A method for preparing 18F-BPA and an intermediate, by which high-purity 18F-BPA is obtained. The method simplifies the synthesis steps after 18F labeling, and is easy to operate and efficient.
C07B 59/00 - Introduction of isotopes of elements into organic compounds
C07C 229/34 - Compounds containing amino and carboxyl groups bound to the same carbon skeleton having amino and carboxyl groups bound to acyclic carbon atoms of the same carbon skeleton the carbon skeleton containing six-membered aromatic rings
C07C 249/02 - Preparation of compounds containing nitrogen atoms doubly-bound to a carbon skeleton of compounds containing imino groups
An animal irradiation system includes a radioactive source and an irradiation fixing apparatus having irradiated bodies. The radioactive source includes a beam outlet having a first central axis. Radioactive rays generated by the radioactive source exit from the beam outlet and irradiate the irradiated bodies. The radioactive rays define a main axis around the first central axis. The irradiation fixing apparatus includes a box body, which is divided into multiple accommodating chambers around a second central axis. Each accommodating chamber accommodates an irradiated body. Multiple first irradiation holes corresponding to the accommodating chambers are formed on the box body. The radioactive rays pass through the first irradiation holes and then irradiate the irradiated bodies. A maximum distance from an inner wall of each first irradiation hole to the first central axis is less than a minimum distance from an inner wall of the beam outlet to the first central axis.
The present disclosure provides a neutron capture therapy system, including an accelerator for generating a charged particle beam, a neutron generator for generating a neutron beam having neutrons after irradiation by the charged particle beam, and a beam shaping assembly for shaping the neutron beam. The beam shaping assembly includes a moderator and a reflecting assembly surrounding the moderator. The neutron generator generates the neutrons after irradiation by the charged particle beam. The moderator moderates the neutrons generated by the neutron generator to a preset energy spectrum. The reflecting assembly includes a reflecting assembly to deflected neutrons back to the neutron beam and a supporting member to support the reflectors. A lead-antimony alloy is for the reflecting assembly to mitigate a creep effect that occurs when only a lead material is for the reflectors, thereby improving the structural strength of a beam shaping assembly.
An animal irradiation system (100) comprises a radioactive source (10) and an irradiation fixing apparatus (20); the radioactive source (10) comprises a beam outlet (OUT); a radioactive ray generated by the radioactive source (10) exits from the beam outlet (OUT) and irradiates irradiated bodies (200) in the irradiation fixing apparatus (20); the radioactive ray exiting from the beam outlet (OUT) defines a main axis around a first central axis (X); the irradiation fixing apparatus (20) comprises a box body (21) used for accommodating the irradiated bodies (200); the box body (21) has a second central axis (Y); the box body (21) is divided into multiple accommodating cavities (C) in the peripheral direction around the second central axis (Y); each accommodating cavity (C) is used for accommodating an irradiated body (200); multiple first irradiation holes (22) corresponding to each accommodating cavity (C) are formed on the box body (21); the radioactive ray generated by the radioactive source (10) passes through the first irradiation holes (22) and then irradiates the irradiated bodies (200) in the accommodating cavities (C); the maximum distance (R1) from the inner wall of the first irradiation hole (22) to the first central axis (X) is less than the minimum distance (R2) from the inner wall of the beam outlet (OUT) to the first central axis (X). The animal irradiation system (100) and the irradiation fixing apparatus (20) thereof simultaneously fix and irradiate multiple irradiated bodies (200), thereby improving experiment efficiency.
Provided is a radiation detection system for improving the accuracy of a neutron beam irradiation dose for a neutron capture therapy system. The neutron capture therapy system includes a charged particle beam, a charged particle beam inlet for passing the charged particle beam, a neutron generating unit for generating the neutron beam by means of a nuclear reaction with the charged particle beam, a beam shaping assembly for adjusting flux and quality of the neutron beam, and a beam outlet adjoining to the beam shaping assembly, the radiation detection system includes a radiation detection device arranged within the beam shaper or outside the beam shaping assembly, the radiation detection device is used for real-time detection of the overflowing neutron beam by the neutron generating unit or the generated γ-ray after the nuclear reaction of the charged particle beam with the neutron generating unit.
A neutron capture therapy system and a target for a particle beam generating device, which may improve the heat dissipation performance of the target, reduce blistering and extend the service life of the target. The neutron capture therapy system includes a neutron generating device and a beam shaping assembly. The neutron generating device includes an accelerator and a target, and a charg\ed particle beam generated by acceleration of the accelerator interacts with the target to generate a neutron beam. The target includes an acting layer, a backing layer and a heat dissipating structure, the acting layer interacts with the charged particle beam to generate the neutron beam, the backing layer supports the action layer, and the heat dissipating structure includes a tubular member composed of tubes arranged side by side.
Disclosed is a fluorescent compound as represented by general formula I, or a salt, an enantiomer, a diastereomer, a tautomer, a solvate or a polymorph thereof, having the structure (I); wherein m and n are each an integer between 0-10; and Y1 and Y2 are each independently selected from the group of hydrogen, phenyl, hydroxyl, carboxyl, an ester group, a boric acid group, a borate group, and a 3 to 7 membered ring substituted with one or more boric acid groups or borate groups, and at least one of Y1 and Y2 is a boron-containing group. The compound has the characteristics of a high fluorescence intensity and a high sensitivity.
123455 is hydrogen or a protecting group for a carboxyl group; and B contains 10B. The method is simple, efficient, and high in yield, and the prepared radiolabeled boron-containing compound has high purity, can be used as an imaging agent for medical images, and can also be used as a drug for boron neutron capture therapy.
A method for preparing a lyophilized preparation of BPA includes a solution preparation process and a freeze-drying process, where the solution preparation process includes: (1) dissolving BPA and polyol in an aqueous solution by using a base to obtain a clear solution; (2) regulating the clear solution back to 7.5
A neutron capture therapy system includes an accelerator for accelerating charged particles to generate a charged particle beam, a beam transmitting device, and a neutron beam generating device. The neutron beam generating device further includes a first, a second and a third neutron beam generating device. The beam transmitting device further includes a first transmitting device connected to the accelerator, a beam direction conversion device configured to switch a traveling direction of the charged particle beam, and a second, a third and a fourth transmitting device that respectively transmit the charged particle beam from the beam direction conversion device to the first, the second and the third neutron beam generating device, wherein two of the first, the third and the fourth transmitting device define a first plane, a first and a second transmitting device define a second plane, and the first plane is different from the second plane.
C07B 59/00 - Introduction of isotopes of elements into organic compounds
C07C 229/34 - Compounds containing amino and carboxyl groups bound to the same carbon skeleton having amino and carboxyl groups bound to acyclic carbon atoms of the same carbon skeleton the carbon skeleton containing six-membered aromatic rings
C07C 249/02 - Preparation of compounds containing nitrogen atoms doubly-bound to a carbon skeleton of compounds containing imino groups
Disclosed is a moderator for moderating neutrons, including a substrate and a surface treatment layer or a dry inert gas layer or a vacuum layer coated on the surface of the substrate, wherein the substrate is prepared from a moderating material by a powder sintering device through a powder sintering process from powders or by compacting powders into a block, and the moderating material includes 40% to 100% by weight of aluminum fluoride; wherein the surface treatment layer is a hydrophobic material; and the surface treatment layer or the dry inert gas layer or the vacuum layer is used for isolating the substrate from the water in the environment in which the substrate is placed. The surface treated moderator can avoid the hygroscopic or deliquescence of the moderating material during use, improve the quality of the neutron source and prolong the service life.
C04B 35/553 - Shaped ceramic products characterised by their composition; Ceramic compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on non-oxides based on fluorides
A neutron capture therapy system includes a neutron beam generating unit, an irradiation room configured to irradiate an irradiated body with a neutron beam, a preparation room configured to implement preparation work required to irradiate the irradiated body with the neutron beam, and an auxiliary positioner disposed in the irradiation room and/or the preparation room. The irradiation room includes a first shielding wall, a collimator is disposed on the first shielding wall for emitting the neutron beam, and the neutron beam is emitted from the collimator and defines a neutron beam axis. The auxiliary positioner includes a laser emitter that emits a laser beam to position the irradiated body, wherein the position of the laser emitter is selectable. Therefore, the irradiated body can be positioned in any case to implement precise irradiation.
Disclosed is a method for preparing a BPA lyophilized preparation, comprising a solution formulating process and a freeze drying process; wherein the solution formulating process comprises: (1) dissolving BPA and a polyol in an aqueous solution by means of a base to obtain a clear solution; and (2) adjusting the clear solution back to 7.5 < pH ≤ 8.5 by means of an acid to obtain a BPA solution; and the freeze drying process comprises: (3) sub-packaging the BPA solution and freeze drying same under the conditions of a vacuum degree of 10-20 Pa to obtain the lyophilized preparation. The BPA lyophilized preparation prepared by means of the method has a good stability and a low impurity content.
C09B 23/08 - Methine or polymethine dyes, e.g. cyanine dyes characterised by the methine chain containing an odd number of CH groups more than three CH groups, e.g. polycarbocyanines
A neutron capture therapy system, including a beam shaping assembly and a vacuum tube. The beam shaping assembly includes a beam entrance, an accommodating cavity accommodating the vacuum tube, a moderator adjacent to an end of the accommodating cavity, a reflector surrounding the moderator, a radiation shield disposed in the beam shaping assembly, and a beam exit. A target is disposed at an end of the vacuum tube, nuclear reactions occur between the target and a charged particle beam entering through the beam entrance to generate neutrons. The moderator moderates the neutrons, the reflector guides deflected neutrons back to the moderator. The moderator at least includes two cylindrical moderating members with different outer diameters respectively, the moderator has a first end close to the beam entrance and a second end close to the beam exit, and the target is accommodated between the first end and the second end.
The present disclosure provides a neutron capture therapy system, including a neutron generator to generate neutrons after irradiation by charged particles, and a beam shaping assembly includes a moderator and a reflector surrounding the moderator. A vacuum tube connected to the accelerator is provided at an accommodating portion. The vacuum tube transmits the charged particles accelerated by the accelerator to the neutron generator to generate neutrons. The neutron generator moves between a first position and a second position, at the first position, the neutron generator react with the charged particle beam to generate neutrons, at the second position, the neutron generator falls off the beam shaping assembly. The vacuum tube is detached to make the neutron generator fall off the beam shaping assembly, to reduce direct contact of a worker with the neutron generator after nuclear reactions, thereby reducing radioactive hazards for workers.
A neutron capture therapy system includes an accelerator for generating a charged particle beam, a neutron generator for generating a neutron beam having neutrons after irradiation by the charged particle beam, and a beam shaping assembly for shaping the neutron beam. The beam shaping assembly includes a moderator and a reflecting assembly surrounding the moderator. The neutron generator generates the neutrons after irradiation by the charged particle beam. The moderator moderates the neutrons generated by the neutron generator to a preset energy spectrum. The reflecting assembly includes a plurality of reflectors configured to guide deflected neutrons back to the neutron beam and a supporting member to support the plurality of reflectors. A lead-antimony alloy is for the reflecting assembly to mitigate a creep effect that occurs when only a lead material is for the plurality of reflectors, thereby improving the structural strength of a beam shaping assembly.
A neutron capture therapy system includes an accelerator for accelerating charged particles to generate a charged particle beam, a beam transmitting device, and a neutron beam generating device. The neutron beam generating device further includes a first, a second and a third neutron beam generating device. The beam transmitting device further includes a first transmitting device connected to the accelerator, a beam direction conversion device configured to switch a traveling direction of the charged particle beam, and a second, a third and a fourth transmitting device that respectively transmit the charged particle beam from the beam direction conversion device to the first, the second and the third neutron beam generating device, wherein two of the first, the third and the fourth transmitting device define a first plane, a first and a second transmitting device define a second plane, and the first plane is different from the second plane.
A neutron capture therapy system, including a beam shaping assembly, and a vacuum tube and at least one cooling device. The beam shaping assembly includes a beam inlet, an accommodating cavity accommodating the vacuum tube, a moderator adjacent to an end portion of the accommodation cavity, a reflector surrounding the moderator, and a radiation shield and a beam outlet arranged in the beam shaping assembly. An end portion of the vacuum tube is provided with a target. The cooling device undergoes a nuclear reaction with a charged particle beam incident from the beam inlet to produce neutrons. The moderator decelerates the neutrons produced by the target to an epithermal neutron energy region. The reflector leads deviating neutrons back to the moderator. At least one accommodating pipeline accommodating the cooling device is arranged in the beam shaping assembly. A filler is filled between the cooling device and the accommodating pipeline.
Provided are a method for preparing 18F-BPA and an intermediate. High-purity 18F-BPA can be obtained by means of the method, which simplifies synthesis steps after 18F labeling, with simple operation and high efficiency.
C07C 229/36 - Compounds containing amino and carboxyl groups bound to the same carbon skeleton having amino and carboxyl groups bound to acyclic carbon atoms of the same carbon skeleton the carbon skeleton containing six-membered aromatic rings with at least one amino group and one carboxyl group bound to the same carbon atom of the carbon skeleton
C07C 251/24 - Compounds containing nitrogen atoms doubly- bound to a carbon skeleton containing imino groups having carbon atoms of imino groups bound to carbon atoms of six-membered aromatic rings
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, 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 material of the moderator is subjected to a powder sintering process using a powder sintering device so as to change powders or a power compact into blocks. 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.
C04B 35/553 - Shaped ceramic products characterised by their composition; Ceramic compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on non-oxides based on fluorides
A method for measuring radiation intensity includes measuring the radiation intensity received by the protein in a radiation field based on degree of protein degradation in the radiation field, wherein the degree of degradation is a ratio of the molecular weight of the protein before and after irradiation. The measuring method is simple in operation, small in number of steps, small in error, and capable of measuring radiation doses of various radiation fields or even mixed radiation fields. Use of a biological dosimeter for measuring the radiation intensity by the method in a neutron capture therapy system can not only assess radiation contamination in the irradiation chamber, but also evaluate the neutron dose.
A boron neutron capture therapy system includes a neutron capture therapy device, a photon emission detection device and a treatment bed. The photon emission detection device includes a detecting portion surrounding the periphery of the treatment bed and detecting gamma rays generated after irradiating a boron-containing drug with neutrons; the detecting portion includes a first detecting portion and a second detecting portion moving away from or close to the first detecting portion so that the detecting portion forms a ring with the radius being increased or decreased; and the ring surrounds the treatment bed. The photon emission detection device for use in the boron neutron capture therapy system can change the radius of the ring, surrounding an irradiated object, of the detecting portion according to the actual condition in the boron neutron capture therapy so as to improve the detection precision of the photon emission detection device.
A neutron capture therapy system and a target for a particle beam generating device, which may improve the heat dissipation performance of the target, reduce blistering and extend the service life of the target. The neutron capture therapy system includes a neutron generating device and a beam shaping assembly. The neutron generating device includes an accelerator and a target, and a charged particle beam generated by acceleration of the accelerator interacts with the target to generate a neutron beam. The target includes an acting layer, a backing layer and a heat dissipating layer, the acting layer interacts with the charged particle beam to generate the neutron beam, the base layer supports the action layer, and the heat dissipating layer includes a tubular member composed of tubes arranged side by side.
G21G 1/06 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by neutron irradiation
G21G 1/10 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by bombardment with electrically-charged particles
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
A beam shaping assembly (10) used in a neutron capture system and capable of changing an irradiation range of a neutron beam. The beam shaping assembly includes: a beam inlet (11), a target (12), a moderator (13) adjoining the target (12), a reflector (14) surrounding the moderator (13), a thermal neutron absorber (15) adjoining the moderator (13), a radiation shield (16) arranged inside the beam shaping assembly (10), and a beam outlet (17). The beam shaping assembly (10) further includes replacement components (21, 22) that can be attached to and detached from the beam shaping assembly (10) to change the irradiation range of the neutron beam.
A process for analyzing elements and mass ratios of elements of a tissue includes approximating the tissue having unknown elements and mass ratios of the unknown elements thereof using the data of the medical image corresponding to a tissue having known elements and mass ratios of the known elements thereof. A method for establishing a geometric model based on a medical image includes: reading data of the medical image; defining a type of a tissue according to a conversion relationship between the data of the medical image and tissue types or according to the process; determining a quantity of tissue clusters of the tissue; defining a tissue density of the tissue by a conversion relationship between the data of the medical image and density values; establishing a 3D coding matrix with information about the tissue and the density; and generating the geometric model.
In one aspect, a method for establishing a smooth geometric model based on data of a medical image includes: inputting or reading the data of the medical image; establishing a three-dimensional medical image voxel model based on the data of the medical image; smoothing the three-dimensional medical image voxel model; and establishing a three-dimensional voxel phantom tissue model based on the smoothed three-dimensional medical image voxel model. In another aspect, a method for establishing a smooth geometric model based on data of a medical image includes: inputting or reading the data of the medical image; establishing a three-dimensional voxel phantom tissue model based on the data of the medical image; and smoothing the three-dimensional voxel phantom tissue model.
The present disclosure provides a positioning assembly for a radiation irradiation system. The positioning assembly includes a shielding body made of polymer and radiation shielding material capable of shielding the radiation and a sealing bag for accommodating the shielding body, when the target to be irradiated is placed on the positioning assembly, the positioning assembly is recessed with a shape of the target at the position where the target is placed and forms a contour corresponding to the target to position the target to be irradiated.
G21F 3/00 - Shielding characterised by its physical form, e.g. granules, or shape of the material
G21F 1/02 - Selection of uniform shielding materials
A61B 90/00 - Instruments, implements or accessories specially adapted for surgery or diagnosis and not covered by any of the groups , e.g. for luxation treatment or for protecting wound edges
A61B 90/10 - Instruments, implements or accessories specially adapted for surgery or diagnosis and not covered by any of the groups , e.g. for luxation treatment or for protecting wound edges for stereotaxic surgery, e.g. frame-based stereotaxis
The present disclosure provides a neutron capture therapy system. The neutron capture therapy system includes an accelerator, the accelerator generates a charged particle beam; a neutron generator, the neutron generator generates a neutron beam after being irradiated by the charged particle beam; a beam shaping assembly, the beam shaping assembly includes a moderator and a reflector surrounds around the outer periphery of the moderator, the moderator moderates the neutrons generated by the neutron generator to a preset spectrum, and the reflector leads the deflected neutrons back to increase the neutron intensity within the preset spectrum; and a collimator, the collimator concentrates the neutrons generated by the neutron generator; the spectrum of the neutron beam is changed by changing the spectrum of the charged particle beam.
H05H 6/00 - Targets for producing nuclear reactions
G21K 1/06 - Arrangements for handling particles or ionising radiation, e.g. focusing or moderating using diffraction, refraction, or reflection, e.g. monochromators
The application provides a neutron capture therapy system. The neutron capture therapy system comprises: a neutron generation part; an irradiation chamber; a preparation chamber; and an auxiliary position-locating device provided within the irradiation chamber and the preparation chamber. The neutron beam generation part comprises: an accelerator for accelerating a charged particle beam; a neutron beam generating portion for reacting with the charged particle beam to generate a neutron beam; and a charged particle beam transmitting portion located between the accelerator and the neutron beam generating portion and used to transmit the charged particle beam. The irradiation chamber is a room for irradiating an irradiated subject with the neutron beam. The preparation chamber is a room for performing preparation tasks required before irradiating the irradiated subject with the neutron beam. The auxiliary position-locating device is provided with a laser emitter for emitting a laser beam to locate the position of the irradiated subject. The position of the laser emitter is selectable to realize position-locating of the irradiated subject under any circumstances, achieving precise irradiation.
The present application provides a neutron capture treatment system, comprising a beam shaping body and a vacuum tube arranged in the beam shaping body, wherein the beam shaping body comprises a beam inlet, a receiving chamber for accommodating the vacuum tube, a retarding body adjacent to the end of the receiving chamber, a reflector surrounded by the retarding body, a radiation shield arranged inside the beam shaping body, and a beam exit, the end of the vacuum tube is provided with a target material, the target material reacts with a charged particle beam incident from the beam inlet to generate neutrons, the neutrons then form a neutron beam, and the neutron beam exits the beam exit and defines a neutron beam axis, the retarding body decelerates the neutrons generated from the target material to a superheated neutron energy region, the reflector guides deviated neutrons back to the retarding body, the radiation shield is used to shield leaking neutrons and photons, the retarding body comprises at least two cylindrical retarding bodies having different outer diameters, the retarding body has a first end adjacent the beam inlet and a second end adjacent the beam exit, and the target material is received between the first end and the second end.
A neutron capture treatment system (100), comprising an accelerator (200) for use in generating a charged particle beam (P), a neutron generating portion (10) that reacts with the charged particle beam (P) to generate a neutron beam (N), and a beam shaping body (20); the beam shaping body (20) comprises an accommodating portion (21), a speed reducing body (22), a reflecting body (23), a thermal neutron absorbing body (24), a radiation shield (25) and a beam exit port (26); the accommodating portion (21) is provided with a vacuum tube (30) that is connected to the accelerator (200), the vacuum tube (30) transmitting the charged particle beam (P) that is accelerated by the accelerator (200) to the neutron generating portion (10) such that the neutron generating portion (10) and the charged particle beam (P) generate neutrons; the neutron generating portion (10) moves between a first position and a second position, and in the first position, the neutron generating portion (10) may react with the charged particle beam (P) to generate neutrons, while, in the second position, the neutron generating portion (10) detaches from the beam shaping body (20), which is to say that disassembling a part of the vacuum tube (30) that is provided with the neutron generating portion (10) causes the neutron generating portion (10) to detach from the beam shaping body (20), thereby reducing the direct contact between workers and the generating portion (10) following a nuclear reaction, and reducing radiation safety hazards for the workers.
The present disclosure provides a beam shaping assembly for neutron capture therapy, wherein the beam shaping assembly includes a neutron generating device, a moderator, a disturbing unit and a beam outlet. The neutron generating device is used to generate neutrons that form a neutron beam in a direction from the neutron generating device to the beam outlet, the moderator adjacent to the neutron generating device for adjusting fast neutrons in the neutron beam to epithermal neutrons. The disturbing unit is located between the moderator and the beam outlet for passing through the neutron beam and reducing the gamma ray content in the neutron beam passing through the beam outlet. The technical solution provided by the present disclosure can effectively reduce the gamma ray content in the neutron beam under the premise that the quality of the neutron beam is not significantly adversely affected.
A medical image-based radiation shielding device and method thereof, which may form a targeted and highly accurate radiation shielding according to individual differences in patients, such as tumor location and size, thereby reduce or avoid radiation from a irradiation apparatus to normal tissues of patients. The shielding device includes a medical image scanning means for scanning an irradiated site of an irradiated subject and outputting medical image voxel data, a data processing and three-dimensional modeling means for establishing a three-dimensional phantom tissue model according to the medical image voxel data and establishing a three-dimensional shield model according to the three-dimensional phantom tissue model; a shield located between the irradiation apparatus and the irradiated site, wherein the shield is formed by printing the three-dimensional shield model data input to a 3D printer.
B33Y 30/00 - ADDITIVE MANUFACTURING, i.e. MANUFACTURING OF THREE-DIMENSIONAL [3D] OBJECTS BY ADDITIVE DEPOSITION, ADDITIVE AGGLOMERATION OR ADDITIVE LAYERING, e.g. BY 3D PRINTING, STEREOLITHOGRAPHY OR SELECTIVE LASER SINTERING - Details thereof or accessories therefor
B33Y 50/02 - Data acquisition or data processing for additive manufacturing for controlling or regulating additive manufacturing processes
B33Y 80/00 - Products made by additive manufacturing
In order to provide a neutron therapy apparatus which give multi angles neutron beam irradiation, the neutron therapy apparatus includes: a beam shaping assembly including a moderator and a reflector surrounding the moderator, wherein the moderator moderates neutrons to a predetermined energy spectrum and the reflector guides deflected neutrons back to enhance the neutron intensity in the predetermined energy spectrum; a neutron generator embedded inside the beam shaping assembly, wherein the neutron generator generates neutrons after irradiated by an ion beam; at least a tube for transmitting the ion beam to the neutron generator, wherein the tube defines at least an axis; deflection magnets for changing the transmission direction of the ion beam; a collimator for concentrating neutrons; and an irradiation room for receiving a irradiated object, wherein the beam shaping assembly rotates around the axis of the tube.
In order to provide a neutron therapy apparatus which give multi angles neutron beam irradiation, the neutron therapy apparatus includes: a beam shaping assembly including a moderator and a reflector surrounding the moderator, wherein the moderator moderates neutrons to a predetermined energy spectrum and the reflector guides deflected neutrons back to enhance the neutron intensity in the predetermined energy spectrum; a neutron generator embedded inside the beam shaping assembly, wherein the neutron generator generates neutrons after irradiated by an ion beam; and an irradiation room for receiving a irradiated object, a shielding assembly connected to the beam shaping assembly, wherein the shielding assembly moves together with the beam shaping assembly and shields the radioactive rays leaked from the beam shaping assembly all the time.
Provided is a neutron capture therapy system, wherein same can effectively use a space and perform therapy on a plurality of patients at the same time, and same does not excessively prolong the route of beam transmission and has a relatively small loss. The neutron capture therapy system in the present invention comprises an accelerator accelerating charged particles to generate charged particle beams, a beam transmission part transmitting the charged particle beams generated by the accelerator to a neutron beam generation part, and the neutron beam generation part generating neutron beams for performing therapy, wherein the neutron beam generation part comprises first, second and third neutron beam generation parts; the beam transmission part comprises a first transmission part connected to the accelerator, a beam direction switcher switching a direction of travel of the charged particle beams, and second, third and fourth transmission parts respectively transmitting the charged particle beams from the beam direction switcher to the first, second and third neutron beam generation parts; two of the first, third and fourth transmission parts define a first plane; the first and second transmission parts define a second plane; and the first plane is different from the second plane.
Provided is a neutron capture therapy system, comprising a beam-shaping body, and a vacuum tube and at least one cooling device, which are arranged in the beam-shaping body, wherein the beam-shaping body comprises a beam inlet, an accommodation cavity accommodating the vacuum tube, a retarder, which is adjacent to an end portion of the accommodation cavity, a reflector surrounding the retarder, and a radiation shield and a beam outlet arranged in the beam-shaping body; an end portion of the vacuum tube is provided with a target material; the cooling device is used for cooling the target material; the target material undergoes a nuclear reaction with a charged particle beam incident from the beam inlet so as to produce neutrons; the retarder decelerates the neutrons produced by the target material to an epithermal neutron energy region; the reflector leads deviating neutrons back to the retarder to enhance the intensity of an epithermal neutron beam; at least one accommodation pipeline accommodating the cooling device is further arranged in the beam-shaping body; and a filler is filled between the cooling device and an inner wall of the accommodation pipeline.
11C, the compound can also be used in conjunction with PET/CT for determining the part of the brain where amyloid β-protein is deposited, for diagnosing Alzheimer's disease. Also disclosed is a preparation process for the compound. The beneficial effect of the present disclosure is to make the therapy and diagnosis of Alzheimer's disease more targeted by providing the compound for specifically binding to amyloid β-protein.
A61P 25/28 - Drugs for disorders of the nervous system for treating neurodegenerative disorders of the central nervous system, e.g. nootropic agents, cognition enhancers, drugs for treating Alzheimer's disease or other forms of dementia
G01N 33/68 - Chemical analysis of biological material, e.g. blood, urine; Testing involving biospecific ligand binding methods; Immunological testing involving proteins, peptides or amino acids
A61K 41/00 - Medicinal preparations obtained by treating materials with wave energy or particle radiation
The present application provides a neutron capture therapy system. The neutron capture therapy system comprises an accelerator for generating a charged particle beam, a neutron generating portion for generating a neutron beam after irradiation by the charged particle beam, and a beam shaping body for shaping the neutron beam. The beam shaping body comprises a retarding body and a reflecting portion coated on the periphery of the retarding body. The neutron generating portion generates neutrons after irradiation by the charged particle beam. The retarding body decelerates, to a preset energy spectrum, the neutrons generated by the neutron generating portion. The reflecting portion comprises a reflecting body capable of guiding deviated neutrons to increase neutron intensity in the preset energy spectrum and a supporting member capable of supporting the reflecting body. By using a lead-antimony alloy as the reflecting body, thus improving on the creep effect that arises from using only a lead material, structural strength of the beam shaping body is improved.
Disclosed is a moderator for moderating neutrons, comprising a substrate (402) and a surface treatment layer (401) or a dry inert gas layer or a vacuum layer coated on the surface of the substrate (402), wherein the substrate (402) is prepared from a moderating material through a powder sintering process by using a powder sintering device so as to change powders or powder compacts into blocks, and the moderating material comprises 40%-100% parts by weight of aluminium fluoride; the surface treatment layer (401) is a hydrophobic material; and the surface treatment layer (401) or the dry inert gas layer or vacuum layer is used for isolating the substrate (402) from the water in the environment where the substrate (402) is located. The surface treated moderator can avoid the hygroscopic deliquescence of the moderating material during use, improve the quality of the neutron source and prolong the service life thereof.
A method for measuring radiation intensity, comprising: measuring, according to a degradation degree of protein in a radiation field, radiation intensity accepted by the protein in the radiation field, wherein the degradation degree is the ratio of a molecular weight of the protein before being irradiated by radiation rays to after being irradiated by the radiation rays. The measurement method is simple to operate, and can measure radiation dosage of many kinds of radiation fields, even a mixed radiation field.
The present invention provides a neutron capture therapy (NCT) system and a target material for use with a particle beam production device, capable of increasing heat dissipation capabilities of the target material, reducing bubbling, and increasing the lifespan of the target material. The NCT system disclosed by the present invention comprises a neutron production device and a radiation beam shaping component. The neutron production device comprises an accelerator and a target material, wherein acceleration of the accelerator electrically charges a particle beam, and a neutron beam is produced by interaction thereof with the target material. The target material comprises an active layer, a base layer, and a heat dissipation layer, wherein the interaction between the active layer and the electrically charged particle beam produces a neutron beam, the base layer supports the active layer, and the heat dissipation layer comprises a winding cooling channel.
Provided are a method for measuring dose distribution in a mixed radiation field of neutrons and gamma rays, and a method for measuring beam uniformity of a mixed radiation field of neutrons and gamma rays. The planar dose measuring method includes: a step of obtaining a total dose of neutrons and gamma rays by measuring with a dosimeter; and a step of analyzing a neutron dose. The method may effectively measure the doses of neutrons and gamma rays, may be applied to beam measurement and treatment plan validation, and thus improve the quality of treatment.
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 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.
A neutron capture therapy system capable of eliminating amyloid β-protein includes a neutron capture therapy device and a compound capable of specifically binding to the amyloid β-protein having a nuclide with a large thermal neutron capture cross section. The neutron capture therapy device includes a neutron source, a beam shaping assembly and a collimator, the neutrons released by the neutron source pass through the beam shaping assembly and are slowed into a neutron beam within a certain energy range. The neutron beam irradiates the compound, and the energy generated by the reaction thereof can destroy the structure of the amyloid β-protein. The neutron capture therapy system can specifically eliminate the amyloid β-protein, and reduce the damage to the tissues surrounding the amyloid β-protein.
A beam shaping assembly (10) used in a neutron capture system and capable of changing an irradiation range of a neutron beam. The beam shaping assembly comprises: a beam inlet (11), a target (12), a moderator (13) adjoining the target (12), a reflector (14) surrounding the moderator (13), a thermal neutron absorber (15) adjoining the moderator (13), a radiation shield (16) arranged inside the beam shaping assembly (10), and a beam outlet (17). The target (12) has a nuclear reaction with an incident proton beam from the beam inlet (11) to produce neutrons, the neutrons form a neutron beam, and the neutron beam defines a main axis (X); the moderator (13) moderates the neutrons produced from the target (12) to an epithermal neutron energy range; the reflector (14) leads the neutrons deviated from the main axis (X) back to the main axis (X) so as to achieve the effect of converging epithermal neutrons; the thermal neutron absorber (15) is used for absorbing thermal neutrons to avoid overdosing in superficial normal tissue during therapy; the radiation shield (16) is used for shielding leaking neutrons and photons, so as to reduce the dose of the normal tissue of a non-irradiated area; and the beam shaping assembly (10) further comprises replacement components (21, 22) that can be attached to and detached from the beam shaping assembly (10) to change the irradiation range of the neutron beam.
A boron neutron capture therapy system, comprising a neutron capture therapy device (100), a photon emission detection device (200), and a therapy bed (300). Neutrons are irradiated by a born-containing (10B) medicine and then produce gamma rays; the photon emission detection device (200) comprises a detection portion (201) surrounding the periphery of the therapy bed (300) and detecting the gamma rays produced by the neutrons irradiated by the born-containing (10B) medicine; the detection portion (201) comprises a first detection portion (202) and a second detection portion (203); the first detection portion (202) and the second detection portion (203) can be distant from or close to each other so that the detection portion (201) can form a ring with the radius being increased or decreased; and the ring surrounds the therapy bed (300). The photon emission detection device (200) for use in the boron neutron capture therapy system can change the radius of the ring, surrounding an irradiated object, of the detection portion (201) according to the actual condition in the boron neutron capture therapy so as to improve the detection precision of the photon emission detection device (200).
A radiation detection system and method for a neutron capture therapy system, which may increase the accuracy of neutron beam irradiation dose of the neutron capture therapy system and find out a fault position in time. The neutron capture therapy system includes a charged particle beam, a charged particle beam inlet allowing the charged particle beam to pass through, a neutron beam generating unit which may generate a neutron beam after a nuclear reaction occurs between the neutron beam generating unit and the charged particle beam, a beam shaping assembly for adjusting the flux and the quality of the neutron beam generated by the neutron beam generating unit, and a beam outlet adjacent to the beam shaping assembly, the radiation detection system includes a radiation detection device for real-time detection of γ rays instantly emitted under neutron beam irradiation.
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.
11C, the compound can also be used in conjunction with PET/CT for determining the part of the brain where amyloid β-protein is deposited, for diagnosing Alzheimer's disease. Also disclosed is a preparation process for the compound. The beneficial effect of the present disclosure is to make the therapy and diagnosis of Alzheimer's disease more targeted by providing the compound for specifically binding to amyloid β-protein.
A radiation irradiation system comprises a radiation irradiation device and a therapeutic bed (300) for transporting a target to be irradiated to the radiation irradiation device for irradiation. The therapeutic bed (300) comprises a positioning component (52). The positioning component (52) comprises a shielding body (54) and a sealing bag (53) for accommodating the shielding body (54). The shielding body (54) comprises silicone and a radiation shielding material which is capable of shielding a radiation. When the positioning component (52) with the target to be irradiated being placed on the surface of the sealing bag (53) is vacuumized, the positioning component (52) is recessed with the shape of the target to be irradiated at the position where the target to be irradiated is placed to form the same contour as the target to be irradiated, so as to position the target to be irradiated. The positioning component (52) is provided to position the target to be irradiated to avoid therapeutic effect differences caused by movement of the target to be irradiated during an irradiation therapy process, and avoid radioactive damages of radiation to parts of the target to be irradiated except for the parts on which irradiation therapy needs to be performed, and to medical staffs during the radiation irradiation therapy process.
Disclosed is a method for evaluating an irradiation angle of a beam, including a step of sampling the irradiation angle of the beam, wherein the irradiation angle of the beam is defined as being the direction of the vector of the irradiation point of the beam to the pre-set point of the tumor; and a step of calculating the track of the beam passing through the organs, wherein it is determined whether the tumor is fully covered within the effective treatment depth, and if so, entering the steps of calculating the evaluation coefficient, recording the irradiation conditions and calculating the results, and returning to the step of sampling the irradiation angle of the beam; and if not, entering the step of giving the worst evaluation coefficient and returning to the step of sampling the irradiation angle of the beam.
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.
G21K 1/06 - Arrangements for handling particles or ionising radiation, e.g. focusing or moderating using diffraction, refraction, or reflection, e.g. monochromators
G21K 1/12 - Resonant absorbers or driving arrangements therefor, e.g. for Mössbauer-effect devices
H05H 7/12 - Arrangements for varying final energy of beam
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.
Provided is a geometric model establishment method based on medical image data, including: a step of reading medical image data; a step of defining a tissue type by a conversion relationship between the medical image data and the tissue type; a step of deciding the number of tissue clusters; a step of defining a tissue density by a conversion relationship between the medical image data and the density; a step of establishing 3D encoding matrix with information about the tissue and the density; and a step of generating a geometric model. According to a conversion relationship between medical image data and a tissue type, the number of tissue clusters can be determined according to actual requirements, so that the tissue type, the element composition and the density are provided more accurately, and an established geometric model is better matched to the real situation reflected by the medical image data.
A medical image-based method for deconstructing a tissue element mass ratio and a method for establishing a geometric model. The method for deconstructing the tissue element mass ratio comprises: a step of approximating an element mass ratio of a tissue corresponding to unknown medical image data by means of medical image data corresponding to a tissue with a known element mass ratio. The method for establishing the geometric model comprises steps of: reading the medical image; defining the type of a tissue according to the method for deconstructing the tissue element mass ratio; deciding tissue grouping number; defining a tissue density by means of the conversion relation between the medical image and density; establishing a 3D encoding matrix carrying tissue and density information; and generating the geometric model. Deconstructing an organism tissue element mass ratio by means of the medical image data of a known tissue to be better approximated by the real situation when making voxel prosthesis can increase dose calculation accuracy and improve treatment quality.
G06F 19/00 - Digital computing or data processing equipment or methods, specially adapted for specific applications (specially adapted for specific functions G06F 17/00;data processing systems or methods specially adapted for administrative, commercial, financial, managerial, supervisory or forecasting purposes G06Q;healthcare informatics G16H)
A medical image data-based method for establishing a smooth geometric model, comprising: inputting or reading medical image data; establishing a three-dimensional medical image voxel model according to the medical image data, smoothing the three-dimensional medical image voxel model, and establishing a three-dimensional voxel prosthesis tissue model; or establishing the three-dimensional voxel prosthesis tissue model according to the medical image data, and smoothing the three-dimensional voxel prosthesis tissue model. Smoothing the three-dimensional medical image voxel model or the three-dimensional voxel prosthesis tissue model on the basis of the medical image data-based method for establishing a smooth geometric model enables a model to be closer to the real situation of a human organ, so that the dose calculation reliability can be improved, thereby improving the treatment quality.
G06F 19/00 - Digital computing or data processing equipment or methods, specially adapted for specific applications (specially adapted for specific functions G06F 17/00;data processing systems or methods specially adapted for administrative, commercial, financial, managerial, supervisory or forecasting purposes G06Q;healthcare informatics G16H)
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.
A neutron capturing therapy system (100) and a target material (T) for use in a neutron generating device (10), capable of increasing the heat dissipation performance of the target material (T), reducing foaming, and extending the service life of the target material (T). The neutron capturing therapy system (100) comprises the neutron generating device (10) and a beam shaper (20). The neutron generating device (10) comprises an accelerator (11) and the target material (T). An electrically charged particle beam (P) accelerated and generated by the accelerator (11) interacts with the target material (T) to generate a neutron beam (N). The target material (T) comprises an acting layer (14), a base layer (13), and a heat dissipating layer (12). The acting layer (14) interacts with the electrically charged particle beam (P) to generate the neutron beam (N). The base layer (13) supports the action layer (14). The heat dissipating layer (12) comprises a pipe-shaped element (121) consisting of multiple pipes arranged side by side.
Provided is a beam diagnostic system for a neutron capture therapy system. The neutron capture therapy system includes a charged particle beam, a charged particle beam inlet for passing the charged particle beam, a neutron generating unit generating a neutron beam by a nuclear reaction with the charged particle beam, and a beam shaping assembly for adjusting flux and quality of the neutron beam generated by the neutron generating unit and a beam outlet adjoining to the beam shaping assembly. The charged particle beam inlet is accommodated into the beam shaping assembly and the neutron generating unit is accommodated in the beam shaping assembly. The beam diagnostic system includes a charged particle beam diagnostic device and a neutron beam diagnostic device, and the beam diagnostic system is used to simultaneously diagnose whether the neutron capture therapy system and/or the beam diagnostic system is malfunctioning.
2 group represents a protecting group;
2 group of the N-protected (S)-4-boronophenylalanine to obtain L-BPA, wherein the L-BPA has a structure of Formula III.
The present invention provides a medical image-based radiation shielding device and method, capable of forming targeted and high-precision radiation shielding according to the individual differences of a patient, such as the position and size of a tumor, so as to reduce or avoid radiation of a radiation irradiation device to normal tissue of the patient. The shielding device of the present invention comprises: a medical image scanning unit that scans an irradiation site of an irradiation target and outputs medical image voxel data; a data processing and three-dimensional modeling unit for establishing a three-dimensional prosthesis tissue model according to the medical image voxel data and establishing a three-dimensional shielding body model according to the three-dimensional prosthesis tissue model; and a shielding body formed by printing the three-dimensional shielding body model data input to a 3D printer, the shielding body being located between the radiation irradiation device and the irradiation site.
A neutron capture therapy system (100), comprising: an accelerator (200) used for producing a charged particle beam P; a neutron production part (10) used for producing a neutron beam after being irradiated by the charged particle beam P; a beam shaping body (11); and a collimator (12); the beam shaping body (11) comprises a retarding body (13) and a reflecting body (14) cladded at periphery of the retarding body (13); the neutron production part (10) are irradiated by the charged particle beam P to produce neutrons; the retarding body (13) decelerates the neutrons produced by the neutron production part (10) to a preset energy spectrum; the reflecting body (14) reflects back deflected neutrons to improve the neutron intensity in the preset energy spectrum; the collimator (12) performs concentrated irradiation on the neutrons produced by the neutron production part (10); in the process of neutron-capture therapy, the neutron-capture therapy system (100) changes energy of the neutron beam N produced by irradiating the neutron production part (10) by changing the energy of the charged particle beam P.
A beam shaping body (100, 200) for neutron capture therapy, comprising a neutron production device (110, 210), a retarding body (120, 220), a disturbing element (130, 230), and a beam outlet (140, 240); the neutron production device (110, 210) is used for producing neutrons; the neutrons are formed into a neutron beam (160) in the direction from the neutron production device (110, 210) to the beam outlet (140, 240); the retarding body (120, 220) is next to the neutron production device (110, 210) and is used for adjusting fast neutrons in the neutron beam (160) into epithermal neutrons; gamma rays are produced in the neutron production process and in the process of adjusting a neutron beam energy spectrum by the retarding body (120, 220); the disturbing element (130, 230) is located between the retarding body (120, 220) and the beam outlet (140, 240) for passing through the neutron beam (160) and reducing the content of gamma rays in the neutron beam (160) passing through the beam outlet (140, 240).
A shielding material for shielding radioactive ray and preparation method thereof. The shielding material consists of water, a cementing material, a fine aggregate material, a coarse aggregate material and an additive, wherein the fine aggregate material consists of a borosilicate glass powder and a barite sand, and the coarse aggregate material consists of a barite. A content of boron element in the borosilicate glass powder accounts for 0.5%-1% of the total weight of the shielding material. A content of barium sulfate in the barite sand and the barite accounts for 71%-75% of the total weight of the shielding material. Other contents include water, the cementing material and the additive, and a sum of contents of all components is 100% total weight of the shielding material.
C04B 28/02 - Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
C04B 103/30 - Water reducers, plasticisers, air-entrainers
C04B 111/00 - Function, property or use of the mortars, concrete or artificial stone
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.
A neutron therapy device (100), comprising a beam forming body (10), a neutron generating component (11) provided within the beam forming body (10), a tube (20) for transmitting an ion beam (P) to the neutron generating component (11), a deflection electromagnet (30) for changing a transmission direction of the ion beam (P), and a collimator (40). The beam forming body (10) comprises a decelerator (12) and a reflective body (13) disposed around the periphery of the decelerator (12). The neutron generating component (11) generates a neutron after being irradiated by the ion beam (P). The decelerator (12) decelerates the neutron generated by the neutron generating component (11) to a preset energy spectrum. The reflective body (13) returns a deviating neutron to increase the neutron intensity in the preset energy spectrum. The tube (20) has an axial line and the beam forming body (10) can rotate about the tube (20) to irradiate a body (M) to be irradiated from different angles. Owing to the configuration of a supporting frame (60), the beam forming body (10), and the deflection electromagnet (30), the neutron therapy device (100) needs only to rotate the structure thereof to enable the entire neutron therapy device (100) to perform irradiation from different angles. The device has a simple structure and convenient operations, and can be realized easily.
The present invention discloses a neutron therapy device, comprising a beam forming body, a neutron generating component provided within the beam forming body, a tube for transmitting an ion beam to the neutron generating component, a deflection electromagnet for changing a transmission direction of the ion beam, and a collimator. The beam forming body comprises a decelerator and a reflective body disposed around the periphery of the decelerator. The neutron generating component generates a neutron after being irradiated by the ion beam. The decelerator decelerates the neutron generated by the neutron generating component to an epithermal neutron energy range. The reflective body reflects a deviated neutron to increase the neutron intensity in the epithermal neutron energy range. The tube has an axial line and the beam forming body can rotate about the tube to irradiate a body to be irradiated from different angles. Owing to the configuration of a supporting frame, beam forming body and deflection electromagnet, the neutron therapy device needs only to rotate the structure thereof to enable the entire device to perform irradiation from different angles. The device has a simple structure and convenient operations, and can be realized easily.
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, 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 material of the moderator is subjected to a powder sintering process using a powder sintering device so as to change powders or a power compact into blocks. 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.
C04B 35/553 - Shaped ceramic products characterised by their composition; Ceramic compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on non-oxides based on fluorides
Disclosed are a method for measuring dose distribution in a mixed neutron and gamma radiation field, and a method for measuring the beam uniformity of a mixed neutron and gamma radiation field. The radiation dose measuring method is used for the mixed neutron and gamma radiation field. The planar dose measuring method comprises: the step of obtaining, by means of a dosimeter, the total dose of neutrons and gamma by means of measurement, and the step of analysing the dose of the neutrons. The method can effectively measure the dose of neutrons and gamma, can be applied to beam measurement and treatment plan verification, and thus improve the quality of treatment.
Provided is an application of a compound comprising 10B for preparing a pharmaceutical product specifically binding an amyloid β-protein. After the pharmaceutical product specifically binding the amyloid β-protein binds the amyloid β-protein, the pharmaceutical product can reduce or eliminate the amyloid β-protein when irradiated by a neutron beam generated by a neutron capture therapy device, thereby treating an Alzheimer's disease. The invention provides a novel method for treating the Alzheimer's disease.
C07D 207/04 - Heterocyclic compounds containing five-membered rings not condensed with other rings, with one nitrogen atom as the only ring hetero atom with only hydrogen or carbon atoms directly attached to the ring nitrogen atom having no double bonds between ring members or between ring members and non-ring members
C07D 207/02 - Heterocyclic compounds containing five-membered rings not condensed with other rings, with one nitrogen atom as the only ring hetero atom with only hydrogen or carbon atoms directly attached to the ring nitrogen atom
C07D 207/00 - Heterocyclic compounds containing five-membered rings not condensed with other rings, with one nitrogen atom as the only ring hetero atom
A61P 25/28 - Drugs for disorders of the nervous system for treating neurodegenerative disorders of the central nervous system, e.g. nootropic agents, cognition enhancers, drugs for treating Alzheimer's disease or other forms of dementia
75.
NEUTRON CAPTURE THERAPY SYSTEM FOR ELIMINATING AMYLOID Β-PROTEIN PLAQUE
A neutron capture therapy system for eliminating an amyloid β-protein plaque. The system comprises: a neutron capture therapy device and a compound comprising 10B, wherein the compound can specifically bind to an amyloid β-protein plaque. When a neutron beam generated by the neutron capture therapy device irradiates a 10B element, an energy generated by the irradiation can disrupt a structure of the amyloid β-protein plaque. The invention provides a benefit of effective and targeted destruction of an amyloid β-protein plaque.
A61P 25/28 - Drugs for disorders of the nervous system for treating neurodegenerative disorders of the central nervous system, e.g. nootropic agents, cognition enhancers, drugs for treating Alzheimer's disease or other forms of dementia
76.
BORON NEUTRON CAPTURE TREATINGSYSTEM AND APPLICATION OF Α-AMINO ACID-LIKE BORON TRIFLUORIDE INMANUFACTURING MEDICAMENT FOR TREATING TUMORS
As one aspect of the present invention, disclosed is a boron neutron capture therapy system, comprising: a boron neutron capture therapy device and an α-amino acid-like boron trifluoride; the α-amino acid-like boron trifluoride has a structure as shown in the formula (I) wherein R refers to hydrogen, methyl, isopropyl,1-methylpropyl, 2-methylpropyl, hydroxymethyl, 1-hydroxyethyl, benzylor hydroxybenzyl, and M refers to H or a metal atom; theenergy generated after a neutron beam generated by the boron neutron capture therapy device acts on the α-amino acid-like boron trifluoride can damage DNA of tumour cells. As another aspect of the present invention, disclosed also is the application of an α-amino acid-like boron trifluoride in manufacturing medicament for treating tumors.
Disclosed are a radiation ray detection system for a neutron capture therapy system and a method for detecting radiation rays. The radiation detection system and method can improve the accuracy of a neutron beam irradiation dose for a neutron capture therapy system and can detect a fault position in time, wherein the neutron capture therapy system comprises a charged particle beam (P), a charged particle beam entrance for passing the charged particle beam (P), a neutron generating part (T) generating the neutron beam (N) by means of a nuclear reaction with the charged particle beam (P), a beam shaper (30) for adjusting the beam flux and the quality of neutrons generated by the neutron generating part (T), and a beam exit (40) abutting the beam shaper (30), wherein the radiation ray detection system comprises a radiation ray detection device (800), and the radiation ray detection device (800) is used for real-time detection of the prompt gamma ray after irradiation with the neutron beam (N).
A beam shaper (10) for a neutron capture therapy. The neutron capture therapy comprises an accelerating tube (12) for accelerating a proton beam. The beam shaper (10) comprises a beam inlet (11), a target material (13) disposed in the accelerating tube (12), a retarder (14) adjoining to the target material (13), a reflector (15) surrounding the retarder (14), a thermal neutron absorber (16) adjoining to the retarder (14), and a radiation shied (17) and a beam outlet (18) disposed within the beam shaper (10). The beam shaper (10) is further provided with a cooling apparatus (20). The cooling apparatus (20) comprises a first cooling portion (21) for cooling the target material (13), and a second cooling portion (22) and a third cooling portion (23) extending respectively in a direction parallel to an axial direction of the accelerating tube (12) and in communication with the first cooling portion (21). The first cooling portion (21) is in plane contact with the target material (13). The second cooling portion (22) inputs a cooling medium into the first cooling portion (21), and the third cooling portion (23) outputs the cooling medium in the first cooling portion (21). The beam shaper (10) of the present invention cools a target material (13) by a cooling apparatus (20) disposed therein, and thus is simple in structure and easy to assemble.
A neutron capture therapy system capable of eliminating an amyloid β protein. Said system comprises a neutron capture therapy device and a compound that has a nuclide with a large capture cross section for a thermal neutron and is capable of specifically binding with an amyloid β protein. The neutron capture therapy device comprises a neutron source, a beam shaping body and a collimator. The neutrons released by the neutron source pass through the beam shaping body and are slowed into a neutron beam having energy within a certain range. The neutron beam irradiates the compound, and the energy generated by the reaction thereof is able to destroy the structure of the amyloid β protein. The neutron capture therapy system is able to specifically eliminate an amyloid β protein, and reduce the damage to the tissues surrounding the amyloid β protein.
Disclosed is a compound capable of specifically binding with β amyloid protein. The compound has thereon a nuclide having a large cross section for capturing thermal neutrons and the compound is capable of specifically binding with β amyloid protein. The nature of the compound allows same to be used in conjunction with a neutron capturing therapeutic apparatus to eliminate β amyloid protein. Similarly, when the compound is marked using radioactive element 11C, the compound can also be used in conjunction with PET/CT for determining the part of the brain at where β amyloid protein is deposited, thus being used for diagnosing Alzheimer's disease. Also disclosed is a preparation method for the compound. The beneficial effect of the present invention is such that the compound capable of specifically binding with β amyloid protein is provided, thus making the treatment and diagnosis of Alzheimer's disease more targeted.
Disclosed is a method for evaluating the irradiation angle of a beam, comprising a step of sampling the irradiation angle of the beam, wherein the irradiation angle of the beam is defined as being the direction of the vector of the irradiation point of the beam to the pre-set point of the tumour; and a step of calculating the track of the beam passing through the organs, wherein it is determined whether the tumour is fully covered within the effective treatment depth, and if so, entering the steps of calculating the evaluation coefficient, recording the irradiation conditions and calculating the results, and returning to the step of sampling the irradiation angle of the beam; and if not, entering the step of giving the worst evaluation coefficient and returning to the step of sampling the irradiation angle of the beam. According to the method for evaluating the irradiation angle of the beam, it can be clearly recognised whether the performance of the beam irradiating at a certain position and at a certain angle is good or bad, thus providing strong data support to allow doctors or physicists to decide on the irradiation mode.
In order to improve the flux and the quality of a neutron source, provided are beam shaping bodies (60 and 70) for neutron capture therapy, wherein the beam shaping bodies (60 and 70) comprise beam inlets (61 and 71), targets (62 and 72), retarding bodies (63 and 73) adjacent to the targets (62 and 72), reflecting bodies (64 and 74) surrounding the outside of the retarding bodies (63 and 73), thermal neutron absorbers (65 and 75) adjacent to the retarding bodies (63 and 73), and radiation shields (66 and 76) and beam outlets (67 and 77) provided in the beam shaping bodies (60 and 70). A nuclear reaction occurs between t targets (62 and 72) and proton beams entering from the beam inlets (61 and 71), so as to produce neutrons. The neutrons form a neutron beam. The neutron beam defines main axes (X6 ad X7). The retarding bodies (63 and 73) slow down the neutrons produced by the targets (62 and 72) when arriving at an epithermal neutron energy region. The retarding bodies (63 and 73) are designed to be in a shape containing at least one cone. The retarding bodies (63 and 73) have main bodies (631 and 731) and replenishing portions (632 and 732) surrounding the outside of the main bodies (631 and 731). The material of the replenishing portions (632 and 732) is different from that of the main bodies (631 and 731). The reflecting bodies (64 and 74) guide the neutrons deviating from the main axes back to the main axes (X6 and X7), so as to increase the strength of the epithermal neutron beam. The thermal neutron absorbers (65 and 75) are used for absorbing thermal neutrons, so as to prevent the thermal neutrons from causing an excessive dosage for a superficial normal tissue during therapy. The radiation shields (66 and 67) are used for blocking leaking neutrons and photons, so as to reduce the normal tissue dosage of a non-irradiated region.
Provided is a geometric model establishment method based on medical image data, comprising: a step of reading medical image data; a step of defining a tissue type by a conversion relationship between the medical image data and the tissue type; a step of deciding the number of tissue clusters; a step of defining a tissue density by a conversion relationship between the medical image data and the density; a step of establishing 3D encoding matrix with information about the tissue and the density; and a step of generating a geometric model. In addition, also comprised is a step of determining whether a medical image voxel is within an ROI boundary. According to a conversion relationship between medical image data and a tissue type, the number of tissue clusters can be determined according to actual requirements, so that the tissue type, the element composition and the density are provided more accurately, and an established geometric model is better matched to the real situation reflected by the medical image data.
A neutron capture therapy system, comprising a beam shaping body (10), which comprises a beam inlet (11), a neutron generator (12) provided in the beam shaping body (10), a moderator (13) adjacent to the neutron generator (12), a reflector body (14) surrounding the moderator (13) and a beam outlet (15); the neutron generator (12) and a proton beam emitted from the beam inlet (11) generate neutrons by means of a nuclear reaction, the moderator (13) slows the neutrons generated by the neutron generator (12), and the reflector body (14) guides diverging neutrons back toward the moderator (13) to increase epithermal neutron beam intensity; the beam shaping body (10) comprises at least one movable member (16) capable of moving in the direction away from or toward the neutron generator (12), said movable member (16) having a first position (L1) and a second position (L2), and said movable member (16) being capable of moving between the first position (L1) and the second position (L2); when the movable member (16) is in the first position (L1), the neutron generator (12) can be replaced, when the movable member (16) is in the second position (L2), the neutron generator (12) cannot be replaced. In the present system, the neutron generator can be easily replaced, the structure is simple, and operation is flexible.
A neutron moderation material for use in a BNCT beam-shaping body. 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.
Disclosed is a beam shaper (10) for neutron capture therapy, comprising a beam entrance (11), a target (12), a retarder (13) abutting the target (12), a reflector (14) surrounding the retarder (13), and a beam exit (17), wherein the retarder (13) may be replaced to adjust the retarding capacity of the retarder (13) for neutrons. The beam shaper (10) for neutron capture therapy only needs the actual requirements of beam neutron energy region, neutron beam flux and other indexes, according to the tumour, to select different materials of the retarder (13) to adjust the slow capacity of neutrons, wherein the same medical equipment can be used to treat different patients, and same has a simple structure and a strong applicability.
One aspect of the present invention is to improve the accuracy of a neutron beam irradiation dose for a neutron capture therapy system and provide a beam diagnostic system that can be used in a neutron capture therapy system to perform a fault diagnosis. Provided in one technical scheme is a beam diagnostic system for a neutron capture therapy system, wherein the neutron capture therapy system comprises a charged particle beam, a charged particle beam entrance for passing the charged particle beam, a neutron generating part generating the neutron beam by means of a nuclear reaction with the charged particle beam, and a beam shaper for adjusting the beam flux and quality of neutrons generated by the neutron generating part and a beam exit abutting the beam shaper, wherein the charged particle beam entrance is accommodated in the beam shaper and the neutron generating part is accommodated in the beam shaper, the beam diagnostic system comprises a charged particle beam diagnostic device and a neutron beam diagnostic device, and the beam diagnostic system is used to simultaneously diagnose whether the neutron capture therapy system and/or the beam diagnostic system is malfunctioning.
One aspect of the present invention is to provide a radiation detection system for improving the accuracy of a neutron beam irradiation dose for a neutron capture therapy system. The neutron capture therapy system comprises a charged particle beam, a charged particle beam entrance for passing the charged particle beam, a neutron generating part generating the neutron beam by means of a nuclear reaction with the charged particle beam, a beam shaper for adjusting the beam flux and quality of neutrons generated by the neutron generating part, and a beam exit abutting the beam shaper, wherein the neutron generating part is accommodated in the beam shaper, the radiation detection system comprises a radiation detection device set within the beam shaper or outside the beam shaper, the radiation detection device is used for real-time detection of the overflowing neutron beam by the neutron generating part or the generated γ-ray after the nuclear reaction of the charged particle beam with the neutron generating part. Another aspect of the present invention is to provide a radiation detection method for improving the accuracy of a neutron beam irradiation dose for the neutron capture therapy system.
Provided is a method for preparing L-BPA, which comprises the following steps: reacting (S)-4-halophenylalanine having a protected amine terminal, a boronizing agent, a Grignard reagent and bis(2-methylaminoethyl)ether to obtain a reaction mixture, wherein the reaction mixture comprises (S)-4-borono-L-phenylalanine having a protected amine terminal, the (S)-4-halophenylalanine having a protected amine terminal has a structure as shown by the following formula (I), the (S)-4-borono-L-phenylalanine having a protected amine terminal has a structure as shown by the following formula (II), and in formula I and formula II, R2 is a protecting group; separating and obtaining the (S)-4-borono-L-phenylalanine having a protected amine terminal from the reaction mixture; and removing the protecting group of the (S)-4-borono-L-phenylalanine having a protected amine terminal so as to obtain the L-BPA, wherein the L-BPA has a structure as shown by the above formula (III).
Provided are a shielding material for shielding a radioactive ray and preparation method thereof. The shielding material consists of water, a cementing material, a fine aggregate material, a rough aggregate material and an additive, wherein the fine aggregate material consists of a borax glass powder and a barite sand, and the rough aggregate material consists of barite. A content of a boron component in the borax glass powder accounts for 0.5%-1% of the total weight of the shielding material. A content of barium sulfate in the barite sand and barite accounts for 71%-75% of the total weight of the shielding material. Other contents include water, the cementing material and the additive, and a sum of contents of all components is 100% total weight of the shielding material.
C04B 28/00 - Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
Provided is a beam shaping body for neutron capture therapy, comprising a beam inlet, a target material, a retarder adjacent to the target material, a reflector surrounding the retarder, a thermal neutron absorber adjacent to the retarder, a radiation shield provided inside the beam shaping body and a beam exit, wherein the target material and a proton beam incident from the beam inlet undergo a nuclear reaction to produce neutrons, the neutrons form a neutron beam defining a main axis, and the neutrons produced from the target material are retarded by the retarder to an epithermal neutron energy range; wherein the material of the retarder is made of MgF2 or a mixture containing MgF2 and 6LiF accounting for 0.1-5% in percentage by weight of the MgF2, which is subjected to a powder sintering process using a powder sintering device so as to change a powder or a powder compact into blocks, the reflector guides neutrons deviating from the main axis back to the main axis so as to improve the intensity of the epithermal neutron beam, the thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdose in superficial normal tissue during a therapy, and the radiation shield is used for shielding leaking neutrons and photons so as to reduce the dose of normal tissues in non-radiation areas.
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.
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.
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