Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: A neutron capture therapy system capable of eliminating amyloid ?-protein includes a neutron capture therapy device and a compound capable of specifically binding to the amyloid ?-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 ?-protein. The neutron capture therapy system can specifically eliminate the amyloid ?-protein, and reduce the damage to the tissues surrounding the amyloid ?-protein.

Abstract: 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.

Abstract: Provided is a compound for specifically binding to amyloid ?-protein. The compound has thereon a nuclide with a large thermal neutron capture cross section and the compound is capable of specifically binding to the amyloid ?-protein. The property of the compound allows it to be used in conjunction with a neutron capture therapy device to eliminate amyloid ?-protein. Similarly, when the compound is labelled with radioactive element 11C, the compound can also be used in conjunction with PET/CT for determining the part of the brain where amyloid ?-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 ?-protein.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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 ? rays instantly emitted under neutron beam irradiation.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: Provided is a method for preparing L-BPA, which includes steps of: reacting N-protected (S)-4-halophenylalanine of Formula I, a boronating agent, Grignard reagent and bis(2-dimethylaminoethyl)ether to obtain a reaction mixture, wherein the reaction mixture comprises N-protected (S)-4-boronophenylalanine of Formula II and the R2 group represents a protecting group; isolating the N-protected (S)-4-boronophenylalanine from the reaction mixture; and deprotecting the R2 group of the N-protected (S)-4-boronophenylalanine to obtain L-BPA, wherein the L-BPA has a structure of Formula III.

Abstract: Provided is a compound for specifically binding to amyloid ?-protein. The compound has thereon a nuclide with a large thermal neutron capture cross section and the compound is capable of specifically binding to the amyloid ?-protein. The property of the compound allows it to be used in conjunction with a neutron capture therapy device to eliminate amyloid ?-protein. Similarly, when the compound is labelled with radioactive element 11C, the compound can also be used in conjunction with PET/CT for determining the part of the brain where amyloid ?-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 ?-protein.

Abstract: 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 ?-rays in epithermal neutron beams.