CN108295385A - Neutron capture therapeutic device - Google Patents
Neutron capture therapeutic device Download PDFInfo
- Publication number
- CN108295385A CN108295385A CN201710017520.7A CN201710017520A CN108295385A CN 108295385 A CN108295385 A CN 108295385A CN 201710017520 A CN201710017520 A CN 201710017520A CN 108295385 A CN108295385 A CN 108295385A
- Authority
- CN
- China
- Prior art keywords
- neutron
- flexible shielding
- therapeutic device
- neutron capture
- shielding body
- 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.)
- Granted
Links
- 230000001225 therapeutic effect Effects 0.000 title claims abstract description 46
- 238000002560 therapeutic procedure Methods 0.000 claims abstract description 15
- 238000002139 neutron reflectometry Methods 0.000 claims abstract description 4
- 238000011282 treatment Methods 0.000 claims description 31
- 230000005855 radiation Effects 0.000 claims description 19
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims description 17
- 229910052796 boron Inorganic materials 0.000 claims description 17
- 239000000463 material Substances 0.000 claims description 15
- 239000000203 mixture Substances 0.000 claims description 10
- 239000006096 absorbing agent Substances 0.000 claims description 8
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 5
- 239000000741 silica gel Substances 0.000 claims description 5
- 229910002027 silica gel Inorganic materials 0.000 claims description 5
- 230000009471 action Effects 0.000 claims description 4
- 239000012188 paraffin wax Substances 0.000 claims description 2
- VGGSQFUCUMXWEO-UHFFFAOYSA-N Ethene Chemical compound C=C VGGSQFUCUMXWEO-UHFFFAOYSA-N 0.000 claims 1
- 239000005977 Ethylene Substances 0.000 claims 1
- 230000003760 hair shine Effects 0.000 claims 1
- 230000005251 gamma ray Effects 0.000 abstract description 9
- 230000006378 damage Effects 0.000 abstract description 7
- 208000027418 Wounds and injury Diseases 0.000 abstract description 4
- 208000014674 injury Diseases 0.000 abstract description 4
- 206010028980 Neoplasm Diseases 0.000 description 23
- 230000004907 flux Effects 0.000 description 20
- 238000006243 chemical reaction Methods 0.000 description 18
- 238000001514 detection method Methods 0.000 description 12
- 230000000694 effects Effects 0.000 description 12
- 239000002245 particle Substances 0.000 description 8
- 238000007493 shaping process Methods 0.000 description 7
- 238000011109 contamination Methods 0.000 description 6
- 239000003814 drug Substances 0.000 description 6
- 230000002285 radioactive effect Effects 0.000 description 6
- 201000011510 cancer Diseases 0.000 description 5
- 229940079593 drug Drugs 0.000 description 5
- 210000004881 tumor cell Anatomy 0.000 description 5
- 230000004071 biological effect Effects 0.000 description 4
- 238000013461 design Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 229910052744 lithium Inorganic materials 0.000 description 4
- 230000002105 relative biological effectiveness Effects 0.000 description 4
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 3
- 230000008901 benefit Effects 0.000 description 3
- 229910052802 copper Inorganic materials 0.000 description 3
- 239000010949 copper Substances 0.000 description 3
- 230000008021 deposition Effects 0.000 description 3
- 238000011161 development Methods 0.000 description 3
- 239000011133 lead Substances 0.000 description 3
- 210000004027 cell Anatomy 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 238000002512 chemotherapy Methods 0.000 description 2
- 230000008030 elimination Effects 0.000 description 2
- 238000003379 elimination reaction Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000007769 metal material Substances 0.000 description 2
- 238000001959 radiotherapy Methods 0.000 description 2
- 230000010415 tropism Effects 0.000 description 2
- CVOFKRWYWCSDMA-UHFFFAOYSA-N 2-chloro-n-(2,6-diethylphenyl)-n-(methoxymethyl)acetamide;2,6-dinitro-n,n-dipropyl-4-(trifluoromethyl)aniline Chemical compound CCC1=CC=CC(CC)=C1N(COC)C(=O)CCl.CCCN(CCC)C1=C([N+]([O-])=O)C=C(C(F)(F)F)C=C1[N+]([O-])=O CVOFKRWYWCSDMA-UHFFFAOYSA-N 0.000 description 1
- 241000208340 Araliaceae Species 0.000 description 1
- 208000003174 Brain Neoplasms Diseases 0.000 description 1
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 description 1
- 201000010915 Glioblastoma multiforme Diseases 0.000 description 1
- 206010053159 Organ failure Diseases 0.000 description 1
- 235000005035 Panax pseudoginseng ssp. pseudoginseng Nutrition 0.000 description 1
- 235000003140 Panax quinquefolius Nutrition 0.000 description 1
- 239000004698 Polyethylene Substances 0.000 description 1
- 208000019155 Radiation injury Diseases 0.000 description 1
- 239000004809 Teflon Substances 0.000 description 1
- 229920006362 Teflon® Polymers 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000001133 acceleration Effects 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 1
- 239000008280 blood Substances 0.000 description 1
- 210000004369 blood Anatomy 0.000 description 1
- 230000037396 body weight Effects 0.000 description 1
- 210000004556 brain Anatomy 0.000 description 1
- 230000030833 cell death Effects 0.000 description 1
- 230000002490 cerebral effect Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 210000002249 digestive system Anatomy 0.000 description 1
- 201000010099 disease Diseases 0.000 description 1
- 208000037265 diseases, disorders, signs and symptoms Diseases 0.000 description 1
- 238000010894 electron beam technology Methods 0.000 description 1
- 235000008434 ginseng Nutrition 0.000 description 1
- 210000002165 glioblast Anatomy 0.000 description 1
- 208000005017 glioblastoma Diseases 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 239000004615 ingredient Substances 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 229910052745 lead Inorganic materials 0.000 description 1
- 201000001441 melanoma Diseases 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 210000000653 nervous system Anatomy 0.000 description 1
- 150000007523 nucleic acids Chemical class 0.000 description 1
- 102000039446 nucleic acids Human genes 0.000 description 1
- 108020004707 nucleic acids Proteins 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- -1 polyethylene Polymers 0.000 description 1
- 229920000573 polyethylene Polymers 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 230000000644 propagated effect Effects 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000013077 target material Substances 0.000 description 1
- 238000002626 targeted therapy Methods 0.000 description 1
- 230000008685 targeting Effects 0.000 description 1
- 238000011287 therapeutic dose Methods 0.000 description 1
Classifications
-
- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/1001—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy using radiation sources introduced into or applied onto the body; brachytherapy
-
- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61K—PREPARATIONS FOR MEDICAL, DENTAL OR TOILETRY PURPOSES
- A61K41/00—Medicinal preparations obtained by treating materials with wave energy or particle radiation ; Therapies using these preparations
- A61K41/009—Neutron capture therapy, e.g. using uranium or non-boron material
- A61K41/0095—Boron neutron capture therapy, i.e. BNCT, e.g. using boronated porphyrins
-
- 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
- A61N5/1001—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy using radiation sources introduced into or applied onto the body; brachytherapy
- A61N5/1007—Arrangements or means for the introduction of sources into the body
-
- 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
-
- 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
- A61N5/1077—Beam delivery 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
- A61N5/1001—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy using radiation sources introduced into or applied onto the body; brachytherapy
- A61N2005/1019—Sources therefor
-
- 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
-
- 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
- A61N2005/1092—Details
-
- 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
- A61N2005/1092—Details
- A61N2005/1094—Shielding, protecting against radiation
Landscapes
- Health & Medical Sciences (AREA)
- Engineering & Computer Science (AREA)
- Biomedical Technology (AREA)
- General Health & Medical Sciences (AREA)
- Veterinary Medicine (AREA)
- Public Health (AREA)
- Life Sciences & Earth Sciences (AREA)
- Animal Behavior & Ethology (AREA)
- Nuclear Medicine, Radiotherapy & Molecular Imaging (AREA)
- Radiology & Medical Imaging (AREA)
- Pathology (AREA)
- Chemical & Material Sciences (AREA)
- Medicinal Chemistry (AREA)
- Pharmacology & Pharmacy (AREA)
- Epidemiology (AREA)
- Radiation-Therapy Devices (AREA)
Abstract
Present invention is disclosed a kind of neutron capture therapeutic devices; the neutron capture therapeutic device includes neutron generating unit, slow body, reflector, beam outlet and flexible shielding body; wherein neutron generating unit is for generating neutron; the neutron beam that the slow body generates neutron generating unit is slowly to epithermal neutron beam; reflector is used to the neutron reflection spread around returning neutron beam; neutron beam is exported by beam and reaches patient, and the patient is protected by flexible shielding body.The present invention reduces patient in the injury brought by the irradiation of extra neutrons dosage and gamma ray in receiving neutron capture therapeutic process by providing such a technical solution.
Description
Technical field
The present invention relates to a kind of radiotherapy apparatus more particularly to a kind of neutron capture therapeutic devices.
Background technology
As the radiation cures such as the development of atomics, such as cobalt 60, linear accelerator, electron beam have become cancer
One of the main means of disease treatment.However conventional photonic or electronic therapy are limited by radioactive ray physical condition itself, are being killed
While dead tumour cell, a large amount 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
Tumor (glioblastoma multiforme), melanocytoma (melanoma)) treatment effect it is often bad.
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 the radiation source of biological effect (relative biological effectiveness, RBE), as proton therapeutic, heavy particle are controlled
Treatment, neutron capture treatment etc..Wherein, neutron capture treatment is to combine above two concept, if boron neutron capture is treated, by
Boracic drug gathers in the specificity of tumour cell, and accurately neutron beam regulates and controls for cooperation, provides more better than conventional radiation
Treatment of cancer selects.
It will produce various radioactive ray in neutron capture therapeutic process, such as gamma-rays and neutron beam, these radioactive ray can be to people
Body causes different degrees of damage, wherein gamma-rays to have extremely strong penetrating power, gamma-rays when human body is irradiated by gamma-rays
Ionization can occur with internal cell, the main component such as albumen for constituting living cell tissue can be destroyed by ionizing the ion of generation
Matter, nucleic acid etc. can seriously lead to cell death；And neutron irradiation can cause blood forming organ failure, damage digestive system and maincenter
Nervous system, neutron irradiation also will produce hereditary effect, influence offspring's development of raying person.Therefore it was treated in neutron capture
These radioactive rays are effectively rationally shielded in journey, protects patient not injured by radioactive ray and is asked as urgently to be resolved hurrily
Topic.
Invention content
It is injured caused by operating personnel or patient to solve the radioactive ray generated in neutron capture therapeutic process, this
Invention provides a kind of neutron capture therapeutic device comprising neutron generating unit, slow body, reflector, beam outlet and flexibility
Shield, wherein the neutron generating unit is for generating neutron, and the neutron forms neutron beam, during neutron beam includes fast
Son；The slow body is adjacent to the neutron generating unit and the fast neutron that generates the neutron generating unit is slowly in superthermal
Son；The reflector surrounds the slow body, and the neutron beam is returned in the neutron reflection for will be spread to surrounding；The beam
Outlet is passed through by the slow neutron beam of the slow body to make and is irradiated to patient；The flexible shielding body is for suffering from
Patient is covered without receiving the position of neutron exposure to shield in therapeutic process during the underway sub- capture treatment of person
Neutron ray, and can be bonded under external force with the profile at the position.
The wherein described flexible shielding body refers to the object that can deform upon and be bonded patient contours under the effect of external force,
The object can be the soft objects that deformation disappears after external force elimination；Or keep the deformation shape after external force elimination
The object of state, the deformation can be eliminated by needing additionally to apply external force again in this state.The flexible shielding body is in neutron
Patient can be bonded under the effect of external force in capture therapeutic process to be not necessarily to by the position of neutron exposure to shield in therapeutic process
Existing various neutron rays, the external force include gravity.
Preferably, in the neutron capture therapeutic device, the neutron capture therapeutic device includes collimator and hankers
Sub- absorber, wherein collimator are adjacent to beam outlet outside, to converge the neutron beam for exporting out from beam；Institute
It stating thermal neutron absorber and is adjacent to the slow body, shallow-layer normal structure being caused when for absorbing thermal neutron to avoid treatment
Multi-dose.
The neutron beam energy that neutron generating unit generates is different, and epithermal neutron is used in therapeutic process, is produced by neutron
The thermal neutron of life portion generation or the thermal neutron slowly to get off through slow body can cause neutron to pollute ambient enviroment, neutron absorption
Body can effectively reduce the content of thermal neutron in neutron beam；Collimator can converge neutron beam, it is made to have better beam product
Matter and therapeutic effect.
Preferably, in the neutron capture therapeutic device, the flexible shielding body is selected from paraffin, lead, polyethylene or contains
The composition of boron, wherein the boron element in the composition of the boracic is10B。
The composition of the boracic preferably comprises silica gel and contains10The composition of the neutron capture material of B element, wherein
Contain10The neutron capture material of B element accounts for the 10%~50% of the boron-containing compositions weight.The flexible shielding body penetrates neutron
The shielding action of line, which is derived mainly from, to be contained10The neutron capture material of B element, especially10B element, therefore contain10The substance of B element contains
Amount is higher, and the flexible shielding body is better to the shielding action of neutron ray, but if contains10The content of material of B element is excessively high,
Corresponding amount of silica gel will reduce, and then the flexibility of the flexible shielding body can also substantially reduce, and influence using effect.
The composition of the boracic is in addition to including silica gel and containing10It, can be according to this field outside the neutron capture material of B element
Knownly suitable curing agent is added in order to make flexible shielding body have certain form in technical staff.
Further, described to contain10The neutron capture material of B element is preferably10BN or10B4C。
It is even furthermore preferable that the thickness of the flexible shielding body is less than or equal to 1cm.In the material for constituting flexible shielding body
Expect and match it is fixed under the premise of, the thickness of flexible shielding body is thicker, better to the shielding line effect of neutron ray, but simultaneously
The flexibility of flexible shielding body is reduced also with the increase of thickness, and it is flexible to influence it in order to avoid the thickness of flexible shielding body is blocked up
And in order to mitigate heavier flexible shielding body sense of discomfort caused by patient, the thickness of the preferred flexible shielding body of the present invention is less than
Equal to 1cm, preferably 0.5cm, 0.7cm and 1cm.
In neutron capture therapeutic process, patient position to be illuminated need the beam as close to collimator to export with
Therapeutic effect is improved, the preferably flexible shielding body distance nearest apart from collimator is less than or equal to 20cm.
It may further be preferable that in the neutron capture therapeutic device, the flexible shielding body has elasticity, is caught in neutron
It obtains in therapeutic process, the flexible shielding body is close to patient contours under the action of elastic force.
Preferably, in the neutron capture therapeutic device, any opening of the flexible shielding body is equipped with tightening
Structure, the tightening structure make flexible shielding body opening be bonded patient contours, to avoid neutron ray from it is described opening and
Gap between patient contours enters and then the normal structure of patient harm.
In the neutron capture therapeutic device, the normal structure of the flexible shielding body covering was treated in neutron capture
The dose of radiation received in journey is less than 18Gy/h.
Flexible shielding body of the present invention over the course for the treatment of will be without by the position covering of neutron exposure for patient
Get up, the flexible shielding body can be cut into the shape of clothes, and can also be other can protect patient not by neutron ray
The shape of injury.
Note：Hanker subzone between 0.5eV to 40keV and be less than 0.5eV, fast-neutron range is more than in epithermal neutron energy area
40keV。
The beneficial effects of the invention are as follows provide a kind of can effectively mitigate neutron ray and cause in additional injury patient
Son capture therapeutic device.
Description of the drawings
Fig. 1 is accelerator formula neutron capture therapeutic device schematic diagram；
Fig. 2 is reactor formula neutron capture therapeutic device schematic diagram；
Fig. 3 is the shield effectiveness schematic diagram for measuring flexible shielding body to neutron ray；
Fig. 4 is the flexible shielding body for being cut into garment shape.
Specific implementation mode
Neutron capture treatment is gradually increased 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 neutron capture therapeutic device can be divided into according to the difference of neutron generating unit in nuclear reactor formula
Son capture therapeutic device or accelerator formula neutron capture therapeutic device.Accelerator boron neutron capture therapeutic device as shown in Figure 1
Accelerator 11a, target T, the beam that basic module is generally included for being accelerated to charged particle (such as proton, deuteron) are whole
Body 30a, collimator 40a and the body 51b to be illuminated wrapped up with flexible shielding body 50, wherein accelerating charged particle P and metallic target
Material T effect generates neutron, according to required neutron yield rate and energy, available acceleration charged particle energy and size of current,
The characteristics such as the materialization of metal targets select suitable nuclear reaction, and the nuclear reaction being often discussed has7Li(p,n)7Be and9Be(p,
n)9B, both reactions are all the endothermic reaction.The energy threshold of two kinds of nuclear reactions is respectively 1.881MeV and 2.055MeV, due to
The ideal neutron source of boron neutron capture treatment is the epithermal neutron of keV energy grades, if being theoretically only slightly taller than valve using energy
The proton bombardment lithium metal target of value can generate the neutron of opposite low energy, and clinic can be used for by being not necessary to too many slow processing, so
And two kinds of targets of lithium metal (Li) and beryllium metal (Be) and the proton-effect section of threshold values energy be not high, for generate it is sufficiently large in
Sub- flux usually selects the proton of higher-energy to cause nuclear reaction.
Ideal target should have high neutron yield rate, the neutron energy of generation is distributed (will be under close to epithermal neutron energy area
Text detailed description), without wear by force too much radiation generate, the characteristics such as cheap easily operated and high temperature resistant of safety, but actually and can not
It finds and meets required nuclear reaction, using target made of lithium metal in the embodiment of the present invention.But art technology
Known to personnel, the material of target can also be made of other metal materials other than the above-mentioned metal material talked about.
Requirement for hot removal system is then different according to the nuclear reaction of selection, such as7Li(p,n)7Be is because of metal targets (lithium
Metal) fusing point and thermal conductivity coefficient it is poor, requirement to hot removal system just compared with9Be(p,n)9B high.It is adopted in the embodiment of the present invention
With7Li(p,n)7The nuclear reaction of Be.
No matter boron neutron capture treatment nuclear reaction of the neutron source from nuclear reactor or accelerator charged particle and target,
What is generated is all mixed radiation field, i.e., beam contains neutron, photon of the low energy to high energy；The boron neutron of deep tumor is caught
Treatment is obtained, other than epithermal neutron, remaining radiation content is more, causes the ratio of the non-selective dosage deposition of normal structure
It is bigger, therefore these can cause the radiation of unnecessary dosage that should reduce as possible.
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 suggestion, this five suggestions can be used for the quality of the different neutron sources of comparison, and be provided with as select neutron generate way
Reference frame when diameter, design beam-shaping body.This five suggestion difference are as follows：
Epithermal neutron beam flux Epithermal neutron flux>1x 109n/cm2s
Fast neutron pollutes Fast neutron contamination<2x 10-13Gy-cm2/n
Photon contamination Photon contamination<2x 10-13Gy-cm2/n
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：Hanker subzone between 0.5eV to 40keV and be less than 0.5eV, fast-neutron range is more than in epithermal neutron energy area
40keV。
1, epithermal neutron beam flux：
Boracic drug concentration has codetermined the clinical treatment time in neutron beam flux and tumour.If tumour boracic drug
The enough height of concentration, the requirement for neutron beam flux can reduce；Conversely, if boracic drug concentration is low in tumour, high pass is needed
Epithermal neutron is measured to give tumour enough dosage.Requirements of the IAEA for epithermal neutron beam flux is per second every square centimeter
Epithermal neutron number be more than 109, the neutron beam under this flux can substantially control treatment for current boracic drug
Time, short treatment time other than advantageous to patient's positioning and comfort level, also can relatively efficiently use boracic medicine in one hour
Object limited residence time within the tumor.
2, fast neutron pollutes：
Since fast neutron can cause unnecessary normal tissue dose, it is regarded as pollution, this dosage size and neutron
Energy is proportionate, therefore should reduce the content of fast neutron to the greatest extent in neutron beam design.Fast neutron pollution definition is unit
The adjoint fast neutron dosage of epithermal neutron flux, IAEA are less than 2x 10 to the suggestion that fast neutron pollutes-13Gy-cm2/n。
3, photon contamination (gamma-ray contamination)：
Gamma-rays belongs to wears radiation by force, can non-selectively cause the organized dosage deposition of institute on course of the beam, therefore
Reduce gamma-rays content be also neutron beam design exclusive requirement, gamma-ray contamination define for unit epithermal neutron flux it is adjoint
Gamma-rays dosage, IAEA are less than 2x 10 to the suggestion of gamma-ray contamination-13Gy-cm2/n。
4, thermal and epithermal neutron flux ratio：
Since thermal neutron decay speed is fast, penetration capacity is poor, into human body after most of energy be deposited on skin histology, remove
The Several Epidermal Tumors such as melanocytoma need to be used outside the neutron source that thermal neutron is treated as boron neutron capture, swollen for deep layers such as brain tumors
Tumor should reduce thermal neutron content.IAEA is less than 0.05 to thermal and epithermal neutron flux ratio suggestion.
5, middle electron current and flux ratio：
Middle electron current represents the directionality of beam with flux ratio, and tropism is good before the bigger expression neutron beam of ratio, high
The neutron beam of preceding tropism can reduce because neutron dissipate caused by normal surrounding tissue dosage, in addition also improve can treat depth and
Put pose gesture elasticity.IAEA centerings electron current is more than 0.7 with flux ratio suggestion.
The dosage in tissue is obtained using prosthese to be distributed, and 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 of different neutron beam treatment benefits.
1, effective therapeutic depth：
Tumor dose is equal to the depth of normal structure maximum dose, the position after this depth, what tumour cell 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 indicate that medicable tumor depth is deeper, unit cm.
2, effective therapeutic depth dosage rate：
That is the tumor dose rate of effective therapeutic depth is also equal to the maximum dose rate of normal structure.Because normal structure receives
Accumulated dose is the factor for influencing to give tumour accumulated dose size, therefore parameter influences the length for the treatment of time, and effectively treatment is deep
Degree dosage rate is bigger, and the irradiation time for indicating to give needed for tumour doses is shorter, unit cGy/mA-min.
3, dose therapeutically effective ratio：
From brain surface to effective therapeutic depth, the mean dose ratio that tumour and normal structure receive, referred to as effectively
Therapeutic dose ratio；The calculating of mean dose can be integrated to obtain by dose versus depth curve.Dose therapeutically effective ratio is bigger, represents
The treatment benefit of the neutron beam is better.
Compare foundation to make beam-shaping body have in design, in addition to five IAEA suggest air in beam quality because
Three plain and above-mentioned parameters also utilize the following ginseng good and bad for assessing the performance of neutron beam dosage in the embodiment of the present invention
Number：
1, irradiation time≤30min (proton current that accelerator uses is 10mA)
2,30.0RBE-Gy can treat depth >=7cm
3, tumour maximum dose >=60.0RBE-Gy
4, normal cerebral tissue's maximum dose≤12.5RBE-Gy
5, skin maximum dose≤11.0RBE-Gy
Note：RBE (Relative Biological Effectiveness) is relative biological effect, due to photon, neutron
Can caused by biological effect it is different, so dosage item as above be respectively multiplied by the relative biological effect of different tissues in the hope of etc.
Imitate dosage.
Neutron capture treatment is gradually increased 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 present invention will be described in further detail below with reference to the accompanying drawings, to enable people in the art
Member can implement according to this with reference to specification word.
It should be appreciated that such as " having ", "comprising" and " comprising " term used herein are not precluded one or more
The presence or addition of a other ingredients or combinations thereof.
The neutron used in neutron capture therapeutic device is generated by neutron generating unit, in the principle difference generated according to neutron
Sub- generating unit is divided into accelerator formula neutron generating unit and reactor formula neutron generating unit, no matter the neutron source of boron neutron capture treatment
Nuclear reaction from nuclear reactor or accelerator charged particle and target, generation is all mixed radiation field, i.e. beam contains
Neutron, photon of the low energy to high energy；Boron neutron capture treatment for deep tumor, other than epithermal neutron, remaining radiation
Line content is more, causes the ratio of the non-selective dosage deposition of normal structure bigger, therefore these can cause unnecessary dosage
Radiation should reduce as possible.
<Embodiment 1>
Accelerator formula neutron capture therapeutic device as shown in Figure 1 includes accelerator formula neutron generating unit 10a, beam-shaping body
30a, collimator 40a and flexible shielding body 50 form, and wherein accelerator formula neutron generating unit 10a includes accelerator 11a and embeds
Body 12a is generated in the neutron of beam-shaping body 30a, wherein neutron, which generates inside body 12a, target T；Accelerator 11a is for accelerating
Charged particle P, charged particle and target T effects generate neutron.Beam-shaping body 30a include reflector 31a, slow body 32a and
Thermal neutron absorber 33a, the neutron that accelerator formula neutron generating unit 10a is generated is since power spectrum is very wide, in addition to epithermal neutron meets
Other than treatment needs, needs to reduce other kinds of neutron content as far as possible and cause to hinder to avoid to operating personnel or patient
Evil, therefore the neutron come out from neutron generating unit 10a is needed fast neutron energy adjusting therein by slow body 32a to superthermal
Neutron energy range, the material of slow body 32a can use contain Al, Mg, Ca, in the compound or Teflon of the elements such as Pb, F
One or more combinations；Reflector 31a surrounds the slow body 32a, and the neutron spread around across slow body 32a is anti-
Neutron beam N is emitted back towards to improve the utilization rate of neutron, there are one thermal neutron absorber 33a, the thermal neutrons at the rear portions slow body 32a
Absorber 33a for absorbing the thermal neutron across slow body 32a to reduce the content of thermal neutron in neutron beam N, inhale by thermal neutron
There are one beams to export 34a to make neutron beam N pass through at the rear portions acceptor 33a, in addition, setting outside beam outlet 34a
One collimator 40, collimator 40 converging the neutron beam, make neutron beam have during being treated compared with
High targeting；Neutron beam is irradiated to after the convergence of collimator 40 with patient 51, and is penetrated by the neutron of collimator 40
Beam and the gamma-ray irradiation being mingled in the neutron beam often cause patient when being not necessarily to the position for the treatment of to patient
Serious injury, therefore patient 51 needs when treating preparation by the position flexible shielding body 50 without being irradiated by epithermal neutron
It blocks and is protected, flexible shielding body 50, which is just played, to be exposed to position 52 to be illuminated in the range of exposures of neutron beam and protect
The effect that shield patient is not injured by more neutron rays, the flexible shielding body 50 surround the normal portions of patient body, and
And it can be bonded the body of patient 51 under the effect of external force, flexible shielding device shown in FIG. 1 and patient have certain distance only
That can arbitrarily change its shape according to the profile of patient body in order to illustrate flexible shielding device, to flexible shielding body whether
Fitting patient does not have any restrictions meaning, exists on the contrary, can be better protected from neutron ray when flexible shielding shows consideration for conjunction patient
Human body is damaged by changing the direction propagated in flexible shielding body.The flexible shielding body 51 can have elasticity,
It is close to the body of patient under the elastic force effect of itself.
<Embodiment 2>
Reactor formula neutron capture therapeutic device as shown in Figure 2 includes reactor formula neutron generating unit 10b, beam-shaping body
The neutron that 30b, collimator 40b and flexible shielding body 50, wherein reactor generate is mixed radiation field, in beam-shaping body 30b
Slow body 32b be used to the fast neutron in mixed radiation field be slowly epithermal neutron, and reflector 31b will be spread around
Neutron beam N is returned in neutron reflection, and thermal neutron absorber 33b is used to absorb the heat in the neutron beam through the slow slow mistakes of body 32b
Neutron is to improve the content of epithermal neutron in neutron beam；Epithermal neutron beam exports 34b by beam and reaches patient 51, wherein
Collimator 40b at beam outlet 34b is for converging neutron beam N to improve the precision for the treatment of.Flexible shielding body 50
The position to be illuminated 52 of patient 51 is exposed in neutron beam and is covered by patient without the position for the treatment of, such patient
51 normal structure then can avoid being injured by the gamma ray in neutron beam and the neutron beam mixed.
<Embodiment 3>
When being treated to patient using neutron capture therapeutic device, the neutron beam N ' after being converged by collimator is right
The patient part of patient is irradiated, meanwhile, the position that need not be irradiated is protected with flexible shielding body.
Fig. 3 show the schematic diagram for measuring flexible shielding body to the shield effectiveness of neutron ray, and N ' is accelerator formula neutron
Capture the neutron beam after being collimated device convergence in therapeutic device or reactor formula neutron capture therapeutic device, 50 in Fig. 3 shown in
Be thickness be 1cm flexible shielding body, wherein flexible shielding body include silica gel and10BN, the present embodiment are selected respectively10BN's
Weight is that 10%, 20%, 30%, 40% and 50% material of flexible shielding body weight calculates separately tool as flexible shielding body
There is different content10Shield effectiveness of the flexible shielding body of BN to neutron ray.It is for measuring neutron reaction shown in 53 in Fig. 3
The detection device of rate,
Detection device detection neutron reaction rate is the gamma for according to copper sheet and neutron reaction and generating gamma ray, and generating
The quantity of ray and the neutron flux for passing through copper sheet are proportional, and detection device is by measuring the quantity of the gamma ray come really
Determine neutron reaction rate, in order to simplify the description to the present embodiment, in the present embodiment, the location presentation of the detection device is
The position of the copper sheet of gamma ray is generated with neutron reaction.
The present embodiment comments shield effectiveness of the flexible shielding body to neutron ray with parameter A, wherein
A=RR/RRref
When wherein RR is detection device position shown in Fig. 3, flexible shielding body is set among detection device and neutron beam,
The neutron reaction rate that detection device detects；
RRrefFor detection device position shown in Fig. 3 when, flexible shielding body is not provided among detection device and neutron beam,
The neutron reaction rate that detection device measures.
It can be seen that the value of A is smaller, illustrate that flexible shielding body is better to the shield effectiveness of neutron.
Detection device measures RR and RRrefWhen, the position relative to collimator immobilizes.
Under these experimental conditions, when flexible shielding body is respectively containing 10%, 20%, 30%, 40% and 50%10BN
When, corresponding A values are respectively：8.3%, 7.5%, 6.2%, 5.4%/and 4.9%, it can be seen that in flexible shielding body material
Addition10BN can effectively shield neutron ray, and with10BN contents increase, shielding of the flexible shielding body to neutron ray
Effect becomes strong.
<Embodiment 4>
In order to improve comfort level of the patient in receiving therapeutic process, flexible shielding body can be cut into various as needed
Shape is to protect patient, the preferably described flexible shielding type to be cut into the shape (as shown in Figure 4) of clothes, and flexible shielding
Body can make patient that the position for irradiating neutron beam be needed to expose by cutting.
The neutron capture therapeutic device that the present invention discloses is not limited to the content described in above example and attached drawing institute
The structure of expression.The material and shape to wherein component and position are made on the basis of the present invention apparently change is replaced
Generation or modification, all within the scope of protection of present invention.
Claims (10)
1. a kind of neutron capture therapeutic device, it is characterised in that：The neutron capture therapeutic device includes neutron generating unit, slow
Body, reflector, beam outlet and flexible shielding body, wherein the neutron generating unit is for generating neutron, during the neutron is formed
Sub-beam, neutron beam include fast neutron；The slow body is adjacent to the neutron generating unit and produces the neutron generating unit
Raw fast neutron is slowly to epithermal neutron；The reflector surrounds the slow body, the neutron reflection for will be spread to surrounding
Return the neutron beam；The beam outlet is passed through by the slow neutron beam of the slow body to make and shines patient
It penetrates；The flexible shielding body covers patient without receiving neutron exposure during being treated for the underway sub- capture of patient
Position can be bonded with shielding the neutron ray in therapeutic process with the profile at the position under external force.
2. neutron capture therapeutic device as described in claim 1, which is characterized in that the neutron capture therapeutic device includes standard
Straight device and thermal neutron absorber, wherein collimator be adjacent to beam outlet outside, exports out from beam to converge
Neutron beam；The thermal neutron absorber is adjacent to the slow body, for absorb thermal neutron to avoid treatment when to shallow-layer just
Often tissue caused multi-dose.
3. neutron capture therapeutic device as claimed in claim 2, which is characterized in that the flexible shielding body is selected from paraffin, gathers
The composition of ethylene or boracic, wherein boron element is in the composition of the boracic10B。
4. neutron capture therapeutic device as claimed in claim 3, which is characterized in that the composition of the boracic include silica gel and
Contain10The neutron capture material of B element, wherein containing10The neutron capture material of B element accounts for the 10% of the boron-containing compositions weight
~50%.
5. neutron capture therapeutic device as claimed in claim 4, which is characterized in that described to contain10The neutron capture material of B element
For10BN or10B4C。
6. such as neutron capture therapeutic device according to any one of claims 1 to 5, which is characterized in that the external force includes weight
The thickness of power, the flexible shielding body is less than or equal to 1cm.
7. neutron capture therapeutic device as claimed in claim 2, which is characterized in that flexible in neutron capture therapeutic process
The shield distance nearest apart from collimator is less than or equal to 20cm.
8. such as neutron capture therapeutic device according to any one of claims 1 to 5, which is characterized in that the flexible shielding body
With elasticity, in neutron capture therapeutic process, the flexible shielding body is close to patient contours under the action of elastic force.
9. such as neutron capture therapeutic device according to any one of claims 1 to 5, which is characterized in that the flexible shielding body
Any opening be equipped with tightening structure, the tightening structure makes flexible shielding body be bonded patient contours in opening.
10. such as neutron capture therapeutic device according to any one of claims 1 to 5, which is characterized in that the flexible shielding body
The dose of radiation that the normal structure of covering receives in neutron capture therapeutic process is less than 18Gy/h.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710017520.7A CN108295385B (en) | 2017-01-11 | 2017-01-11 | Neutron capture therapeutic device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710017520.7A CN108295385B (en) | 2017-01-11 | 2017-01-11 | Neutron capture therapeutic device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN108295385A true CN108295385A (en) | 2018-07-20 |
| CN108295385B CN108295385B (en) | 2024-04-16 |
Family
ID=62871631
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201710017520.7A Active CN108295385B (en) | 2017-01-11 | 2017-01-11 | Neutron capture therapeutic device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN108295385B (en) |
Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4172979A (en) * | 1978-06-15 | 1979-10-30 | Morrison Richard A | Method and apparatus for automatically providing radiation therapy treatment conforming to a desired volume of tissue |
| US5190990A (en) * | 1990-04-27 | 1993-03-02 | American Dental Association Health Foundation | Device and method for shielding healthy tissue during radiation therapy |
| CA2118185A1 (en) * | 1993-10-15 | 1995-04-16 | Jamie Garza | Protective face mask system using varying thicknesses of energy absorption and dissipation material |
| US20030128808A1 (en) * | 2001-11-23 | 2003-07-10 | Johann Kindlein | Device for effecting radiation therapy in an animal body |
| US8354658B1 (en) * | 2005-09-22 | 2013-01-15 | Xoft, Inc. | Lightweight radiation absorbing shield |
| US20130263864A1 (en) * | 2010-08-30 | 2013-10-10 | Hubertus von Treuenfels | Teat device for preventing snoring and other habits |
| CN104771837A (en) * | 2015-04-03 | 2015-07-15 | 中国中原对外工程有限公司 | Cancericidal nuclide neutron knife adopting one-reactor and three-irradiation-seat layout |
| CN105268103A (en) * | 2015-11-19 | 2016-01-27 | 北京品驰医疗设备有限公司 | In vitro charging implantation medical instrument |
| CN205073542U (en) * | 2015-09-28 | 2016-03-09 | 南京中硼联康医疗科技有限公司 | A radiant ray detecting system for neutron capture treatment system |
| CN207076025U (en) * | 2017-01-11 | 2018-03-09 | 南京中硼联康医疗科技有限公司 | Neutron capture therapeutic system |
-
2017
- 2017-01-11 CN CN201710017520.7A patent/CN108295385B/en active Active
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4172979A (en) * | 1978-06-15 | 1979-10-30 | Morrison Richard A | Method and apparatus for automatically providing radiation therapy treatment conforming to a desired volume of tissue |
| US5190990A (en) * | 1990-04-27 | 1993-03-02 | American Dental Association Health Foundation | Device and method for shielding healthy tissue during radiation therapy |
| CA2118185A1 (en) * | 1993-10-15 | 1995-04-16 | Jamie Garza | Protective face mask system using varying thicknesses of energy absorption and dissipation material |
| US20030128808A1 (en) * | 2001-11-23 | 2003-07-10 | Johann Kindlein | Device for effecting radiation therapy in an animal body |
| US8354658B1 (en) * | 2005-09-22 | 2013-01-15 | Xoft, Inc. | Lightweight radiation absorbing shield |
| US20130263864A1 (en) * | 2010-08-30 | 2013-10-10 | Hubertus von Treuenfels | Teat device for preventing snoring and other habits |
| CN104771837A (en) * | 2015-04-03 | 2015-07-15 | 中国中原对外工程有限公司 | Cancericidal nuclide neutron knife adopting one-reactor and three-irradiation-seat layout |
| CN205073542U (en) * | 2015-09-28 | 2016-03-09 | 南京中硼联康医疗科技有限公司 | A radiant ray detecting system for neutron capture treatment system |
| CN105268103A (en) * | 2015-11-19 | 2016-01-27 | 北京品驰医疗设备有限公司 | In vitro charging implantation medical instrument |
| CN207076025U (en) * | 2017-01-11 | 2018-03-09 | 南京中硼联康医疗科技有限公司 | Neutron capture therapeutic system |
Non-Patent Citations (1)
| Title |
|---|
| 杨玉青: "含硼卟啉在硼中子捕获治疗中的研究进展", 核技术 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN108295385B (en) | 2024-04-16 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN108325092B (en) | Beam shaping body for neutron capture therapy | |
| TWI581821B (en) | A beam shaping assembly for neutron capture therapy | |
| CN107661577B (en) | Beam shaping body for neutron capture therapy | |
| RU2717363C1 (en) | Beam forming unit for neutron capture therapy | |
| WO2017206485A1 (en) | Radiation dose measuring method | |
| Lee et al. | A Monte Carlo dosimetry‐based evaluation of the reaction near threshold for accelerator boron neutron capture therapy | |
| CN109407133B (en) | Biological dosimeter and neutron capture treatment system with same | |
| WO2018076787A1 (en) | Beam shaping body for neutron capture therapy | |
| CN205339881U (en) | Beam shaper for neutron -capture therapy | |
| Brenner et al. | Reduction of the secondary neutron dose in passively scattered proton radiotherapy, using an optimized pre-collimator/collimator | |
| US6674829B1 (en) | Neutron radiation installation for treatment of cancer | |
| KR20200111270A (en) | Therapeutic electron radiation device for cancer treatment | |
| CN207076025U (en) | Neutron capture therapeutic system | |
| CN208355947U (en) | Neutron capture treatment system | |
| CN107292075A (en) | Promote the method that radiotherapy system calculates benefit | |
| CN107224675A (en) | Boron neutron capture treatment system | |
| Ghassoun et al. | Spatial and spectral characteristics of a compact system neutron beam designed for BNCT facility | |
| Ye | Boron self‐shielding effects on dose delivery of neutron capture therapy using epithermal beam and boronophenylalanine | |
| CN109925610B (en) | Neutron capture therapy system | |
| Wang et al. | An AB-BNCT epithermal neutron source using 7Li (p, n) 7Be reaction | |
| Hu et al. | Accelerator based epithermal neutron source for clinical boron neutron capture therapy | |
| CN108295385A (en) | Neutron capture therapeutic device | |
| CN109925606A (en) | Neutron capture treatment system | |
| CN207856088U (en) | Beam-shaping body for neutron capture treatment | |
| Elshahat et al. | Design calculations of an accelerator based BSA for BNCT of brain cancer |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |