Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

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: 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.

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: 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.

Abstract: 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.

Abstract: 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.

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: 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.

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: 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 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: 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.