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82 results about "Epithermal neutron" patented technology
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Non Proliferating Thorium Nuclear Fuel Inert Metal Matrix Alloys for Fast Spectrum and Thermal Spectrum Thorium Converter Reactors
InactiveUS20080144762A1Improve heat transfer performanceRobust assemblyOptical rangefindersNuclear energy generationHigh energyEpithermal neutron
A set of alloy formulations is disclosed to use with thorium based nuclear fuels in a fast spectrum reactor; with thorium based nuclear fuels in existing thermal spectrum power reactors; for medical isotope production in the epithermal, the fast, the fission spectrum and the thermal spectra; and to use as fuel in test and experimental reactors that are non proliferative. The alloys form inert metal matrixes to hold fine particles of dispersed thorium containing fuel. The formulations also are useful for the production of medical and commercial isotopes in the high energy, fast and epithermal neutron spectra.
Owner:RGT UNIV OF CALIFORNIA
Beam shaper for neutron-capture therapy
The invention provides a beam shaper for neutron-capture therapy in order to improve flux and quality of a neutron source. The beam shaper comprises a target, a slowing body adjacent to the target, a reflector wrapping the slowing body, a thermal neutron absorber adjacent to the slow body, a radiation shield arranged in the beam shaper and a beam outlet. The target generates nuclear reaction with a proton beam incident from a beam inlet so as to generate neutrons, the neutrons form a neutron beam which defines a main axis, the slowing body slows down the neutrons generated from the target to an epithermal neutron energy region, the reflector guides the neutrons deviating from the main axis to the main axis so as to improve intensity of the epithermal neutron beam, a gap passage is arranged between the slowing body and the reflector so as to improve epithermal neutron flux, the thermal neutron absorber is used for absorbing the thermal neutron so as to avoid causing overmuch dosed with shallow normal tissue during therapy, and the radiation shield is used for shielding leaked neutrons and photon so as to reduce normal tissue dose in a non-radiation region.
Owner:NEUBORON MEDTECH
Production of thorium-229
InactiveUS20050105666A1Conversion outside reactor/acceleratorsRadioactive sourcesNeutron captureAlpha particle
A method for producing 229Th includes the steps of providing 226Ra as a target material, and bombarding the target material with alpha particles, helium-3, or neutrons to form 229Th. When neutrons are used, the neutrons preferably include an epithermal neutron flux of at least 1×1013 n s−1·cm−2. 228Ra can also be bombarded with thermal and / or energetic neutrons to result in a neutron capture reaction to form 229Th. Using 230Th as a target material, 229Th can be formed using neutron, gamma ray, proton or deuteron bombardment.
Owner:UT BATTELLE LLC
Beam shaping body for neutron capture therapy
In order to improve the flux and the quality of a neutron source, the invention provides a beam shaping body for neutron capture therapy. The beam shaping body comprises a beam inlet, a target, a retarding body adjacent to the target, a reflecting body surrounding the external of the retarding body, a thermal neutron absorber adjacent to the retarding body, and a radiation shield and a beam outlet formed in the beam shaping body, wherein the target has nuclear reaction with proton beam entering from the beam inlet, so as to produce a neutron; the neutron forms a neutron beam; the neutron beam defines a main axis; the retarding body slows down the neutron produced by the target to an epithermal neutron energy region; the retarding body is designed to a shape containing at least one cone; the reflecting body guides the neutron deviated from the main axis back to the main axis, so as to improve the strength of an epithermal neutron beam; the thermal neutron absorber is used for absorbing a thermal neutron, so as to prevent the thermal neutron from causing excessive dosage with a superficial normal tissue during therapy; the radiation shield is used for shielding leaked neutron and photon, so as to reduce the normal tissue dosage of a non-irradiated region.
Owner:NEUBORON MEDTECH
Method and Apparatus for Neutron Logging Using a Position Sensitive Neutron Detector
InactiveUS20110272570A1Improve propertiesReduction of statistical noiseNuclear radiation detectionPorosityElectronic controller
A neutron logging tool includes a neutron source and at least one position sensitive thermal or epithermal neutron detector. The logging tool further includes an electronic controller configured to estimate the axial location of detected neutrons. Measurement of the axial neutron flux distribution enables other formation and borehole parameters such as formation porosity and sensor standoff to be computed. In logging while drilling embodiments, a borehole caliper may also be computed form the axial neutron flux distribution.
Owner:SCHLUMBERGER TECH CORP
Beam shaping assembly for neutron capture therapy
ActiveUS20160158579A1Increase fluxQuality improvementRadiation/particle handlingDirect voltage acceleratorsReduced doseNuclear reaction
A beam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam defining a main axis, a moderator adjoining to the target, a reflector surrounding the moderator, a thermal neutron absorber adjoining to the moderator, a radiation shield arranged inside the beam shaping assembly and a beam outlet. The neutrons are moderated to epithermal neutron energies. An outer surface of the moderator includes at least a first tapered section. The reflector leads the neutrons deviated from the main axis back. The thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdosing in superficial normal tissue during therapy. The radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation.
Owner:NEUBORON MEDTECH
High Flux Neutron Source
InactiveUS20130129027A1Weaken energyImprove throughputConversion outside reactor/acceleratorsNeutron sourcesHigh fluxEpithermal neutron
Owner:ADELPHI TECH INC
Thermal neutron porosity from neutron slowing-down length, formation thermal neutron capture cross section, and bulk density
A method for determining at least one formation property calculated from neutron measurements acquired with a downhole tool includes emitting neutrons from a source in the tool into the formation, detecting neutrons with at least one detector in the downhole tool, calculating a first slowing-down length (L1) based on the detected neutrons, and deriving a second slowing-down length (L2) based on the first slowing-down length (L1). Further steps include deriving a correlation function for relating slowing-down lengths from a first tool to slowing-down lengths associated with a different source, wherein the correlation function depends on formation properties such as bulk density; and applying the correlation function to the slowing-down length of the first tool to derive the slowing-down length of the second tool. A method for determining a thermal neutron formation porosity based on a slowing-down length from epithermal neutron measurements from an electronic neutron source includes converting the slowing-down length into a computed neutron slowing-down length from thermal neutron measurements from a chemical neutron source, wherein the converting uses a correlation function that depends on formation bulk density; deriving a thermal neutron countrate ratio based on the computed neutron slowing-down length, wherein the deriving uses a function that depends on the formation bulk density and formation sigma; and computing the thermal neutron formation porosity from the thermal neutron countrate ratio.
Owner:SCHLUMBERGER TECH CORP
Borehole imaging and standoff determination using neutron measurements
Apparatus and methods for determining borehole diameter and standoff for neutron porosity logging systems. The apparatus comprises an isotopic neutron source, a single epithermal neutron detector and two thermal neutron detectors, where all detectors are at different axial spacings from the neutron source. Thermal neutron porosity is determined from the combined response of the thermal neutron detectors. Epithermal neutron porosity is determined from the response of the single epithermal neutron detector. Embodied as a wireline system, a difference between thermal neutron porosity and epithermal neutron porosity is used to compute a tool standoff, which in turn is used to correct the thermal neutron porosity for effects of standoff. Borehole size measurements are made independently and preferably with a mechanical caliper of a density tool subsection. Embodied as a LWD system, the difference between thermal neutron porosity and epithermal neutron porosity is used to correct the thermal neutron porosity measurement for both borehole diameter and radial position (standoff) of the tool within the borehole.
Owner:WEATHERFORD TECH HLDG LLC
Thermal Neutron Porosity from Neutron Slowing-Down Length, Formation Thermal Neutron Capture Cross Section, and Bulk Density
A method for determining at least one formation property calculated from neutron measurements acquired with a downhole tool includes emitting neutrons from a source in the tool into the formation, detecting neutrons with at least one detector in the downhole tool, calculating a first slowing-down length (L1) based on the detected neutrons, and deriving a second slowing-down length (L2) based on the first slowing-down length (L1). Further steps include deriving a correlation function for relating slowing-down lengths from a first tool to slowing-down lengths associated with a different source, wherein the correlation function depends on formation properties such as bulk density; and applying the correlation function to the slowing-down length of the first tool to derive the slowing-down length of the second tool. A method for determining a thermal neutron formation porosity based on a slowing-down length from epithermal neutron measurements from an electronic neutron source includes converting the slowing-down length into a computed neutron slowing-down length from thermal neutron measurements from a chemical neutron source, wherein the converting uses a correlation function that depends on formation bulk density; deriving a thermal neutron countrate ratio based on the computed neutron slowing-down length, wherein the deriving uses a function that depends on the formation bulk density and formation sigma; and computing the thermal neutron formation porosity from the thermal neutron countrate ratio.
Owner:SCHLUMBERGER TECH CORP
Device for online measurement of a flow of fast and epithermal neutrons
InactiveUS20110274230A1Nuclear energy generationNuclear monitoringThermal neutron detectorEpithermal neutron
A device for online measurement of a flow of fast and epithermal neutrons. The device has a fast and epithermal neutron detector (DNR) able to detect principally fast and epithermal neutrons; a thermal neutron detector (DNT) able to detect principally thermal neutrons; a first circuit (C1) for processing the signal delivered by the fast neutron detector; a second circuit (C2) for processing the signal delivered by the thermal neutron detector; a means (CE, PMM) suitable for determining the progressive sensitivity to the fast neutrons and to the thermal neutrons of each of the neutron detectors, and a computer (CALC) which computes the flow of fast and epithermal neutrons on the basis of the said progressive sensitivities and of the signals delivered by the first and second processing circuits.
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES +1
Method of using gadolinium neutron capture to treat cancers
Described is a method of using gadolinium-containing compounds as agents for neutron capture therapy to treat neoplastic cell growth. The subject is exposed to a gadolinium-containing compound for a time sufficient to allow the compound to accumulate in neoplastic cells. The subject is then exposed to a thermal and / or epithermal neutron flux, thereby initiating a neutron capture reaction in the gadolinium atoms that results in specific death of neoplastic cells.
Owner:WISCONSIN ALUMNI RES FOUND
Neutron filter material and preparation method thereof
The invention discloses a neutron filter material and a preparation method thereof. The preparation method comprises 1, orderly carrying out primary compacting molding, sintering and hot isostatic pressure molding on an epithermal neutron filter material, or 2, putting the epithermal neutron filter material into a jacket and carrying out hot isostatic pressure molding, wherein the epithermal neutron filter material comprises at least one of tungsten powder, aluminum powder, titanium powder, boron carbide, titanium oxide, lithium fluoride, aluminum fluoride, gadolinium oxide, gadolinium fluoride, boron nitride, boron oxide, zirconium boride, titanium boride and lithium oxide powder. The neutron filter material has the advantages that 1, the neutron filter material has outstanding filterability and provides a specific energy section and especially provides a neutron beam of an epithermal neutron energy section, 2, the preparation method is reliable, product performances are outstanding, and in boron neutron capture therapy device use, the epithermal neutron filtration satisfies apparatus design indexes, and 3, the large-scale thick neutron filter material can be prepared and machining can be realized.
Owner:BEIJING RADIATION APPL RES CENT
Method of using gadolinium neutron capture to treat cancers
Described is a method of using gadolinium-containing compounds as agents for neutron capture therapy to treat neoplastic cell growth. The subject is exposed to a gadolinium-containing compound for a time sufficient to allow the compound to accumulate in neoplastic cells. The subject is then exposed to a thermal and / or epithermal neutron flux, thereby initiating a neutron capture reaction in the gadolinium atoms that results in specific death of neoplastic cells.
Owner:WISCONSIN ALUMNI RES FOUND
Beam shaping body for neutron capture therapy
Owner:NEUBORON MEDTECH
Beam shaping assembly for neutron capture therapy
ActiveUS9889320B2Increase fluxQuality improvementRadiation/particle handlingDirect voltage acceleratorsNeutron captureLight beam
Owner:NEUBORON MEDTECH
Beam shaping assembly for neutron capture therapy
Disclosed is a beam shaping assembly, including a beam inlet; a target, wherein the target has nuclear reaction with the incident proton beam; a moderator adjoining to the target, wherein the neutrons are moderated by the moderator to epithermal neutrons; a reflector surrounding the moderator, and leads the deflected neutrons back to the moderator to enhance the epithermal neutron beam intensity; and a cooling system, wherein the cooling system comprises a first cooling part for cooling target, a second cooling part and a third cooling part connecting with the first cooling part and extending in a direction parallel to the axis of the accelerating tube respectively, the first cooling part connects with the target in a face to face manner, the cooling medium is inputted into the first cooling part from the second cooling part and is outputted from first cooling part through the third cooling part.
Owner:NEUBORON MEDTECH
Radiation shielding glass and preparation method thereof
The invention provides a radiation shielding glass, which is represented by mass percentage and whose chemical composition is SiO 2 : 10~30%, PbO: 25~60%, Al 2 o 3 : 0~20%, B 2 o 3 : 0~20%, Li 2 O: 0~20%, Re 2 o 3 (Re=Gd, Eu, Dy): 0~15%, In 2 o 3 : 0~15%, CeO 2 : 0~1.5%, and provide a preparation method of shielding glass with the same composition, the gamma ray absorption coefficient of the shielding glass is 0.5cm ‑1 (0.511MeV) and 0.3cm ‑1 (1.25MeV), the visible light transmittance is greater than 80% when the thickness is 6mm, and the shielding rates of slow, medium energy and fast neutrons are above 97%, 40% and 20% respectively, which can be used for gamma rays and medium neutrons in the nuclear industry. Shielding windows (plates) for neutron radiation, epithermal neutron radiation fields for medical use or gamma rays for PET inspection.
Owner:北京玻璃研究院有限公司
Beam shaping assembly for neutron capture therapy
ActiveUS20160158578A1Increase fluxQuality improvementRadiation/particle handlingDirect voltage acceleratorsReduced doseNeutron capture
A beam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam defining a main axis, a moderator adjoining to the target, a reflector surrounding the moderator, a thermal neutron absorber adjoining to the moderator, a radiation shield arranged inside the beam shaping assembly and a beam outlet. The neutrons are moderated to epithermal neutron energies. The reflector leads the neutrons deviated from the main axis back, and a gap channel is arranged between the moderator and the reflector. The thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdosing in superficial normal tissue during therapy. The radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation.
Owner:NEUBORON MEDTECH
Fission neutron well logging correction method
ActiveCN104074501AReduce the number of samplesReduce exploration costsSurveyWell loggingFission neutron
The invention relates to a fission neutron well logging correction method, which comprises the following steps that: 1, a correction counting rate of a neutron monitor of a tested wellhole is obtained; 2, a water correction factor is obtained; 3, the neutron counting rates near a well wall and along a well axis after the water correction in a tested well are obtained; and 4, the neutron counting rates near the well wall and along the well axis after the epithermal neutron service life correction in the tested well are obtained. The method provided by the invention can be used for directly measuring the uranium content. Compared with drill hole rock core sampling chemical analysis results, the method has the advantages that the deviation does not exceed 10 percent. The uranium ore grade is more objectively reflected; particularly in sections with damaged uranium-radium balance, conventional gamma well logging is combined, and a uranium-radium balance factor of a drill hole ore block can be determined in site; and the rock core sampling quantity is reduced, and the uranium resource investigation cost is reduced. The method can be used for accurately measuring the uranium leaching rate in mining using the leaching technology, avoids the environment pollution and the cost waste due to unquestioning excessive liquid injection in the process of the mining using the leaching technology, and has important practical significance on improving the efficiency of the mining using the leaching technology, reducing the cost and protecting the environment.
Owner:核工业航测遥感中心
Prompt uranium fission neutron logging technique based on epithermal neutron and thermal neutron ratio
ActiveCN103711479ARealize loggingBorehole/well accessoriesNuclear radiation detectionReal time algorithmSecondary neutron
The invention discloses a prompt uranium fission neutron logging technique based on the epithermal neutron and thermal neutron ratio. The technique is specifically characterized in that in boreholes, fast neutrons, also called virgin neutrons, are transmitted to formation rock by means of pulsing; the virgin neutrons are successively moderated by in-well medium into epithermal neutrons and thermal neutrons; the thermal neutrons induce 235U fission to radiate prompt uranium fission neutrons, also called secondary neutrons; the secondary neutrons are successively moderated into epithermal neutrons and thermal neutrons, inducing 235U fission again; from any moment t after the virgin neutrons are moderated into the thermal neutrons, the total nE(t) of existing epithermal neutrons in the formation rock is in direct proportion to the total nT(t) of existing thermal neutrons and uranium content qu, namely nE(t)<nT(t) qu. By using a bi-neutron detector and a dual-time detector disposed in the invention to measure time spectra of the epithermal and thermal neutrons and defining an attenuation ratio of the epithermal neutrons to the thermal neutrons as 'E / T', from a moment, when the virgin neutrons are moderated into the thermal neutrons, to any moment, a uranium quantitative real-time algorithm based on saturated seams is constructed.
Owner:EAST CHINA UNIV OF TECH
Beam shaping assembly for neutron capture therapy
ActiveUS10639499B2Improving flux and qualityReduce doseHandling using diffraction/refraction/reflectionMedical devicesNuclear engineeringNeutron capture
In order to improve flux and quality of neutron sources, the disclosure provides a beam shaping assembly for neutron capture therapy includes: a beam inlet; a target, wherein the target has nuclear reaction with an incident proton beam from the beam inlet to produce neutrons; a moderator adjoining to the target, wherein the neutrons are moderated by the moderator to epithermal neutron energies, the moderator includes a main body and a supplement section surrounding the main body, the main body and the supplement section form at least a tapered structure; a reflector surrounding the moderator; a thermal neutron absorber adjoining to the moderator; a radiation shield arranged inside the beam shaping assembly, wherein the radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation; and a beam outlet.
Owner:NEUBORON MEDTECH
Neutron moderation material
ActiveUS10157693B2Excellent prosthetic beam qualityAdd depthRadiation/particle handlingNuclear engineering solutionsEpithermal neutronMg element
A neutron moderation material for use in a BNCT beam shaping assembly. The neutron moderation material comprises three elements, i.e., Mg, Al, and F, wherein the mass fraction of the Mg element is 3.5%-37.1%, the mass fraction of the Al element is 5%-90.4%, and the mass fraction of the F element is 5.8%-67.2%; the sum of the weights of the Mg, Al, and F elements is 100% of the total weight of the neutron moderation material. The neutron moderation material may be doped with a small amount of 6Li-containing substances, and the addition of the 6Li-containing substances effectively decreases the content of γ-rays in epithermal neutron beams.
Owner:NEUBORON MEDTECH
Beam shaping body for neutron capture therapy
ActiveCN106798969ANuclear energy generationX-ray/gamma-ray/particle-irradiation therapyProtonEpithermal neutron
The invention, on one hand, provides a beam shaping body for neutron capture therapy, so as to improve the flux and the quality of a neutron source. The beam shaping body comprises a beam inlet, a target material, a retarding body adjacent to the target material, a reflector surrounding the retarding body, a thermal neutron absorber adjacent to the retarding body, a radiation shield arranged inside the beam shaping body and a beam outlet, wherein the target material and a proton beam incident from the beam inlet are subjected to a nuclear reaction to produce neutrons; the neutrons form a neutron beam; the neutron beam limits a spindle; the retarding body retards the neutrons generated from the target material to an epithermal neutron energy region; the retarding body is set to be in a shape containing at least one cone; the retarding body comprises a main body part and a supplementary part surrounding the periphery of the main body part; the material of the supplementary part is different from that of the main body part; the reflector guides neutrons deviating from the spindle back to the spindle to improve the epithermal neutron beam intensity; the thermal neutron absorber is used for absorbing thermal neutrons to avoid over dose with superficial normal tissues in the case of therapy; and the radiation shield is used for shielding leaked neutrons and photons to reduce the normal tissue dose in a non-radiation area.
Owner:NEUBORON MEDTECH
Neutron capture therapy system
ActiveUS10898731B2Increase beam intensityEasy to replaceAcceleratorsIrradiation devicesNuclear engineeringNeutron capture
The present disclosure provides a neutron capture therapy system including a beam shaping assembly. The beam shaping assembly includes a beam inlet; a neutron generator arranged into the beam shaping assembly, the neutron generator has nuclear reaction with an incident proton beam from the beam inlet to produce neutrons; a moderator adjacent to the neutron generator, the neutrons are moderated by the moderator to epithermal neutron energies; a reflector surrounding the neutron generator and the moderator, the reflector leads the deflected neutrons back to enhance epithermal neutron beam intensity; a beam outlet; and at least a movable member moving away from or close to the neutron generator, the movable member moves between a first position where the neutron generator is replaceable, and a second position where the neutron generator is irreplaceable. The neutron capture therapy system has a simple structure, and the neutron generator is easy to be replaced.
Owner:NEUBORON MEDTECH LTD
Thermal neutron transmission imaging method and imaging device based on compact D-D neutron source
PendingCN111982940AImprove parallelismImprove spatial resolutionMaterial analysis by transmitting radiationNuclear engineeringNeutron moderator
The invention discloses a thermal neutron transmission imaging method and imaging device based on a compact D-D neutron source. The compact D-D neutron source is adopted to provide exogenous neutrons;2.45 MeV D-D fast neutrons outputted by the D-D neutron source are moderated into thermal neutrons or epithermal neutrons through the neutron moderator; after being slowed down, the neutrons enter abig-end-up conical neutron collimation hole channel vertically formed in a neutron slowdown body above a D-D neutron source; the collimated thermal neutron beam transmits a detected object; thermal neutrons penetrating through an object in a transmission mode are detected through the thermal neutron image detector system installed at the upper end of the conical neutron collimation hole channel, the thermal neutrons are converted into digital transmission images through the thermal neutron image detector system, two-dimensional spatial distribution of thermal neutron transmission intensity isobtained, and then the internal structure of the detected object and the spatial distribution situation of different materials are obtained. The method has the characteristics of mobility, rapidness,accuracy, no damage and good spatial resolution, and can be used for nondestructive detection of objects.
Owner:LANZHOU UNIVERSITY
Beam shaping assembly for neutron capture therapy
Abeam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam, a moderator adjoining to the target, a reflector surrounding the moderator. The neutrons are moderated to epithermal neutron energies by the moderator, and part of the moderator disposed on the back of the target can be replaced so as to adjust the epithermal neutron energies. The reflector leads the neutrons deviated from the main axis back.
Owner:NEUBORON MEDTECH
Neutron moderation material
ActiveUS20180233246A1High beam qualityGood advantage depthRadiation/particle handlingNuclear engineering solutionsEpithermal neutronMg element
A neutron moderation material for use in a BNCT beam shaping assembly. The neutron moderation material comprises three elements, i.e., Mg, Al, and F, wherein the mass fraction of the Mg element is 3.5%-37.1%, the mass fraction of the Al element is 5%-90.4%, and the mass fraction of the F element is 5.8%-67.2%; the sum of the weights of the Mg, Al, and F elements is 100% of the total weight of the neutron moderation material. The neutron moderation material may be doped with a small amount of 6Li-containing substances, and the addition of the 6Li-containing substances effectively decreases the content of γ-rays in epithermal neutron beams.
Owner:NEUBORON MEDTECH
Neutron beam current device and neutron irradiation device
InactiveCN111420307ASolve the problem that only one type of neutron beam can be providedTroubleshoot beam issuesX-ray/gamma-ray/particle-irradiation therapyGamma photonNeutron irradiation
The embodiment of the invention provides a neutron beam current device. The neutron beam current device is used for carrying out neutron energy spectrum adjustment on a neutron beam entering the neutron beam current device, wherein particles of the neutron beam comprise fast neutrons, epithermal neutrons, thermal neutrons and gamma photons. The neutron beam current device comprises a filtering part, an adjusting part and a collimator, wherein the filtering part is used for filtering fast neutrons in the neutron beam; the adjusting part is used for adjusting the neutron energy spectrum of the neutron beam so as to obtain an epithermal neutron beam or a thermal neutron beam; and the collimator is used for carrying out collimated emission on the adjusted neutron beam, wherein the filtering part, the adjusting part and the collimator are sequentially arranged in the neutron beam current device in a direction from a position that the neutron beam enters the neutron beam current device to aposition that the neutron beam is emitted out of the neutron beam current device. According to the neutron beam current device provided by the embodiment of the invention, two neutron beams, namely the thermal neutron or the epithermal neutron, can be provided through one beam current channel, so that two beam current channels do not need to be separately arranged, a larger space occupied by a plurality of beam current channels is avoided, and increase of construction cost is avoided.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY
Beam Shapers for Neutron Capture Therapy
In order to improve the flux and the quality of a neutron source, the invention provides a beam shaping body for neutron capture therapy. The beam shaping body comprises a beam inlet, a target, a retarding body adjacent to the target, a reflecting body surrounding the external of the retarding body, a thermal neutron absorber adjacent to the retarding body, and a radiation shield and a beam outlet formed in the beam shaping body, wherein the target has nuclear reaction with proton beam entering from the beam inlet, so as to produce a neutron; the neutron forms a neutron beam; the neutron beam defines a main axis; the retarding body slows down the neutron produced by the target to an epithermal neutron energy region; the retarding body is designed to a shape containing at least one cone; the reflecting body guides the neutron deviated from the main axis back to the main axis, so as to improve the strength of an epithermal neutron beam; the thermal neutron absorber is used for absorbing a thermal neutron, so as to prevent the thermal neutron from causing excessive dosage with a superficial normal tissue during therapy; the radiation shield is used for shielding leaked neutron and photon, so as to reduce the normal tissue dosage of a non-irradiated region.
Owner:NEUBORON MEDTECH
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