319 results about "Neutron capture" patented technology

A method for dose calculation in a boron neutron capture therapy planning system based on a track tracking Monte Carlo method comprises the following steps: sampling according to input description source item particles, carrying out transport calculation by using the track tracking Monte Carlo method under voxel grid geometry, calculating a transport distance while calculating the transport distance, and calculating the dose in the boron neutron capture therapy planning system by using the track tracking Monte Carlo method. Counting based on the voxel grid to obtain particle flux and dose; by adopting the operation of track tracking method acceleration based on voxel grid geometry, the surface crossing judgment method is improved, and the problem that the surface crossing operation takes too long time in the calculation process is solved; counting is carried out while the transportation distance is calculated, the counting time is saved on the premise that the counting precision is guaranteed, and compared with a traditional Monte Carlo method based on CSG geometry, the method is more suitable for a voxel model obtained from a medical image, and the calculation speed is higher.

The invention discloses a multi-metal borate nano-particle as well as a preparation method and application thereof. The preparation method comprises the following steps: in the presence of small molecules with alkyl chains, performing high-temperature thermal decomposition on an organic metal compound or a metal salt compound precursor and organic borate in a solvent, and then centrifuging, modifying, performing ultrafiltration, dialyzing and purifying to obtain the multi-metal borate nanoparticles. The preparation method disclosed by the invention has the characteristics of mildness, high efficiency and strong controllability. The multi-metal borate nanoparticles prepared by the preparation method disclosed by the invention have the advantages of monodisperse size, relatively high magnetic property and good biocompatibility. Therefore, the prepared multi-metal borate nanoparticles not only have multi-modal imaging functions such as magnetic resonance imaging, near-infrared two-region imaging, nuclear medicine imaging and magnetic particle imaging, but also can be used for various treatment means such as magnetocaloric therapy and boron neutron capture therapy; potential advantages are realized in biomedical applications such as magnetic targeting tumor treatment and imaging contrast agents, and high practical values are realized.

Disclosed are a neutron dose measurement apparatus and a neutron capturing treatment device. The neutron dose measurement apparatus includes a measurement unit for receiving neutrons and outputting signals, a signal processing unit for processing the signals output from the measurement unit, a counter for counting the signals output from the signal processing unit to obtain a count rate, and a count rate correction unit for correcting the count rate.

The invention discloses a boron manganese tannate nanoparticle as well as a synthesis method and application thereof. The synthesis method of the tannic acid boron manganese nanoparticles comprises the following steps: sequentially dropwise adding a bivalent manganese salt solution, a boric acid solution, a polyethylene glycol solution and a bovine serum albumin solution into pure water under water bath ultrasonic or magnetic stirring to obtain an assembly stock solution, and adding a tannic acid solution into the assembly stock solution to initiate assembly; and continuously carrying out water-bath ultrasonic treatment or magnetic stirring for a period of time, and then carrying out ultrafiltration to remove free drug molecules, so as to obtain the boron manganese tannate nanoparticles capable of mediating boron neutron capture therapy and magnetic resonance imaging. The boron manganese tannate nanoparticles can improve the boron intake in tumors and prolong the retention time of boron atoms in the tumors in boron neutron capture therapy, drug distribution is monitored through the nuclear magnetic resonance imaging technology, then the treatment effect of the boron neutron capture therapy is improved, the preparation method is simple, the stability is good, the size is uniform, the boron loading amount is high, and the application prospect is wide. The biological safety is good, and the repeatability is high.

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 provides a polypeptide boron carrying agent. The polypeptide boron carrying agent comprises a polypeptide and at least one boron-containing group connected with a main chain or side chain amino group of the polypeptide, the polypeptide comprises at least one MAP peptide and a c (RGD-DPhe-K) cyclic peptide, the C end of the at least one MAP peptide is connected with the N end of the c (RGD-DPhe-K) cyclic peptide, and the MAP peptide is a KLALKLALKAALKLA continuous sequence. The polypeptide boron carrying agent provided by the invention has better targeting property and cell penetrability to tumor cells, has high boron loading amount, and meets the requirements of boron neutron capture therapy.

The invention discloses a benzopyridine ring-containing compound and a preparation method thereof. The invention provides a compound as shown in a formula 4. The compound can be used for synthesizing the compound shown in the formula I. The compound shown in the formula I is low in toxicity to tumor cells and can be combined with boron neutron capture therapy for targeted cancer treatment. # imgabs0 #

Borylated Amino Acid compositions comprising tyrosine derivatives BTS and BTS(OMe) and novel methods of making BTS and BTS(OMe) are disclosed herein. Consequently, the BTS and / or BTS(OMe) can be scaled up to commercial scale and administered to patients as a Neutron Capture Agent and provide a method of treating cancer, immunological disorders, and other disease by utilizing a Neutron Capture Therapy modality.

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.

Systems and methods of the present disclosure relate to determining a borehole holdup. A method comprises logging a well with a pulsed-neutron logging (PNL) tool; receiving, via the PNL tool, transient decay measurements, capture spectrum measurements, and inelastic spectrum measurements; extracting information from each of the capture spectrum measurements, the inelastic spectrum measurements, and the transient decay measurements; inputting all of the extracted information as a single input into artificial neural networks; and determining the borehole holdup with the artificial neural networks.

The invention relates to the technical field of boron neutron capture therapy, in particular to a dose verification device for boron neutron capture therapy. The objective of the invention is to solve the technical problem that dose distribution of tumor tissues and surrounding thereof cannot be accurately measured. To this end, the dose verification device of the present application comprises: a box; the die body assemblies move in the incident direction of the neutron beam and are arranged in a stacked mode; the die body insertion plate comprises a tumor tissue simulation positioning area containing boron-10 with a first concentration and / or a normal tissue simulation positioning area containing boron-10 with a second concentration, and the first concentration is greater than the second concentration; the dose detection module is used for detecting distribution data of secondary particles generated after the boron-10 and neutrons are subjected to nuclear reaction; and the data processing module is used for acquiring the distribution data and determining the dose distribution in the die body assembly according to the distribution data. According to the application, the difference of the boron-10 concentration of the tumor tissue and the normal tissue can be better simulated, and the dose distribution of the tumor tissue and the surrounding thereof can be more accurately measured.

A neutron capture therapy system. The neutron capture therapy system includes: a charged particle generation device used for generating charged particles; an accelerator used for accelerating the charged particles; a neutron generation device including a particle transmission part and a neutron generation part provided in a first end part of the particle transmission part, wherein the charged particles can pass through the particle transmission part and interact with the neutron generation part to generate neutrons; a beam shaping body having an accommodating cavity, wherein the accommodating cavity includes a first surface and a second surface intersecting with the first surface, and the first end part is provided in the accommodating cavity; and a first fitting part provided between the first surface of the accommodating cavity and the outer surface of the particle transmission part. The first fitting part is configured to at least surround part of the particle transmission part.

The invention provides a boron drug with tumor targeted release capability for boron neutron capture therapy and a preparation method thereof, relates to the technical field of tumor therapy, and provides a boron drug which can be activated through high-concentration NAD (P) H at a tumor site and can release a B-10 drug in a targeted manner for boron neutron capture therapy. A boron-10-containing compound in the boron medicine is connected with 3-aldehyde quinoline salt through a self-elimination reactive group, the 3-aldehyde quinoline salt can be specifically reduced by NAD (P) H rich in tumor cells to trigger chain reaction, and the effective boron-10 compound is released for boron neutron capture therapy. The damage to normal cells in the BNCT process can be effectively reduced by a method for targeted aggregation of the boron drug in the tumor cells. The boron drug synthesis method is simple, mild in condition and high in yield, has the advantages of stable chemical property, good light stability, small toxicity and the like, and provides a good application prospect for the field of boron neutron capture therapy.

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.

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 structure, the acting layer interacts with the charged particle beam to generate the neutron beam, the backing layer supports the action layer, and the heat dissipating structure includes a tubular member composed of tubes arranged side by side.

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.

This invention relates to the monitoring and diagnosing of nuclear power plants for its thermal performance using the NCV Method. Its applicability comprises any nuclear reactor such as used for research producing a useful output. Its greatest applicability lies with conventional Pressurized Water Reactor and Boiling Water Reactor nuclear plants generating an electric power. Its teachings of treating fission as an inertial process, a phenomena which is self-contained following incident neutron capture, allows the determination of an absolute neutron flux. This process is best treated by Second Law principles producing a total fission exergy. This invention also applies to the design of fusion thermal systems regards the determination of its Second Law viability and absolute plasma flux.

The invention discloses a drug controlled release layer-by-layer self-assembly nano hydrogel boron carrying agent and application thereof, and belongs to the technical field of biomedicine. According to the method, calcium alginate nano-particles, calcium alginate nano-particles modified by polyallylamine hydrochloride, calcium alginate nano-particles modified by boric acid and polyallylamine hydrochloride, and calcium alginate nano-particles modified by polyallylamine hydrochloride, boric acid and polyallylamine hydrochloride are prepared in sequence. According to the invention, boric acid is loaded into the layer-by-layer self-assembled nano hydrogel material, so that intelligent controlled release can be realized, and the material is applied to boron neutron capture therapy. The material has good water solubility, good dispersity in an aqueous solution, small size and uniform particle size. The material also has good biocompatibility, intelligent and accurate release control is realized, and important technical progress is brought to cancer treatment.

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.

A neutron capture therapy system and a target material for a particle beam generation apparatus, the heat dissipation performance of a target material might be improved. A neutron capture therapy system includes a neutron generation apparatus and a beam shaping body, the neutron generation apparatus includes an accelerator and a target material, and a charged particle beam generated by means of acceleration of the accelerator acts with the target material to generate a neutron beam. The target material includes an active layer, an anti-foaming layer, a heat dissipation layer and a heat conduction layer, the active layer acts with a charged particle beam to generate a neutron beam; the anti-foaming layer suppresses foaming caused by the charged particle beam; the heat dissipation layer directly and rapidly conducts to the heat conduction layer, heat deposited on the active layer, and discharges by means of a cooling medium.

The utility model relates to the technical field of medical treatment, in particular to a radiation shielding device and a boron neutron capture therapy system.The radiation shielding device comprises a first shielding layer used for shielding neutron beam scattering and a second shielding layer which has no shielding effect on neutron beams and is used for shielding gamma rays in the neutron beams. The first shielding layer and the second shielding layer are arranged in an attached mode, the first shielding layer is provided with a beam outlet hole allowing a neutron beam to penetrate through, and the position, corresponding to the beam outlet hole, of the second shielding layer is not provided with the beam outlet hole, so that the second shielding layer is kept complete. Wherein the radiation shielding device can effectively protect normal tissues of a patient from being damaged by scattered neutron beams and gamma rays, and the normal tissues are prevented from being damaged by radiation; the method does not need to adapt to body types of patients, is high in universality and does not need to be customized according to body type differences of the patients, cost is remarkably reduced, and economic burdens of the patients are smaller. And direct contact with a patient is not needed, so that the comfort of the patient is better while the shielding effect is ensured.

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.

The present invention relates to the technical field of target containers in boron neutron capture therapy technology, particularly to a cylindrical target container; the target container includes a container housing, a rotating target, a rotating sealing ring, a transmission device, a liquid collecting tank, an evaporation crucible, a cleaning assembly, a sealing door, and a film thickness gauge; the container housing, the liquid collecting tank, and the sealing door form a container cavity; the rotating target includes a cylindrical target and a rotating shaft; the rotating target is connected to the container housing through the rotating sealing ring; the sealing door is installed at the opening of the container cavity; the cylindrical target is arranged inside the container cavity; the cylindrical target includes a flow guiding plate and a surface substrate; the flow guiding plate is arranged inside the cylindrical target; the surface substrate is arranged on the outer side surface of the cylindrical target. The flow guiding plate and the surface substrate form a heat exchange channel; using this target container can achieve functional integration, non-contact automatic target material replacement, reduce the target material replacement frequency, improve the heat exchange efficiency of the target, save space, and have a self-cleaning function.