Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: A neutron capture therapy system includes a neutron generation device for generating a neutron beam, an irradiation room for irradiating an irradiated body with the neutron beam and a placement table that is accommodated in the irradiation room and is adapted to support the irradiated body. The placement table includes a placement member for supporting a patient, an adjustment device for adjusting a spatial position of the placement member, a driving rod connected between the adjustment device and the placement member and a first shielding member covering the adjustment device. The first shielding member prevents the adjustment device from being radiated by radioactive rays. The adjustment device is disposed in the first shielding member that is basically sealed, thereby greatly reducing radiation damage to the adjustment device by neutrons and gamma rays and prolonging the service life of the adjustment device.

Abstract: 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.

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: 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, 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.

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: 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.

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: 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 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: 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: 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: 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.