200 results about "Neutron capture" patented technology

The invention relates to the technical field of radiation therapy, in particular to a boron neutron capture therapy beam shaping device and a boron neutron capture therapy system. The beam shaping device for boron neutron capture therapy is used for beam shaping of a DT neutron tube generator. The interior of the beam shaping device is provided with a particle beam channel, and the particle beam channel is used for generating an initial neutron source through an incident proton beam. The beam shaping device comprises a value-added layer, a moderator, a filter layer, a reflecting layer, a collimator and a shielding layer, wherein the value-added layer, the moderator, the filter layer and the collimator are sequentially arranged from a target material to an outlet. And the axes of the particle beam channel, the value-added layer, the moderator and the collimator coincide. According to the beam shaping device, 14Mev high-energy neutrons from the DT neutron tube generator are shaped into hot / slow neutron beams meeting the BNCT treatment requirements, and impurities of fast neutrons and gamma rays are reduced to the maximum extent, so that the dosage precision and biological selectivity of treatment are effectively improved.

The invention relates to the technical field of cable logging, and particularly discloses a mineral component and content testing device and method suitable for a uranium-bearing reservoir, and the device comprises a cable logging system, a logging depth calibration system and a time synchronization system, the logging tool assembly comprises a spectral logging tool, a natural gamma-ray spectrum logging tool, an epithermal neutron logging tool and a neutron capture gamma-ray spectrum logging tool. The method comprises the steps of combining a logging tool assembly and a cable logging system, configuring a logging depth calibration system, configuring a time synchronization system, carrying out PTP time synchronization on the cable logging system and the logging depth calibration system, collecting original logging time and original logging data, carrying out time resampling and depth correction on the original logging data, and carrying out time synchronization on the logging depth calibration system and the cable logging system. And resampling the logging data according to the logging depth and time to divide a stratum structure. According to the method, acquisition and data fusion of the mineral components, the radioactive element content and the porosity characteristics of the stratum around the well can be realized, and the exploration precision, efficiency and evaluation accuracy are improved.

The invention relates to the technical field of radiotherapy, and discloses a method for generating a boron neutron capture therapy plan, computer equipment and a storage medium. Comprising the following steps: based on current state data of neutrons, determining first section data, second section data and a current transport distance of the neutrons at a current position, and judging whether the neutrons collide or not; wherein the first cross section data is used for describing the macroscopic cross section of nuclides except boron, and the second cross section data is used for describing macroscopic cross section neutrons obtained through calculation according to the boron concentration of the current grid and the microcosmic cross section of the nuclide boron; and under the condition that neutrons do not collide and the neutrons are transmitted from the current grid to the next grid through the surface, if the two grids are made of the same material, updating the second cross section data based on the boron concentration of the next grid to calculate the dose, and finally generating a boron neutron capture therapy plan by using a dose distribution calculation result. Therefore, only the cross section data related to the boron concentration is updated in the penetrating surface, and the calculation efficiency is optimized.

The application relates to a neutron absorption material and application thereof to a control rod for a nuclear reactor core. The neutron absorption material provided by the application is prepared by mixing ytterbium elements and holmium elements in a certain proportion, can effectively play the high neutron capture cross-section characteristics of the ytterbium elements and the holmium elements, effectively absorb thermal neutrons, and can ensure good chemical and thermal stability, so that the neutron absorption material can maintain its structure and performance stability for a long time in a high irradiation environment, effectively avoids the conversion of the neutron absorption material into a weak neutron absorption material after absorbing neutrons, and further controls the neutron absorption characteristics of the neutron absorption material. Further, the neutron absorption material provided by the application can still ensure the neutron absorption characteristics thereof and maintain the reactivity value under high burnup depth, so as to prolong the service life of the control rod for the nuclear reactor core.

Provided is a BNCT-SPECT technique with which instant gamma rays generated by a BNC reaction can be measured in real time with excellent accuracy in BNCT. A measurement device for measuring a therapeutic effect in boron neutron capture therapy, the measurement device being provided with: a collimator in which holes of a predetermined shape are formed at equal intervals in the vertical and horizontal directions; detectors that are disposed in the deepest portions of the holes and that detect gamma rays that are promptly emitted by the irradiation of neutrons to boron; and an arithmetic processing unit that, when the gamma-rays are detected by the detector, distinguishes between a case where the gamma-rays are not detected by the other surrounding detectors at the same time and a case where the gamma-rays are not detected by the other surrounding detectors at the same time, and performs a simultaneous counting process or a non-simultaneous counting process to create a wave height distribution. The overall gamma-ray intensity distribution is displayed three-dimensionally.

The invention provides a neutron energy spectrum measurement method for a boron neutron capture therapy beam, and belongs to the technical field of medical equipment. The sequence of the activated foils is optimized by adopting a Monte Carlo method; the activated foils are weighed and then stacked in a cadmium / aluminum detection box with the machining precision within 0.01 mm according to the sequence, and the center axis of the activated foils, the center axis of the detection box and the center axis of a beam are aligned through a treatment room positioning system; after irradiation under the nominal irradiation condition of the boron neutron capture therapy system, measuring the characteristic gamma ray full-energy peak net count of each activated foil by using a high-purity germanium gamma spectrometer, and calculating the mononuclear activation rate in combination with irradiation parameters; and processing group cross-section data through an NJOY program, and performing spectrum unfolding in combination with an initial spectrum simulated by Monte Carlo and an SAND-II algorithm. According to the method, a multi-material activated foil synchronous measurement technology is adopted, and the clinical applicability of boron neutron capture therapy beam quality control is remarkably improved through algorithm and data collaboration and activated foil sorting optimization.

The invention discloses a positioning system applied to boron neutron capture therapy, and relates to the technical field of medical neutron radiotherapy, the system comprises a fixing module used for fixing a patient on an operating bed, the fixing module comprises a head fixing film, a plurality of non-coplanar optical reflective balls are integrated on the head fixing film, and the optical reflective balls are arranged on the head fixing film. The construction module is used for constructing a patient reference coordinate system, and the image acquisition module is used for acquiring medical three-dimensional image data of a patient in a fixed state and detecting position information of a reflective ball in an image coordinate system; the positioning system applied to boron neutron capture therapy can effectively cope with positioning errors caused by posture changes of a patient, has submillimeter-level positioning precision, supports linkage with a treatment planning system, and remarkably improves safety, effectiveness and operation efficiency of BNCT treatment.

The invention discloses a tumor targeting boron-containing Fe3O4-based nano-enzyme and a preparation method and application thereof, and belongs to the technical field of tumor treatment.The tumor targeting boron-containing Fe3O4-based nano-enzyme takes boron-10 doped Fe3O4 nano-enzyme as a boron-containing drug group and an enzyme activity center, and the surface of the tumor targeting boron-containing Fe3O4-based nano-enzyme is modified with a targeting group; the targeting group is chitosan-folic acid-polyethylene glycol. The tumor targeting boron-containing Fe3O4-based nano-enzyme has relatively strong selective enrichment capacity on tumor cells such as melanoma, shows good biocompatibility and low toxicity, and has relatively strong apoptosis induction and killing effects on the melanoma cells in boron neutron capture therapy; meanwhile, active oxygen free radicals can be generated in boron neutron capture therapy to generate an oxidative damage effect.

The invention discloses an OpenMC-based BNCT dose full-process automatic calculation output method, and particularly relates to the technical field of boron neutron capture therapy dose calculation, and the method comprises the steps: reading a DICOM-CT image, automatically completing HU value segmentation, material assignment and voxel grid modeling, and generating an OpenMC geometry and material input card; setting a neutron / photon source, an operation mode and a counting grid, and executing Monte Carlo transport calculation; an ICRP flux-dose conversion coefficient library is built in, and dose calculation is automatically completed; the dose field is written into an Rt dose file, and the Rt dose file can be directly imported into mature medical image processing software for visual evaluation and plan optimization. According to the method, end-to-end automation from the CT image to the clinical available dose file is achieved, manual intervention is not needed, the BNCT dose calculation efficiency, precision and standardization level are remarkably improved, and a reliable tool is provided for BNCT dose simulation research.

The invention relates to the technical field of medical data processing, and discloses a neutron source correction method and equipment for a radiotherapy planning system, and the method comprises the steps: obtaining a first value of a target physical quantity obtained based on physical experiment measurement, and obtaining a second value of the target physical quantity corresponding to the radiotherapy planning system; the physical experiment is used for quality guarantee; if it is determined that the deviation does not meet the preset requirement based on the first numerical value and the corresponding second numerical value of the target physical quantity, the target neutron input energy-angle spectrum is obtained through inversion by means of a regularization optimization model, so that the deviation meets the preset requirement; and correcting the neutron input energy-angle spectrum in the radiotherapy planning system based on the target neutron input energy-angle spectrum. According to the invention, the neutron input energy-angle spectrum in a radiotherapy planning system can be corrected, and the consistency of a simulation result and an experimental result is ensured, so that the requirement of boron neutron capture therapy on quality assurance is met.

A radiation dose quantification method and system, the method comprising: detecting, with one or more detectors with respective sensitive volumes, gamma-rays emitted as a result of capture of neutrons by a composition in a subject subjected to an irradiation program, the composition comprising one or more thermal neutron capture agents, the neutrons having been generated by non-elastic collisions between a primary beam of particles and nuclei in the subject, wherein the particles consist of any one or more of protons, deuterons, tritons and heavy ions, the irradiation program comprises at least one period of irradiation with a beam duration that includes beam-on periods and beam-off periods; applying at least one predefined energy window or filter configured to accept only detection events in the one or more detectors resulting from gamma-rays with an energy indicative of selected gamma-rays arising from the capture of thermal neutrons by the one or more thermal neutron capture agents, wherein the thermal neutrons are neutrons with energies below approximately 0.4 eV; applying a timing window configured to reject or ignore detection events in the one or more detectors resulting from at least prompt gamma-rays produced in non-neutron capture events; and determining the radiation dose of neutron radiation received by the subject during the irradiation program from at least the accepted detection events or determining a dose map of the radiation received by the subject from at least the accepted detection events.

To provide a treatment planning system for boron neutron capture therapy.SOLUTION: A treatment planning system for BNCT comprises storage means which stores an ideal patient position that is considered to be a position determined for each patient with respect to a neutron beam irradiation port of a neutron beam irradiation device and an ideal position for a neutron beam treatment for the patient, an estimated gradually-reduced boron concentration value that is estimated from the in-blood boron concentration measurement value right before assumed multiple times of irradiation, and an assumed boron concentration application dose that is calculated by calculation means that calculates the application dose based on each estimated gradually-reduced boron concentration value. The treatment planning system for BNCT selects the estimated gradually-reduced boron concentration value closest to the measurement value upon receiving the in-blood boron concentration measurement value right before irradiation, and transmits the assumed boron concentration application dose based on the boron concentration value to a BNCT system.SELECTED DRAWING: Figure 20

Disclosed herein are boronated amino acid compositions comprising tyrosine derivatives TC220 and TC221 and improved methods of making TC220 and TC221. Thus, the TC220 and / or TC221 can be expanded to commercial scale and administered to patients as neutron trapping agents, and methods of treating cancer, immune disorders, and other diseases by utilizing a neutron capture therapy pattern are provided.

To provide a new boron preparation.SOLUTION: A modified boron carbide particle powder contains boron carbide particles, wherein at least part of the surface of at least some of the boron carbide particles in the boron carbide particles is modified with polyglycerol. The polyglycerol-modified boron carbide particle powder is inherently less toxic and can be administered in a shorter time, and can be suitably used in boron neutron capture therapy applications.SELECTED DRAWING: None

An irradiation target for the production of radioisotopes comprises a plurality of plates having aligned central openings. First and second elongated central members extend in opposite directions through the aligned central openings of the plates. The first and second elongated central members each have a pair of wings at first and second ends of the plurality of plates, respectively. The first and second elongated central members further have a pair of tabs adjacent to the wings of the other elongated central member. Tabs of the first elongated central member are bent to engage one end face of the plurality of plates. Tabs of the second elongated central member are folded over the wings of the first elongated central member. The plates and the first and second elongated central members are formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.

A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.

An arylboron compound, its preparation method, applications, and pharmaceutical compositions are disclosed for tumor imaging. The compound of formula (I) exhibits high fluorescence quantum efficiency through intramolecular charge transfer. The compound of formula (I) synthesized in this invention can be linked to different antibodies via Q3 at certain concentrations, allowing for precise targeting of corresponding tumors based on the antibody. This type of boron drug formulation can be used in boron neutron capture therapy to kill tumor cells. It exhibits better killing effects; the compound of formula (I) targets tumor cells through antigen-antibody interaction. After the boron-10-containing drug accumulates at the tumor site, neutron radiation triggers a nuclear reaction releasing alpha particles and... 7 Lithium particles kill cells; the range of these two particles is approximately 10 μm. High-energy-density heavy ions disrupt the DNA double helix structure in tumor cells, causing irreparable cell death. Simultaneously, the 10 μm distance avoids damage to normal cells and tissues.

The invention discloses a neutron sensitive MCP and a manufacturing method thereof, and the MCP comprises a glass substrate which is provided with a plurality of micro-channels extending from a first surface to a second surface. The microchannel comprises an open end and a blind hole end, and the blind hole end is close to the second surface. An electron multiplication function layer is arranged in the microchannel, a neutron sensitive film layer is arranged on the second surface, and electrode layers are formed on the surfaces of the two ends. According to the invention, neutron capture and electron multiplication functional regions are separated, the blind hole end entity sensitive film layer has no aperture ratio limitation, and the neutron capture probability is maximized; and the U-shaped microchannel realizes electron avalanche amplification. According to the design, the microchannel amplification imaging function is reserved, meanwhile, the influence of the aperture opening ratio on the detection efficiency is avoided, and the detection efficiency is improved.

Provided is a beam shaping body (131) for a neutron capture therapy system (100), comprising: a retarder (1312) used for decelerating neutrons of a neutron beam (N) to epithermal neutrons; a reflector (1313) surrounding the retarder (1312) and used for reflecting neutrons deviating from the neutron beam (N) back to the neutron beam (N) so as to improve the intensity of the neutron beam (N); and an epithermal neutron flux enhancer (1316) used for improving an epithermal neutron flux in the neutron beam (N) and provided in the retarder (1312) and / or in the reflector (1313) and / or between the retarder (1312) and the reflector (1313). Further provided is the neutron capture therapy system (100) comprising the beam shaping body (131), the epithermal neutron flux enhancer (1316) is provided in the beam shaping body (131) to increase the epithermal neutron flux in the neutron beam (N), so that the flux and quality of a neutron source are improved.

The present disclosure provides a neutron target device for boron neutron capture therapy, comprising: a container having a containing cavity; a neutron target component arranged in the containing cavity, the neutron target component comprising a target disc and a target sheet detachably connected with the target disc; a rotating component connected with the target disc for driving the neutron target component to rotate; a driving component connected with the rotating component for driving the rotating component to rotate; and a cooling component arranged at an end of the rotating component away from the neutron target component for supplying a cooling liquid; wherein the rotating component is provided with a liquid inlet cavity and a liquid outlet cavity, the target disc is provided with a liquid inlet flow channel and a liquid outlet flow channel, and the target sheet is provided with a liquid inlet hole and a liquid outlet hole; the liquid inlet flow channel is in communication with the liquid inlet cavity and the liquid inlet hole, and the liquid outlet flow channel is in communication with the liquid outlet cavity and the liquid outlet hole. The flow path structure of the neutron target device of the present disclosure is conducive to improving the cooling rate of the target sheet; and the target sheet is detachably connected with the target disc, which is conducive to the convenience of replacing the target sheet.

To provide new and improved methods of treating cancer, immune disorders, and other diseases utilizing borylated amino acids and neutron capture therapy (NCT).SOLUTION: Disclosed herein are borylated amino acid ("BAA") compositions and methods of making BAAs. Accordingly, BAAs can be administered to patients as neutron capture agents and can provide methods of treating cancer, immune disorders, and other diseases by utilizing neutron capture therapy modalities. The invention described herein relates to the field of boron neutron capture therapy (BNCT). In particular, the present invention relates to borylated amino acid ("BAA") or ("BAAs") compositions that can be used as a vehicle for neutron capture therapy in humans. The invention further relates to the treatment of cancer and other immune disorders and diseases.SELECTED DRAWING: None

This invention relates to the field of nuclear radiation detection technology and discloses a two-dimensional array detector for measuring the spatial distribution of neutrons and photons. The detector body includes a detector body comprising a detection unit layer, a light guide layer, and a readout layer. The detection unit layer, light guide layer, and readout layer are vertically stacked sequentially from top to bottom to form a three-layer modular integrated structure. The layers are precisely mechanically aligned and optically coupled without air gaps. The light guide layer is composed of an array of multiple optical fibers. The detection unit layer is composed of an array of multiple detection units, with each detection unit corresponding to one optical fiber. This invention offers advantages such as modularity, high spatial resolution, and real-time signal processing. It can be applied to the measurement of the spatial distribution of neutrons and photons in the field of boron neutron capture therapy, meeting the practical needs of online real-time measurement of the spatial distribution of the neutron-photon mixed radiation field and accurate verification of the treatment irradiation field dose in boron neutron capture therapy.

1. Name of the designed product: Control panel (boron neutron capture therapy two). 2. Use of the designed product: For boron neutron capture therapy. 3. Design points of the designed product: In shape. 4. Picture or photo that best indicates the design points: Perspective view.

Provided are a beam shaping device (10), a neutron capture therapy system (20), and a moderator auxiliary mounting system (30), relating to the technical field of medical equipment. The beam shaping device (10) comprises a moderator assembly (100) and a fixing mechanism (300). An accommodating cavity (200) is formed in the beam shaping device (10), and the moderator assembly (100) is disposed in the accommodating cavity (200). The moderator assembly (100) is configured for adjusting the energy of a neutron beam, and the fixing mechanism (300) is configured for fixing the moderator assembly (100) in the accommodating cavity (200). The mounting stability of the moderator assembly (100) in the accommodating cavity (200) is ensured, and the structural stability of the beam shaping device (10) is improved, such that the beam shaping device (10) can be applied in a vertical irradiation chamber (642).

The invention provides a neodymium-iron-boron magnet, a preparation method thereof, a high-radiation-resistance bonded neodymium-iron-boron magnet and application. The neodymium-iron-boron magnet is of a core-shell structure. The core-shell structure comprises an inner core, an inner shielding layer and an outer protection layer, wherein the inner shielding layer and the outer protection layer sequentially cover the surface of the inner core. Wherein the inner core comprises a neodymium iron boron magnetic material, the inner shielding layer comprises gadolinium oxide, and the outer protection layer comprises boride. According to the method, efficient cascade shielding of high-energy particles such as neutrons and gamma rays is formed through the nuclear physical shielding principle (the neutron capture effect of the gadolinium element and the gamma ray scattering function of boron nitride), the radiation resistance of the magnet is greatly improved, and the prepared neodymium-iron-boron magnet has the advantages of light weight and low-temperature forming; and the synergistic improvement of high radiation resistance and excellent magnetic performance can be met at the same time. The high-radiation-resistance bonded neodymium-iron-boron magnet prepared based on the neodymium-iron-boron magnet can keep stable magnetic performance in an extreme environment with an accumulated radiation dose of more than 1MGy.

The invention discloses a precise control device for continuous infusion of a boron-loaded drug, which overcomes the defects of insufficient precise control, poor continuity and no dynamic closed loop in the existing boron neutron capture therapy. The device comprises a first shell and a second shell which are connected through a hinge, the device is further provided with an electromagnetic drive extrusion assembly, a fixing assembly and a rope ring, and the electromagnetic drive extrusion assembly comprises an electromagnet, a magnetic conductive block and a first elastic piece. The device further comprises a module which is specifically a data collecting and processing module and can collect liquid medicine parameters, pipeline parameters, physiological parameters and flow velocity data and remove abnormal data through filtering processing. And the influence factor calculation module can calculate a physiological state influence factor and an infusion resistance influence factor. Through electromagnetic pressure control, multi-factor calibration and multi-patient overall planning, the flow velocity precision meets the precision infusion requirement, the effective concentration of boron-loaded medicine in the body is stabilized in a treatment window, and the infusion interruption risk is greatly reduced.

The present application relates to the field of oil and gas well logging, and particularly relates to a method, system and device for determining formation water salinity and a storage medium; well section data, rock-electricity parameters, well temperature curves, shale content curves and porosity curves of a well section are obtained; a first water saturation is determined according to the rock-electricity parameters, the porosity curves and the formation water resistivity; a second water saturation is determined according to the shale content curves, the porosity curves and the thermal neutron capture cross section; a minimum value of the square difference between the first water saturation and the second water saturation is calculated, and the value corresponds to the optimal formation water salinity. By simultaneously solving the resistivity and neutron lifetime data, the resistivity and thermal neutron capture cross section data can correct the influence of salinity on each other when reflecting the formation properties, thereby reducing the error caused by single data, more accurately determining the water saturation, and making the results more comprehensive and accurate.

The present invention concerns h-ferritin complexes loaded with anti-tumoral drugs for the treatment of cancer through Boron Neutron Capture Therapy.

The present invention relates to a labyrinth-type neutron beamforming apparatus for neutron capture therapy that can maintain a neutron flux and dramatically reduce a gamma ray flux by changing a path of the beamforming apparatus like a labyrinth and setting the neutron flux at various angles from the reflective surface and the axis in the front-and-rear direction.

The present application relates to neutron dosimetry method, specifically provide a kind of for boron neutron capture therapy fast neutron dosimetry method, by using the paired ionization chamber test system with different liquid environment, one kind of liquid environment has obvious absorption to thermal neutron, then the radiation source under the same power is measured, to obtain more accurate fast neutron dose and the rest two kinds of mixed radiation dose, to solve the problem of inaccurate neutron dose test of different kinds in the prior art in the application process of mixed radiation field, more accurate mixed radiation quantity value can be obtained, so that the different types of neutron dose in mixed radiation field are grasped, so as to improve the radiation effect in the application scene of mixed radiation field.