to set so that from the source of accelerator until the terminal of body to be shone is both provided with miscellaneous detection
Device, judged by these detection means neutron capture treatment system each critical component or detection means itself whether
In the presence of exception.As one kind preferably, from the source of accelerator until setting detection means as the terminal of body to be shone：Plus
It is provided with vacuum tube at fast device source at detection means, neutron generating unit and is provided with detection means, close to neutron generating unit
And it is provided with detection dress for being provided with the cooling device to neutron generating unit cooling in detection means, beam-shaping body
Put, beam exit is provided with detection means, body to be shone and is provided with detection means.
In the present embodiment, the first current sensing means 100 is Faraday cup (Faraday cup electrometer), its
Being that one kind is metal is designed to cup-shaped, for measuring a kind of vacuum detector of charged particle beam incident intensity and stability,
The electric current measured can for judge charged particle beam quantity.After charged particle beam enters Faraday cup, electricity can be produced
Stream.For a continuous singularly charged charged particle beam：Calculated using formula one, wherein, N is number of charged particles
Amount, t are that time (unit is the second), I are that electric current (unit is ampere), the e measured is elementary charge (about 1.60 × 10-19Coulomb).
We can be evaluated whether, if it is 10 to measure electric current-9A (1nA), that is, there are about 6,000,000,000 charged particles and collected by Faraday cup.
Certainly, those skilled in the art know ground, and the first current sensing means 100 can be suitable in accelerator to be arbitrary
It is used for measuring the detection means of charged particle beam incident intensity and stability, such as wall current detector (Wall at vacuum tube
Current Monitor) and beam transformer (Beam Current Transformer).
Sample resistance is connected across ceramic distance piece two ends by so-called wall current detector, and line image current flows through sampling electricity
Voltage sampling signal can be obtained during resistance, is calculated using formula two, wherein, V is the magnitude of voltage detected, IbFor charged particle
Beam electronic current, Z can be equivalent to resistance under specific frequency, and wall current detector equivalent circuit is Parallel RLC Circuit, such as formula
Three.Therefore electric current of the charged particle beam in certain time period t can be just extrapolated according to the magnitude of voltage detected.
V=-Ib(t) Z (formula two)
So-called beam transformer is to go out current signal using two grades of winding coupleds on magnetic core, can be obtained by analyzing this signal
Obtain the electric current of original charged particle beam.It includes alternating current transformer, and (AC Current Transformer, are abbreviated as
ACCT), fast current transformer (Fast Current Transformer, be abbreviated as FCT), resonant mode current transformer
(Tuned Current Transformer, be abbreviated as TCT), integration current transformer (Integrated Current
Transformer, is abbreviated as ICT) and DC current transformer (DC Current Transformer, be abbreviated as DCCT).By
It is more in species, do not enumerated below with beam transformer, be only used for illustrating with DCCT.DCCT is modulated using nonlinear magnetism
Component is detected the second harmonic of DC signal modulations to pumping signal to be measured.
In the present embodiment, the second current sensing means 200 is galvanometer (galvanometer), during its one end is electrically connected to
Sub- generating unit T, other end ground connection, to form a measure loop, so as to learn in charged particle beam P incident neutron generating units T
During electric current on neutron generating unit T.Galvanometer is the principle deflected according to current-carrying coil in magnetic field by torque
It is made.Ordinary electric meter coil is placed on bearing, and balance is maintained with spring hairspring, and deflection is indicated with pointer.By
There is friction in bearing, tested electric current can not be too weak.Galvanometer replaces bearing suspension in magnetic field using superfine metal suspension, by
Carefully grown in suspension, revolt torque very little, so there is very weak electric current to be just enough to make it produce significant deflection by coil.Cause
And galvanometer is sensitively more than general ammeter, micro-current (10 can be measured-7-10-10) or micro voltage (10 A-3-10- 6V), such as photoelectric current, physiology electric current, thermoelectromotive force.First record nerve action potential, is realized with this quasi-instrument.
Certainly, those skilled in the art know ground, and the second current sensing means 200 can be suitable in neighbouring to be arbitrary
Sub- generating unit is used for detecting the intensity of the charged particle beam through acting on neutron generating unit and the detection means of changing condition, such as electricity
Flow table and voltage meter etc..
In the present embodiment, temperature-detecting device 300 is thermocouple (thermocouple), the conductor of two kinds of different components
(being referred to as thermocouple silk material or thermode) two ends are bonded into loop, when the temperature at abutment is different, will produce in the loop
Electromotive force, this phenomenon is referred to as pyroelectric effect, and this electromotive force is referred to as thermoelectrical potential.Thermocouple is exactly to be carried out using this principle
Temperature survey, wherein, the one end for being directly used as measuring medium temperature is called working end (also referred to as measurement end), and the other end is called
Cold end (also referred to as compensating end)；Cold end is connected with display instrument or matching instrument, and display instrument would indicate that produced by thermocouple
Thermoelectrical potential.
Certainly, those skilled in the art know ground, and temperature-detecting device 300 can be suitable to be arranged on cooling dress to be arbitrary
During being used in putting or at neighbouring cooling device detects cooling device temperature so as to learn that cooling device is produced with neutron generating unit
The detection means of beamlet situation, such as resistance thermometer, it varies with temperature the temperature made by the material of characteristic using known resistance
Sensor is spent, the rule changed with temperature according to conductor resistance is come measurement temperature.
The common neutron beam monitoring device that can be achieved to detect in real time has ionisation chamber and first two difference detection of flash detection former
Reason.Ionization cell structure is wherein used to have He-3 proportional counters, BF for substrate3Proportional counter, division Ionization chamber, boron ionization
Room, and flash detection head can then be divided into organic and inorganic material, for detection thermal neutron purposes, added its flash detection head more
The high thermal neutron capture cross section element such as Li or B.In brief, the neutron energy of such detection device detection is generally thermal neutron, is all
Lean on element and occur capture or the disengaged heavy burden charged particle of nuclear fission reaction and nuclear fission fragment with neutron, in ionisation chamber or sudden strain of a muscle
Produce and largely ionize to (ion pair) in bright detecting head,, just can be by by appropriate circuit conversion after these electric charges are collected
Current signal switchs to voltage pulse signal.Through the size of analysis voltage pulse, then can tell easily neutron signal and
γ signals.In high intensity neutron field, such as BNCT then can suitably reduce the gas pressure of ionisation chamber, can split material or boron painting
The concentration of high neutron capture cross section element in the concentration or flash detection head of cloth, just can effectively reduce it to the sensitive of neutron
Degree, it is to avoid the situation of signal saturation occurs.
As it is further preferred that the first neutron beam monitoring device 400 for division Ionization chamber (fission chamber), when
By dividing during Ionization chamber with division Ionization chamber internal gas molecule or the wall portion for dividing Ionization chamber free make occurs for neutron beam
With, generation electronics and positively charged example, this electronics and positive charge ion are referred to as above-mentioned ion pair.Due to division Ionization chamber
Inside there is extra electric field high pressure, therefore electronics is mobile towards central anode silk, positive charge ion is moved towards the cathode wall of surrounding, thus production
Raw detectable electronic pulse signal.Make gas molecule produce an ion pair needed for energy be referred to as averagely dissociating can, the value according to
Gaseous species and it is different, the average free of such as air can be about 34eV.If there is 340keV neutron beam, air can be made to produce about 10k
Individual ion pair.
Certainly, those skilled in the art know ground, and the first neutron beam monitoring device 400 can be suitable to be embedded in be arbitrary
Being used in beam-shaping body detects the Strength Changes and the detection means of spatial distribution of the neutron beam in beam-shaping body, such as
He-3 proportional counters, BF3Proportional counter, boron chamber and flash detection are first-class.
As it is further preferred that the second neutron beam monitoring device 500 is flash detection head (scintillator
Detector), Cucumber can release visible ray after absorbing energy, and such a material is referred to as scitillating material.It is using free
Radiation is penetrated the electron excitation in crystal or molecule is collected to sharp state, and the fluorescence released when electronics returns to ground state after be used for make
Neutron beam is monitored.The visible ray that flash detection head is launched after being acted on neutron beam, using photomultiplier it will be seen that light turns
Electronics, then amplification of doubling are turned to, usual electron multiplication magnifying power is up to 107 to 108.In the electron number and incidence of anode output
Beamlet energy is directly proportional, therefore flash detection head can measure the energy of neutron beam.
Certainly, those skilled in the art know ground, and the second neutron beam monitoring device 500 can be suitable to be placed in penetrate to be arbitrary
The Strength Changes for being used for detecting the neutron beam in beam exit in beam outlet or neighbouring beam exit and spatial distribution
Detection means, such as He-3 proportional counters, BF3Proportional counter, boron chamber and division Ionization chamber etc..
As it is further preferred that displacement detector 600 is infrared detector, infrared detector is by detection human body
The infrared ray of transmitting is operated.Detector is collected extraneous infra-red radiation and then gathered on infrared sensor.It is infrared
Sensor generally uses pyroelectricity element, and this element will outwards discharge electricity have received when infrared radiation temperature sends change
Alarm is produced after lotus, detection process.This detector is to detect human body radiation as target.So radio-sensitive element is to ripple
A length of 10 μm or so of infra-red radiation must be very sensitive.
Certainly, those skilled in the art know ground, and displacement detector 600 can be waited to shine to be arbitrary suitable for being used for detecting
The detection means of displacement body change, such as displacement transducer.So-called displacement transducer is according to position of the body phase to be shone to a certain object of reference
Change is moved to determine whether body to be shone moves.Also knownly, displacement detector not only can be for inspection by those skilled in the art
The change in displacement of body to be shone is surveyed, can also be used to the change of the displacements such as the support member and/or instrument table of the fixed body to be shone of detection, from
And the change in displacement of body to be shone is learnt indirectly.
Those skilled in the art know ground, the first current sensing means, the second current sensing means, temperature-detecting device,
The number and detecting element of first neutron beam monitoring device, the second neutron beam monitoring device and displacement detector are not limited,
Number and detecting element in the present embodiment are intended only as a kind of citing.
According to the functional relation of the testing result of detection and/or monitoring device each other, can apparently it enumerate
Out of order part, is set forth below out the fault diagnosis situation that the corresponding testing result of several bases is made.
When detecting the first current sensing means 100, the second current sensing means 200, temperature-detecting device 300, first
Any one detection or monitoring device in the neutron beam monitoring device 500 of neutron beam monitoring device 400 and second occur it is abnormal and
When other detections or normal monitoring device, then the abnormal detection or monitoring device faults itself are inferred；When detecting displacement
Detection means 600 occur exception and other detections or monitoring device it is normal in the case of, then infer the displacement of body 50 generation shine
Change or the failure of displacement detector 600.
When detecting the first current sensing means 100, the second current sensing means 200, temperature-detecting device 300, first
When the neutron beam monitoring device 500 of neutron beam monitoring device 400 and second occurs abnormal, then the failure of accelerator 10 is inferred.
When detecting the second current sensing means 200, temperature-detecting device 300, the first neutron beam monitoring device 400 and
When abnormal and the first current sensing means 100 and normal displacement detector 600 occur for two neutron beam monitoring devices 500,
Then infer and expand the failure of device 20.
When detecting temperature-detecting device 300, the first neutron beam monitoring device 400 and the second neutron beam monitoring device 500
When occurring abnormal and the first current sensing means 100, the second current sensing means 200 and normal displacement detector 600,
Then infer neutron generating unit T and/or the failure of cooling device 60.
When detect the first neutron beam monitoring device 400 and the second neutron beam monitoring device 500 occur it is abnormal and first
When current sensing means 100, the second current sensing means 200, temperature-detecting device 300 and normal displacement detector 600,
Then infer the failure of beam-shaping body 30.
When any one monitoring detected in the first neutron beam monitoring component 401 and second neutron beam monitoring component 402 is tied
Any one monitoring component in fruit exception and/or the 3rd neutron beam monitoring component 501 and the 4th neutron beam monitoring component 502 is different
Often, then infer that the uniformity of abnormal neutron beam detection means faults itself or neutron beam is abnormal.
Certainly, those skilled in the art know ground, and the above-described fault diagnosis situation made according to testing result is only
The several frequently seen situation included, have many kinds permutation and combination, still can more than by way of go to judge in which
There is which failure in son capture treatment system or detection means itself.Though here, do not enumerate, according to such essence
The change that god makes, still falls within the content of the invention of the present invention.
Beam diagnostic system includes the control device 700 with control unit 710, and control unit 710 is according to beam diagnostic system
Testing result the signal of human perception is sent to confirm the next step operation of neutron capture treatment system.This human perception
Signal can be the signal that the mankind such as the sense of hearing, vision, tactile or smell Functional tissue can be perceived, and such as send the alarm of the sound
Device, alarm lamp, one or more forms in multi-signal such as vibrate, give out a pungent smell.As one kind preferably, control
Device 700 also includes display part 720, and display part 720 is used for making by the testing result of detection means and/or according to testing result
Fault diagnosis situation be shown on display device, display device can set for the common display such as TV or liquid crystal display
It is standby.By the feedback of control device, operating personnel can easily conclude trouble unit, so that shoots the arrow at the target catches to neutron
Obtain treatment system and/or beam diagnostic system carries out upkeep operation.
It is mark with numeral 400 ' there is disclosed another embodiment of the first neutron beam monitoring device with further reference to Fig. 5
Note, it is illustrated that in Fig. 3 identicals device/component, still using identical Digital ID, and for the ease of display, eliminate
Cooling device and other detection/monitoring devices.
First neutron beam monitoring device 400 ' can include one or more neutron beam and monitor component, and it can set
Put and detected in a straightforward manner in this at beam-shaping body 30 with detecting the neutron beam overflowed through neutron generating unit T
The Strength Changes and spatial distribution of beamlet, can also be positioned adjacent to beam-shaping body 30 sentence detection through charged particle beam P with
The gamma-rays generated after neutron generating unit T effects, can also indirect detection according to the functional relation between gamma-rays and neutron beam
The Strength Changes and spatial distribution of neutron beam.Control device 700 ' includes control unit 710 ' and display part 720 '.Display part 720 '
Display device is shown in for the fault diagnosis situation made by the testing result of detection means 400 ' and/or according to testing result
On, display device can be the common display devices such as TV or liquid crystal display.By the feedback of control device, operating personnel
Trouble unit can easily be concluded, so that shoots the arrow at the target carries out next step operation to accelerator 10.
With further reference to Fig. 6, it is penetrated for the γ for being used to send out in wink after detection is irradiated through neutron beam in beam diagnostic system
The floor map of the radiation detecting system of line, (the gamma-rays inspection that wink is sent out after being irradiated through neutron beam of radiation line detector
Survey device) with numeral 800 for mark, it is illustrated that in Fig. 3 identicals device/component, still using identical Digital ID, and
For the ease of display, cooling device and other detection/monitoring devices are eliminated.
Gamma-ray testing apparatus 800 can include one or more gamma-rays detection means, and it is gamma-ray to detect
Ionization chamber or flash detection head.Gamma-rays is the gamma-rays for occurring to send out in wink after the reaction of boron neutron capture after irradiating through neutron beam.When
Know that the interval γ of the preset energy of measurement counts (0.48MeV that boron neutron capture is produced when reacting is intended only as citing), just
Boron concentration value can be extrapolated according to the functional relation between gamma-rays and boron concentration.Control device 700 " includes control unit
710 " and display part 720 ".Display part 720 " is used for what is made by the testing result of detection means 800 and/or according to testing result
Fault diagnosis situation is shown on display device, and display device can be the common display devices such as TV or liquid crystal display.
By the feedback of control device, operating personnel can easily conclude trouble unit, thus shoot the arrow at the target to accelerator 10
Carry out next step operation.
So-called " gamma-rays that wink is sent out after being irradiated through neutron beam " refers to that with other elements neutron capture core occurs for neutron beam
The gamma-rays produced during reaction, other elements are not limited to the element of boron -10, and neutron capture occurs as known in the art for other elements
Gamma-ray element can be produced during nuclear reaction also central in this definition.In the embodiment of the present invention, " wink is sent out after being irradiated through neutron beam
Gamma-rays " is that with the element of boron -10 gamma-rays produced when boron neutron capture reacts occurs for neutron beam.
As one kind preferably, the boron concentration value is calculated using formula A and drawn：
Wherein, boron concentration value when B (t) is time t, unit is ppm, and time t unit is s, and k is tested definite value, GC
(t) the γ countings that the interval γ tales of preset energy subtract background presence are detected when for time t；The k is pushed away using formula B
Draw：
Wherein, B (t0) it is time t0When boron concentration value, unit is ppm, time t0Unit be s, GC (t0) it is time t0
When detect the interval γ tales of preset energy and subtract the γ of background presence and count, the B (t0) calculated using formula C
Go out：
B(t0)=BBlood(t0)×RT/N(formula C)
Wherein, BBlood(t0) it is time t0When the blood that calculates of meter in boron concentration value, unit is ppm；RT/NAccording to
The ratio of the boron concentration in boron concentration and normal structure in the tumour that PET or experimental data or theoretical foundation can be known.
In order to accurately judge which detection means or monitoring device break down, when following detected value and standard value hair
During raw larger difference, it may be said that bright corresponding detection means or monitoring device there occurs exception.
Tumor dose rate D during time tT(t) calculated and drawn using formula D：
DT(t)=DB(t)+Dn(t)+Dγ(t) (formula D)
Wherein, DT(t) unit is w-Gy/s；DB(t) boron close rate when for time t, unit is w-Gy/s；Dn(t) it is
Neutron dose rate during time t, unit is w-Gy/s；Dγ(t) photon doses rate when for time t, unit is w-Gy/s, described
DB(t) calculated and drawn using formula E：
The Dn(t) calculated and drawn using formula F：
The Dγ(t) calculated and drawn using formula G：
Wherein, DB,ref、Dn,ref、Dγ,nbcap,refAnd Dγ,bcap,refBoron close rate is given respectively in treatment planning systems
The light that reference value or given reference value by correction, the given reference value of neutron dose rate, the reaction of non-boron neutron capture are produced
The given reference value for the photon doses rate that given reference value and boron the neutron capture reaction of sub- close rate are produced, unit is w-
Gy/s；Sn(t) reading of the neutron beam intensity of neutron monitoring device when for time t, unit is examined for counting or by radiation
Survey the selectable reading of device；Sn,refPenetrated for the set-point of neutron beam intensity in treatment planning systems or by the neutron of correction
The set-point of beam intensity；BBlood(t) it is the boron concentration value in the blood sample sample of measurement in t, unit is ppm；BBlood, refFor treatment
The set-point of boron concentration or the set-point for the boron concentration for passing through correction in planning system, unit is ppm；f(BBlood(t),BBlood, ref) be
A set of function for drawing is precalculated by treatment plan to correct the non-linear relation between boron concentration and tumor dose.
Preferably, tumor dose rate during time t can also be calculated by following formula H：
Wherein, SB(t) reading of radiation line detector when for time t, unit detects dress for counting or by radiation
Put selectable reading, SB(t) extrapolated by following formula I；C is to calculate an obtained calculated value by formula J：
Wherein, NNB,refFor the reference value of the number of times that the reaction of boron neutron capture occurs in treatment plan；kBGTo be repaiied to background
Just；σ is the detection efficiency of radiation line detector；Sn(t0) it is time t0When neutron monitoring device neutron beam intensity
Reading, unit is for counting or by the selectable reading of radiation line detector；BBlood(t0) for measurement blood sample sample in t0When
Boron concentration value, unit is ppm；f(BBlood(t0),BBlood, ref) dense to correct boron to precalculate a set of function for drawing by treatment plan
Non-linear relation between degree and tumor dose；SB(t0) be the radiation line detector set initial stage in irradiation reading, it is single
Position is for counting or by the selectable reading of radiation line detector.
As shown in fig. 7, it illustrates the boron concentration B in the present embodimentBlood(t) with tumor dose BTumour(t) function between is closed
System's figure.As one kind preferably, it is 1.7 × 10 to penetrate source strength in neutron11On the basis of n/s, calculate that boron is dense using equation below K
Non-linear relation between degree and tumor dose, so as to can effectively correct boron concentration in this neutron capture treatment system with swelling
Non-linear relation between knurl dosage, improves the accuracy for the treatment of plan.
BTumour(t)=0.01643+0.8034 × BBlood(t)-0.00167×BBlood(t)2-2.42362×10-5×BBlood(t)3
(formula K)
It is well known to those skilled in the art, the boron concentration B shown in Fig. 7Blood(t) with tumor dose BTumour(t) function between is closed
System is not limited to the mode that formula K is represented, based on experience value, draws up this boron concentration BBlood(t) with tumor dose BTumour(t) between
Nonlinear function.Boron concentration B shown in Fig. 7Blood(t) with tumor dose BTumour(t) functional relation between is also not necessarily limited to
It is 1.7 × 10 to penetrate source strength in neutron11It is derived from the basis of n/s, rule of thumb, penetrating source strength based on different neutrons has
Different functional relations may be drawn.Neutron capture treatment system in the embodiment of the present invention can correct boron concentration and tumour agent
Nonlinear function between amount, to improve the accuracy for the treatment of plan.
It should be noted that neutron monitoring device and radiation line detector all should carry out the correction of hesitation.
The other side of the embodiment of the present invention is to provide a kind of neutron beam irradiation for improving neutron capture treatment system
The accuracy of dosage and the radiation line detecting method for neutron capture treatment system that can find trouble location in time, should
Radiate line detecting method and above-mentioned radiation detecting system is mutually corresponding.
To sum up, no matter the first neutron beam monitoring device is arranged in beam-shaping body, still it is positioned adjacent to beam
At shaping body, as long as can be used for detecting Strength Changes and the space of the neutron beam in beam-shaping body in place of set seated position
The detection means of distribution can then be selected.
What the present invention was disclosed detects for the radiation detecting system of neutron capture treatment system and its corresponding radiation
Method is not limited to the structure represented by content and accompanying drawing described in above example.To wherein on the basis of the present invention
Apparently change, replacement or modification that material, shape and the position of component are made, all in claimed model
Within enclosing.
Claims (10)
1. a kind of radiation detecting system for neutron capture treatment system, it is characterised in that：The neutron capture treatment system
System includes charged particle beam, for the charged particle beam entrance by the charged particle beam, through being sent out with the charged particle beam
Raw nuclear reaction is so as to produce the neutron generating unit of neutron beam, for adjusting the neutron beam flux produced through the neutron generating unit
Exported with the beam-shaping body of quality and the beam for being adjacent to the beam-shaping body, wherein, the radiation detecting system bag
Radiation line detector is included, the radiation line detector is used for the gamma-rays sent out in wink after detection is irradiated through neutron beam in real time.
2. the radiation detecting system according to claim 1 for neutron capture treatment system, it is characterised in that：It is described
Radiation detecting system further comprises control device, and the control device is according to the testing result for radiating line detector
The signal of human perception is sent to confirm the next step operation of the neutron capture treatment system；The control device includes control
Portion and display part, the control unit testing result of the radiation detecting system is shown by the display part and
Testing result is fed back into the accelerator to confirm the next step operation of the accelerator.
3. the radiation detecting system according to claim 1 or 2 for neutron capture treatment system, it is characterised in that：
The radiation line detector is detects gamma-ray Ionization chamber or flash detection head, and the radiation detecting system passes through detection
To γ signals extrapolate boron concentration value.
4. the radiation detecting system according to claim 3 for neutron capture treatment system, it is characterised in that：It is described
Boron concentration value is calculated using formula A and drawn：
Wherein, boron concentration value when B (t) is time t, unit is ppm, and time t unit is s, and k is tested definite value, and GC (t) is
The γ countings that the interval γ tales of preset energy subtract background presence are detected during time t；The k is calculated using formula B
Go out：
Wherein, B (t0) it is time t0When boron concentration value, unit is ppm, time t0Unit be s, GC (t0) it is time t0Shi Jian
Measure the γ countings that the interval γ tales of preset energy subtract background presence, the B (t0) drawn using formula C reckonings：
B(t0)=BBlood(t0)×RT/N(formula C)
Wherein, BBlood(t0) it is time t0When the blood that calculates of meter in boron concentration value, unit is ppm；RT/NFor according to PET or
The ratio of the boron concentration in boron concentration and normal structure in the tumour that experimental data or theoretical foundation can be known.
5. the radiation detecting system according to claim 4 for neutron capture treatment system, it is characterised in that：Time
Tumor dose rate D during tT(t) calculated and drawn using formula D：
DT(t)=DB(t)+Dn(t)+Dγ(t) (formula D)
Wherein, DT(t) unit is w-Gy/s；DB(t) boron close rate when for time t, unit is w-Gy/s；Dn(t) it is the time
Neutron dose rate during t, unit is w-Gy/s；Dγ(t) photon doses rate when for time t, unit is w-Gy/s, the DB
(t) calculated and drawn using formula E：
The Dn(t) calculated and drawn using formula F：
The Dγ(t) calculated and drawn using formula G：
Wherein, DB,ref、Dn,ref、Dγ,nbcap,refAnd Dγ,bcap,refThe given reference of boron close rate respectively in treatment planning systems
Value or the given reference value by correction, the given reference value of neutron dose rate, the photon agent of non-boron neutron capture reaction generation
The given reference value for the photon doses rate that given reference value and boron the neutron capture reaction of dose rate are produced, unit is w-Gy/s；
Sn(t) reading of the neutron beam intensity of neutron monitoring device when for time t, unit is for counting or by radiation line detector
Selectable reading；Sn,refFor the set-point of neutron beam intensity in treatment planning systems or the neutron beam intensity for passing through correction
Set-point；BBlood(t) it is the boron concentration value in the blood sample sample of measurement in t, unit is ppm；BBlood, refFor treatment planning systems
The set-point of the set-point of middle boron concentration or the boron concentration for passing through correction, unit is ppm；f(BBlood(t),BBlood, ref) it is to be counted by treatment
Draw and precalculate a set of function for drawing to correct the non-linear relation between boron concentration and tumor dose.
6. a kind of radiation line detecting method for neutron capture treatment system, it is characterised in that：The neutron capture treatment system
System includes charged particle beam, for the charged particle beam entrance by the charged particle beam, through being sent out with the charged particle beam
Raw nuclear reaction is so as to produce the neutron generating unit of neutron beam, for adjusting the neutron beam flux produced through the neutron generating unit
Exported with the beam-shaping body of quality and the beam for being adjacent to the beam-shaping body, wherein, the neutron generating unit is contained in
In the beam-shaping body；Radiation detecting system includes radiation line detector, and the detection method includes detecting step, institute
Stating detecting step includes detecting the gamma-rays sent out in wink after the neutron beam irradiation in real time by the radiation line detector.
7. the radiation line detecting method according to claim 6 for neutron capture treatment system, it is characterised in that：It is described
Radiation detecting system further comprises control device, and the control device includes control unit and display part, the detection method
Including rate-determining steps, the rate-determining steps control the neutron capture by testing result of the control unit in the detecting step
The next step operation for the treatment of system；The detection method also includes step display, and the step display will be in the detecting step
In testing result shown via the display part.
8. the radiation line detecting method for neutron capture treatment system according to claim 6 or 7, it is characterised in that：
The detection method includes calculating step, and it is dense that the reckoning step extrapolates boron according to the testing result in the detecting step
Angle value.
9. the radiation line detecting method according to claim 8 for neutron capture treatment system, it is characterised in that：It is described
Boron concentration value is calculated using formula A and drawn：
Wherein, boron concentration value when B (t) is time t, unit is ppm, and time t unit is s, and k is tested definite value, and GC (t) is
The γ countings that the interval γ tales of preset energy subtract background presence are detected during time t；The k is calculated using formula B
Go out：
Wherein, B (t0) it is time t0When boron concentration value, unit is ppm, time t0Unit be s, GC (t0) it is time t0Shi Jian
Measure the γ countings that the interval γ tales of preset energy subtract background presence, the B (t0) drawn using formula C reckonings：
B(t0)=BBlood(t0)×RT/N(formula C)
Wherein, BBlood(t0) it is time t0When the blood that calculates of meter in boron concentration value, unit is ppm；RT/NFor according to PET or
The ratio of the boron concentration in boron concentration and normal structure in the tumour that experimental data or theoretical foundation can be known.
10. the radiation line detecting method according to claim 9 for neutron capture treatment system, it is characterised in that：When
Between t when tumor dose rate DT(t) calculated and drawn using formula D：
DT(t)=DB(t)+Dn(t)+Dγ(t) (formula D)
Wherein, DT(t) unit is w-Gy/s；DB(t) boron close rate when for time t, unit is w-Gy/s；Dn(t) it is the time
Neutron dose rate during t, unit is w-Gy/s；Dγ(t) photon doses rate when for time t, unit is w-Gy/s, the DB
(t) calculated and drawn using formula E：
The Dn(t) calculated and drawn using formula F：
The Dγ(t) calculated and drawn using formula G：
Wherein, DB,ref、Dn,ref、Dγ,nbcap,refAnd Dγ,bcap,refThe given reference of boron close rate respectively in treatment planning systems
Value or the given reference value by correction, the given reference value of neutron dose rate, the photon agent of non-boron neutron capture reaction generation
The given reference value for the photon doses rate that given reference value and boron the neutron capture reaction of dose rate are produced, unit is w-Gy/s；
Sn(t) reading of the neutron beam intensity of neutron monitoring device when for time t, unit is for counting or by radiation line detector
Selectable reading；Sn,refFor the set-point of neutron beam intensity in treatment planning systems or the neutron beam intensity for passing through correction
Set-point；BBlood(t) it is the boron concentration value in the blood sample sample of measurement in t, unit is ppm；BBlood, refFor treatment planning systems
The set-point of the set-point of middle boron concentration or the boron concentration for passing through correction, unit is ppm；f(BBlood(t),BBlood, ref) it is to be counted by treatment
Draw and precalculate a set of function for drawing to correct the non-linear relation between boron concentration and tumor dose.
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