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 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: 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 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: 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 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.

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: 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.

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 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 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 smart watch with transmission function is disclosed. The smart watch with transmission function includes a movement structure, two transmission watch straps, a first connecting element and a second connecting element. The movement structure includes a judgment unit. The two transmission watch straps connect with respect to the two ends of the movement structure, and thereby connect to the judgment unit. The first connecting element is disposed on one of the two transmission watch straps and opposed to one end of the movement structure. The second connecting element is disposed on another transmission watch strap and opposed to another end of the movement structure.

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 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 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.

Abstract: A film dosimeter is disclosed in the present invention and doped with a sensitizer for determining a neutron and gamma-ray mixed radiation field. The sensitizer comprises quantitative lithium atoms with a different atom percentage of lithium-6 and lithium-7. Theoretically, the atom percentage of the lithium-6 in the lithium atoms is ranged from 0.1 to 99. On the other hand, a method of determining radiation doses of a neutron and gamma-ray mixed radiation field by using the abovementioned film dosimeter is also disclosed in the present invention.

Abstract: A film dosimeter is disclosed in the present invention and doped with a sensitizer for determining a neutron and gamma-ray mixed radiation field. The sensitizer comprises quantitative lithium atoms with a different atom percentage of lithium-6 and lithium-7. Theoretically, the atom percentage of the lithium-6 in the lithium atoms is ranged from 0.1 to 99. On the other hand, a method of determining radiation doses of a neutron and gamma-ray mixed radiation field by using the abovementioned film dosimeter is also disclosed in the present invention.