136 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 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.

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.

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 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.

The invention discloses a boron neutron capture therapy device based on a compact deuterium-deuterium neutron generator. The device comprises a shielding shell, a neutron source part and a support frame part, the support frame part comprises a support base and a support frame, and the end part of the support frame is fixed on the support base; the supporting base and the supporting frame form an accommodating space; the neutron source part is used for emitting neutrons, and the shielding shell is used for shielding all neutrons in a non-0-degree direction; when the boron neutron capture therapy device is started, the accommodating space forms a neutron field only retaining the 0-degree direction. The device is formed by closely splicing a plurality of compact deuterium-deuterium neutron generators, a traditional nuclear reactor or a large accelerator is replaced, miniaturization of the BNCT technology is successfully achieved, the construction and use cost is remarkably reduced, and the clinical accessibility and practicability of the technology are improved.

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.

The present application relates to a boron neutron capture therapy system (100) and a method of operating the same, the boron neutron capture therapy system (100) including a neutron beam irradiation device (10), a treatment planning module (30), and a control module (40), wherein the neutron beam irradiation device (10) generates a neutron beam and irradiates the neutron beam to an irradiated body, the treatment planning module (30) sets a boron concentration for each voxel unit in a three-dimensional voxel prosthetic tissue model to generate a treatment plan, and the control module (40) controls the neutron beam irradiation device (10) to irradiate based on the treatment plan. The treatment planning module (30) sets corresponding boron concentration data for each voxel unit, and then combines it with medical image data to perform dose simulation to formulate a treatment plan, thereby making the distribution of boron atoms in the region of interest more consistent with the actual situation, improving the accuracy of model establishment and dose calculation, and ensuring the accuracy of the treatment plan, thereby guaranteeing the treatment effect.

The present invention relates to a real-time dosimetry device for neutron capture treatments. The device comprises a first module (1) to absorb a flow of dispersed neutrons in a patient which impinge on the device. The first module (1) is made of a lightweight material such as high-density polyethylene, graphite, or a molecular compound, with lithium content. A second module comprises a first segmented gamma radiation detector (2) that is sensitive to radiation interaction positions therein, and a second segmented gamma radiation detector (3), which is also sensitive to the positions, the second gamma radiation detector (3) being detachably coupled to the first gamma radiation detector (2). The device is particularly suitable for real-time dosage monitoring in patients during boron neutron capture treatments (BNCT).

This invention discloses a front-end interaction and clinical safety control method and system for boron neutron capture therapy, comprising the following steps: constructing a patient-specific treatment model; during treatment, collecting real-time monitoring data streams containing boron concentration data and physiological state signals through biosensors; inputting the monitoring data streams into the patient-specific treatment model to predict future outcomes; based on the prediction results, generating evaluation results in real time through a dynamic optimization algorithm; arbitrating real-time control commands and physiological state signals for safety, and ultimately controlling the treatment execution device; and displaying the real-time monitoring data streams, prediction results, control commands, and safety status through a unified interactive interface. This invention achieves continuous and prospective prediction of boron drug distribution and radiation dose by constructing a treatment model that integrates the patient's unique anatomical and physiological information and dynamically driving the model using real-time collected in vivo data.

The beam parameter measurement device for boron neutron capture therapy provided in this application includes: a detector; a beam inlet window provided on the side of the test chamber facing the beam outlet, with the detector head extending into the interior of the test chamber; a moving mechanism on which the detector is mounted for adjusting the position of the detector head inside the test chamber; an adjustment mechanism on which the test chamber is mounted for adjusting the position of the test chamber to make the geometric center of the test chamber coincide with the center of the beam; and a control system including a data acquisition module and a motion control module. The data acquisition module is electrically connected to the detector for acquiring beam data output by the detector, and the motion control module is electrically connected to the moving mechanism and the adjustment mechanism for controlling the moving mechanism and the adjustment mechanism. This application can reliably adjust the position of the detector inside the test chamber, and can also adjust the position of the test chamber to ensure that the geometric center of the test chamber coincides with the center of the beam, thereby improving the accuracy of the measurement data.

Neutron-induced radiation detectors (NiRDs) and radiation dosimetry systems containing the same are described. Examples of NiRDs can include numerous components based on location, function, dimension, and / or constituent materials. A NiRD can be configured to directly measure an absorbed dose (or rate) of particular ionizing reaction products induced by neutrons. The NiRD can utilize various detection schemes for measuring the deposited energy of the reaction products, such as gaseous ionization, semiconducting, scintillating, or homogenous versions of these detection schemes. The NiRD can measure the deposited energy of the reaction products in forward emission, backward emission, or both. Examples of radiation dosimetry systems can include one or more NiRDs, a gamma ray detector, and readout electronics coupled to each of the radiation detectors. Example implementations of the radiation dosimetry systems are described for determining an equivalent dose (or rate) of a neutron beam generated for boron neutron capture therapy (BNCT).

The invention relates to the technical field of radiotherapy equipment, and discloses a simulated beam outlet for boron neutron capture therapy, which comprises a simulated treatment room, a high-precision slide rail type six-dimensional mechanical arm treatment bed is mounted in the simulated treatment room, and an image guide system flat panel detector is mounted in the simulated treatment room. According to the invention, the boundary dimension and the horizontal height of the simulated beam port shell are completely consistent with those of an actual beam port, so that an accurate physical reference is provided for positioning; the two image guide system flat panel detectors which form an included angle of 90 degrees can synchronously collect images of a patient from the horizontal direction and the vertical direction, and the positioning deviation is accurately analyzed; according to the positioning device, the laser lamp can be accurately positioned to the center of a simulation beam outlet through cooperation of a driving motor, a pull rope and a spring, a datum line is projected to assist in checking the positioning precision, a multi-dimensional positioning system is formed through cooperation of the driving motor, the pull rope and the spring, it is ensured that the positioning deviation of a patient is controlled within an extremely small range, and a foundation is laid for the accuracy of subsequent actual treatment.