14434 results about "Radiochemistry" patented technology

Electroporation-based therapies (EBTs) employ high voltage pulsed electric fields (PEFs) to permeabilize tumor tissue, resulting in changes in passive electrical properties detectable using electrical impedance spectroscopy (EIS). Currently, commercial potentiostats for EIS are limited by impedance spectrum acquisition time (˜10 s); this timeframe is much larger than pulse periods used with EBTs (˜1 s). Fourier Analysis SpecTroscopy (FAST) is introduced as a methodology for monitoring tissue inter-burst impedance (diagnostic FAST) and intra-burst impedance (therapeutic FAST) during EBTs. FAST is a rapid-capture (<<1 s) technique which enables monitoring of inter-burst and intra-burst impedance during EBTs in real-time. FAST identified a frequency which delineates thermal effects from electroporation effects in measured impedance. Significance: FAST demonstrates the potential to perform EIS, in addition to intra-burst impedance spectroscopy, using existing pulse generator topologies.

A nuclear fusion reaction device, system and method. The outer wall of a vacuum chamber (301) in the nuclear fusion reaction device (30) comprises an inner ring surface (M1) and an outer ring surface (M2) which are connected to each other; the outer ring surface (M2) surrounds the inner ring surface (M1); the inner ring surface (M1) protrudes toward the central axis of the vacuum chamber (301); the vacuum chamber (301) surrounds a plurality of first coils (302); at least some of the plurality of first coils (302) extend in the circumferential direction of the inner ring surface (M1) and are sequentially arranged in the axial direction of the vacuum chamber (301); a plurality of second coils (303) surround the vacuum chamber (301), extend in the circumferential direction of the outer ring surface (M2), and are sequentially arranged in the axial direction of the vacuum chamber (301); a plurality of third coils (304) all surround the vacuum chamber (301) and are sequentially arranged in the circumferential direction of the vacuum chamber (301); and the plurality of first coils (302), the plurality of second coils (303), and the plurality of third coils (304) are used for generating a magnetic field, such that plasma rings with negative triangular deformation are generated in the vacuum chamber (301), and a fusion reaction occurs.

The invention relates to the technical field of nuclear fusion devices, and discloses a nuclear fusion device and a monitoring system and an installation method thereof, the monitoring system comprises a cold shield main body, the cold shield main body is of an annular rotation structure, and the cold shield main body is arranged in a cavity and wraps the circumferential outer side of a vacuum chamber; the cold shield main body comprises a plurality of groups of fan-shaped cold shield sections which are sequentially arranged in the circumferential direction, and the plurality of groups of fan-shaped cold shield sections are encircled to form the cold shield main body; the distance measuring assembly is arranged on the cold shield main body, the distance measuring assembly comprises a plurality of groups of distance measuring sensors which are arranged in the circumferential direction of the cold shield main body at intervals, and each group of distance measuring sensors comprises a plurality of distance measuring sensors; the distance measuring sensor is used for detecting the size of a gap between the cold shield body and the longitudinal field coil and the size of a gap between the cold shield body and the vacuum chamber. Therefore, the cold shield main body can be assisted to be assembled at a position in the nuclear fusion device, and the matching position of the cold shield main body, the vacuum chamber and the longitudinal field coil can be monitored in real time.

The invention relates to the technical field of radiation measurement, in particular to a radiation data calibration method for a regional radiation monitor, which comprises the following steps of: according to the variation trend of data in a local range of each moment in a radiation slope sequence of each position and the difference of time intervals between all adjacent extreme points in a radiation data curve, calculating the radiation data of the regional radiation monitor; obtaining the interference degree of the radiation data at each moment of each position; according to the correlation degree between the radiation data sequence of each position and the radiation data sequence of other positions and the interference degree, the corrected interference degree of the radiation data of each moment of each position is obtained; and correcting the radiation data of all positions at each moment according to the distribution of the radiation data of all positions at each moment in the region and the corrected interference degree to obtain the radiation data after region calibration. According to the invention, the accuracy of regional radiation data monitoring is improved.

One variation of a system includes a pressure vessel: including a wall; defining a primary working fluid circuit extending vertically within the wall; defining a secondary working fluid circuit extending vertically within the wall and fluidly isolated from the primary working fluid circuit; and configured to store a nuclear fuel, a primary working fluid, and a secondary working fluid. The wall of the pressure vessel: defines a heat exchanger configured to transfer thermal energy from the primary working fluid flowing through the primary working fluid circuit into the secondary working fluid flowing through the secondary working fluid circuit; and defines a radiation shield configured to attenuate radiation emitted by the nuclear fuel.

The invention relates to the technical field of intelligent evaluation and early warning methods, in particular to a nuclear radiation dose space distribution intelligent evaluation and early warning method and system, and the method comprises the following steps: obtaining multi-source monitoring data which comprises gamma radiation dose, alpha radiation dose and beta radiation dose measuring instrument data; performing fusion and enhancement processing on the multi-source monitoring data to obtain an enhanced radiation monitoring signal; based on the enhanced radiation monitoring signal, high-precision prediction of nuclear radiation dose spatial distribution is carried out through a deep probabilistic neural network model; according to the high-precision prediction result, in combination with a nuclear accident severity level standard, a radiation alert evaluation result and early warning information are generated, short-term radiation fluctuation can be captured, a long-term change trend can be identified, and the understanding ability of the system to a complex radiation field is greatly improved.

An infusion system may include a radioisotope generator that generates a radioactive eluate via elution, a beta detector, a gamma detector, and a controller. The beta detector and the gamma detector may be positioned to measure beta emissions and gamma emissions, respectively, emitted from the radioactive eluate. In some examples, the controller is configured to calibrate the infusion system using the gamma detector. For example, the controller may generate a radioactive eluate and measure the activity of the radioactive eluate using both the beta detector and the gamma detector. The high accuracy of the activity measured by the gamma detector may be used to calibrate the infusion system. In subsequent use, the infusion system calibrated using the gamma detector may adjust measurements made to monitor and / or control patient infusion procedures.

The invention relates to the field of medical equipment, and provides a compact multi-chamber proton treatment system based on a shared beam line, and the system comprises a fixed beam transmission line which is used for guiding the movement direction of a proton beam into a vertical direction; the rotating beam transmission line is used for guiding the movement direction of the proton beam into the horizontal direction; one end of the fixed beam transmission line is connected with the proton cyclotron, the other end of the fixed beam transmission line is connected with one end of the rotary beam transmission line, and the other end of the rotary beam transmission line is in butt joint with a plurality of treatment rooms; the rotating beam transmission line rotates around a central axis extending in the vertical direction. According to the invention, the proton beam can be safely, efficiently and accurately transmitted to each treatment room, and a fixed beam transmission system and a rotating rack do not need to be independently arranged for each treatment room, so that the beam control assembly and the system occupied area of the multi-room particle treatment device are minimized, and the number of treated patients can be remarkably increased.

Electroporation-based therapies (EBTs) employ high voltage pulsed electric fields (PEFs) to permeabilize tumor tissue, resulting in changes in passive electrical properties detectable using electrical impedance spectroscopy (EIS). Currently, commercial potentiostats for EIS are limited by impedance spectrum acquisition time (˜10 s); this timeframe is much larger than pulse periods used with EBTs (˜1 s). Fourier Analysis SpecTroscopy (FAST) is introduced as a methodology for monitoring tissue inter-burst impedance (diagnostic FAST) and intra-burst impedance (therapeutic FAST) during EBTs. FAST is a rapid-capture (<<1 s) technique which enables monitoring of inter-burst and intra-burst impedance during EBTs in real-time. FAST identified a frequency which delineates thermal effects from electroporation effects in measured impedance. Significance: FAST demonstrates the potential to perform EIS, in addition to intra-burst impedance spectroscopy, using existing pulse generator topologies.

The invention relates to the technical field of frequency conversion control, and discloses a frequency conversion control method and system for a nuclear power station ventilation system, and the method comprises the steps: collecting the multi-region real-time operation data of the nuclear power station ventilation system, and carrying out the standardization processing, and obtaining a standardized data set; performing fan performance curve fitting and differential pressure field feature mapping on the standardized data set to obtain differential pressure field mapping features; the differential pressure field mapping features are input into an active neural differential pressure field network model for frequency conversion parameter prediction, and target frequency conversion control parameters are obtained; feedforward-feedback combined control is conducted on the target frequency conversion control parameters through the multi-mode frequency conversion controller, the fan rotating speed and the air valve opening value are obtained, the target frequency conversion control parameters can be generated in a self-adaptive mode, the control performance is remarkably improved, and smooth transition of the nuclear power station ventilation system is achieved.

The invention discloses a processing method of a fusion device, and belongs to the technical field of nuclear fusion. The processing method comprises the following steps: carrying out at least one time of vacuum heat treatment on a Dewar embedded part blank; carrying out cleaning anti-corrosion treatment and physical correction treatment on the surface of the dewar embedded part blank subjected to heat treatment; carrying out grinding and polishing treatment on the surface of the Dewar embedded part blank subjected to the cleaning and antiseptic treatment and the physical correction treatment to obtain the Dewar embedded part; the Dewar embedded part is transported to the installation position of the window to be installed, and the Dewar embedded part located at the installation position is temporarily fixed; performing concrete pouring on the mounting position of the Dewar embedded part; and after the concrete is solidified, a cast-in-place concrete structural body is formed in the area below the Dewar embedded part, and a part of the Dewar embedded part is embedded into the cast-in-place concrete structural body. By means of the method, the magnetic conductivity of the Dewar embedded part is reduced, and the risk that elements are activated to form isotopes with the long decay period and the high irradiation dose rate or isotopes with the short decay period and the high irradiation dose rate is reduced.

An integral molten salt nuclear reactor includes a drain tank section configured to hold a volume of fuel salt. The integral molten salt nuclear reactor further includes a reactor section configured to receive the volume of fuel salt from the drain tank and cause fission reactions that heats the molten salt. The integral molten salt nuclear reactor further includes a heat exchange section configured to receive a flow of the heated fuel salt from the reactor section and remove heat therefrom.

The present application relates to the field of nuclear reactor simulation. Disclosed are a fast simulation method and system for multi-physical field coupling and a storage medium. The method comprises: at intervals of a first preset interval time, collecting state information of each physical field of a nuclear reactor in a transient process, so as to obtain physical field snapshots of a plurality of physical fields, the transient process being simulated by a reactor simulation model corresponding to the nuclear reactor; stitching the physical field snapshots of the plurality of physical fields, so as to obtain a fully-concatenated physical field; constructing a matrix on the basis of the fully-concatenated physical field; performing order reduction processing on the matrix, so as to construct a timing model corresponding to the fully-concatenated physical field; and decomposing the timing model corresponding to the fully-concatenated physical field, so as to obtain timing models corresponding to the plurality of physical fields. The fast simulation method for multi-physical field coupling of the present application can reduce the inconsistency between different physical fields while increasing the computation speed.

The utility model relates to the technical field of electron beam transmission, in particular to a magnet system. Comprising a first shaping unit and a second shaping unit, and the first shaping unit comprises first quadrupole iron tightly attached to an outlet of the accelerating tube and first octupole iron arranged at the focus position of the first quadrupole iron; the second shaping unit comprises second quadrupole iron and second octupole iron, the second quadrupole iron and the first octupole iron meet a first preset distance, the second octupole iron is arranged at the focus position of the second quadrupole iron, and the second shaping unit and the radiation field area meet a second preset distance; the inner diameter of the first octupole iron and the inner diameter of the second octupole iron are both larger than or equal to the maximum size of an electron beam group. Therefore, the quadrupole iron and the octupole iron are utilized to form the shaping unit which is homogenized in one direction, so that the problems that in the prior art, in the electron beam transmission process, a large amount of dose is lost, the size of a radiation field is limited, and the radiation field cannot be adjusted at will are solved; therefore, the electron beam bunch generated by the linear accelerator can be expanded and homogenized in a short distance.

A positron emission tomography (PET) scanner includes a plurality of gamma radiation detector modules arranged to form a detector ring. Each detector module includes an array of scintillator detectors. Each scintillator detector comprises a monolithic scintillation crystal and a plurality of photodetector arrays, such as silicon photomultipliers (SiPMs). A photodetector array is positioned on at least two nonparallel faces of each scintillation crystal. In some examples, a photodetector array is positioned on each of three orthogonal faces of each scintillation crystal.

The present disclosure discloses an integrated rapid treatment system for nuclear medical radioactive wastewater and an application method thereof. This system includes a wastewater collection unit; a pretreatment unit; a deep purification unit; a solid decay unit; a buffer unit; an online monitoring unit; and a control unit, wherein the online monitoring unit includes a radioactivity level detection module for detecting total α and total β radioactivity concentrations of inlet and outlet water of a medium in each unit, and a real-time monitoring module for treatment process parameters. The present disclosure discloses an integrated rapid treatment system for nuclear medical radioactive wastewater and an application method thereof, which can efficiently and quickly purify multi-nuclide organic low-level wastewater produced by a nuclear medical process, and realize rapid online monitoring and automatic control at the same time.

The invention relates to the technical field of isotope production, in particular to a welding-free target capsule for isotope production and a manufacturing method of the welding-free target capsule. The welding-free target capsule comprises a target material used for generating isotopes under bombardment of high-energy particles; the first metal film covers one side of the target material; the second metal film covers the other side of the target material; wherein the first metal film and the second metal film are made of materials with ductility; the edge of the first metal film and the edge of the second metal film are attached to each other on the peripheral side of the target material and are folded into an annular sealing structure. In the invention, the metal film with good ductility is used as a coating material of the target material, and the sealing structure is formed by folding the connecting part of the metal film, so that the target capsule can be ensured to efficiently dissipate heat in a water-cooling environment, the manufacturing mode of the sealing structure can be improved, the manufacturing steps of the sealing structure are simple and easy to implement, and the manufacturing cost of the target capsule is further reduced.

A method comprises: providing FIB and CPB columns with FIB and CPB optical axes coinciding at a wafer surface; in the coincidence arrangement, removing a cross section surface layer of a measurement site of a wafer using the FIB column to make a new cross section accessible for imaging; reducing a working distance between the CPB imaging column and the wafer surface in a direction along the axis of the CPB imaging column; imaging the new cross section at the measurement site of the wafer with the CPB imaging column at the reduced working distance and thus not in the coincidence arrangement; and increasing the working distance between the CPB imaging column and the wafer surface in the direction along the axis of the CPB imaging column until the coincidence arrangement is reached.

The invention relates to the technical field of laser welding, and discloses a laser machining device and method for a nuclear reactor shell, and the method comprises the steps that a shell plate welding area to be welded is subjected to surface modification pretreatment; the laser processing device is used for carrying out initial welding on the pretreated shell plate, in the initial welding process, the temperature sensing assembly is used for monitoring temperature distribution of the welding area in real time, and temperature information of the welding area is obtained; the temperature information is input into a preset temperature-deformation prediction model for prediction of a variable trend and a stress distribution condition so as to obtain a first prediction result; based on the obtained first prediction result, the welding parameters of the laser processing device are dynamically adjusted for the first time; welding deformation and stress concentration are effectively coped with, the welding quality and structural strength of the nuclear reactor shell after laser welding are improved, and the reliability and safety of the nuclear reactor shell during use are effectively improved.

The invention provides a microdosimetry-based evaluation method for a targeted alpha radionuclide treatment biological effective dose, and the method comprises the steps: carrying out the integration of a time activity curve of alpha radionuclide in an organ, obtaining the cumulative activity, and calculating the physical absorbed dose and dose rate of the organ through Monte Carlo simulation; based on micro-dose Monte Carlo simulation, constructing a micro-dose spectrum of the alpha radionuclide to obtain saturation correction dose average linear energy for representing radiation quality; obtaining biological effect parameters of the alpha radionuclide by fitting saturation correction dose average line energy and cell experiment data by using a micro-dose kinetic model; and evaluating the biological effective dose of the target organ in combination with the physical absorbed dose, the dose rate and the biological effect parameter. According to the method, the problem that a biological effective dose evaluation method is lacked in dose evaluation of targeted alpha radionuclide treatment is solved.

The invention discloses a method and tool for manufacturing a cold shield of a nuclear fusion device, and relates to the technical field of metal plate machining. The manufacturing method of the cold shield of the nuclear fusion device comprises the following steps: providing a sub-panel, a flange and a pipe fitting; the multiple sub-panels are welded, and a first middleware is obtained; welding the edge of the first middleware and the turnup to obtain a second middleware; after the pipe fitting is welded to the surface of the second middleware, a third middleware is obtained; and the third middleware is shaped. According to the method, the third middleware is shaped, that is, the third middleware is shaped after all welding procedures are completed, so that the third middleware has relatively small profile tolerance, the profile tolerance of the cold shield meets the design requirement, the assembly difficulty of the cold shield is reduced, and the risk of failure of the cold shield is reduced.

Apparatus, techniques and systems are described for facilitating identification of a target area during a probe-guided radio-localization surgical procedure. The described apparatus, techniques and systems can be used to implement a nuclear-uptake mode controller integrated into a probe to allow a user to instantly switch between multiple nuclear-uptake modes directly from the probe hand-piece. For example, a nuclear-uptake mode controller integrated into the probe can be used to instantly switch between a high-sensitivity nuclear uptake mode and a high-resolution nuclear-uptake mode toeffectively identify the target area in the presence of interfering nuclear signals by better matching the probe's nuclear detection parameters to a search task for that target area.

The invention relates to the technical field of scintillator materials and X-ray detection, in particular to a rare earth organic-inorganic hybrid complex scintillator and a preparation method and application thereof. The general formula of the rare earth organic-inorganic hybrid complex scintillator is [RE (L) 4] <->. [A] < + >, wherein RE is selected from Eu, Tb, Sm or Dy; l is a beta-diketone ligand; [A] < + > is selected from long-chain hydrophobic quaternary ammonium salt cations or heterocyclic quaternary ammonium cations which have the carbon atom number of C8-C20 and do not contain active functional groups. The rare earth organic-inorganic hybrid complex scintillator provided by the invention has good solubility and molecular-level dispersion capability. The scintillator film based on the rare earth organic-inorganic hybrid complex prepared by using the rare earth organic-inorganic hybrid complex has the characteristic of compatibility of high scintillator load and high light transmission, overcomes the problems of low scintillator load rate, poor transparency and limited imaging resolution of the traditional scintillator film, and has excellent practical value and popularization prospect.

The invention provides a radiotherapy plan generation method and device and a storage medium, and relates to the technical field of medical treatment, in particular to the technical field of radiotherapy. According to the specific implementation scheme, the method comprises the steps of predicting reference dose distribution and a reference flux graph of a to-be-radiotherapy object; taking the reference dose distribution and the reference flux diagram as objective functions, and executing reverse optimization to obtain an optimized flux diagram; and generating a radiotherapy plan based on the flux graph. Therefore, reverse optimization based on the flux diagram is realized, and the reverse optimization process also refers to the reference dose distribution and the reference flux diagram, so that the optimized flux diagram is more suitable for an actual application scene, and the accuracy of a radiotherapy plan obtained according to the optimized flux diagram is improved.

The invention provides a multi-nuclide radioactive activity concentration detection method, system and device and a storage medium, and relates to the technical field of radioactive solid waste detection. The detection method comprises the following steps: acquiring attribute information of a to-be-detected sample; obtaining a detection result; acquiring activity proportions of various nuclides; based on the activity proportion of each type of nuclide, determining the activity proportion of each type of nuclide easy to measure and a scale factor between each type of nuclide difficult to measure and the nuclide easy to measure; based on the material type, the volume and the density of the to-be-detected sample, determining the detection efficiency corresponding to each type of easily-detected nuclide; and determining the radioactive activity concentration of each type of nuclide based on the quality of the sample to be detected, the detection result, the detection efficiency of each type of easy-to-detect nuclide, the activity proportion of each type of easy-to-detect nuclide and the scale factor between each type of difficult-to-detect nuclide and easy-to-detect nuclide. The radioactive activity concentration of the easily-detected nuclide in the sample to be detected and the radioactive activity concentration of the difficultly-detected nuclide which cannot be effectively detected by detection equipment are accurately obtained, and high-sensitivity detection and evaluation of the sample to be detected are realized.

An apparatus comprising a radiation source, coincident positron emission detectors configured to detect coincident positron annihilation emissions originating within a coordinate system, and a controller coupled to the radiation source and the coincident positron emission detectors, the controller configured to identify coincident positron annihilation emission paths intersecting one or more volumes in the coordinate system and align the radiation source along an identified coincident positron annihilation emission path.

The invention discloses a method and a system for rapidly measuring the concentration of radioactive radon in air in a gas flow mode based on scintillation. According to the method, the net counting rate of alpha particles is measured based on a scintillation method, and the net counting rate of the alpha particles in a corresponding time period needs to be obtained during measurement; in combination with a radon and daughter decay rule and a chamber ventilation condition, establishing a relationship between the net count of alpha particles generated by radon and daughter decay in newly sucked air in a corresponding measurement time period in the measurement chamber and the volume, the pump speed and the original air radioactivity concentration in the chamber; and a corresponding sensitivity coefficient for measuring the radioactive radon concentration of the to-be-measured air is obtained, so that the radioactive radon concentration of the to-be-measured air is obtained in real time. According to the method, the radioactive radon concentration in the air can be rapidly measured in real time under the dynamic gas flow type condition, the measurement time can be greatly saved, the change of the radon concentration in the air can be reflected in time, workers and the public can be protected against the harm of radon radiation, safety production of the nuclear industry can be promoted, and the method has wide application prospects.

The invention discloses an ocean in-situ radioactivity monitoring method, which is characterized in that feature extraction is carried out based on a maximum likelihood expected value maximization (MLEM) algorithm, and spectrum unfolding operation is carried out by adopting a multi-layer perceptron. The method comprises the following steps: firstly, measuring FWHM related parameters of a CeBr3 detector by adopting a standard source, simulating the response of the detector to gamma rays in a marine environment based on a Monte Carlo method, and establishing a full-spectrum response matrix H in a range of 0-2048keV; based on the response matrix H, reconstructing a gamma energy spectrum y obtained by the detector by using an MLEM iterative algorithm; and the reconstructed spectrum is used as the input of a multi-layer perceptron (MLP), and qualitative and quantitative analysis of radionuclides in the energy spectrum is realized. According to the method, the discrete characteristic peak signal is convolved into the single path address corresponding to the characteristic energy, so that the accuracy of the MLP model in the spectrum unfolding process is effectively improved.

The invention belongs to the technical field of polypeptides, and discloses a polypeptide targeting HER2 protein, a radioactive polypeptide and a preparation method and application of the radioactive polypeptide, and the structural formula of the radioactive polypeptide is as follows: # imgabs0 #. Through in-vitro radiochemical property research and in-vivo stability research, the 68Ga-DOTA-AON is found to be high in stability and hydrophilic; through cell uptake research and receptor binding force research, the 68Ga-DOTA-AON is found to have relatively high affinity to HER2 protein expressed by HT-29 cells; the tumor imaging effect of the radioactive polypeptide 68Ga-DOTA-AON is investigated through small animal PET / CT, and it is found that [68Ga] Ga-DOTA-AON can be used for in-vivo imaging of HER2 positive colorectal cancer.

The invention belongs to but is not limited to the technical field of three-dimensional space dose visualization, and discloses a three-dimensional nuclear emergency radiation field calculation and visualization method and system, based on a point nuclear method, a cumulative factor, mass attenuation factor and flux rate-dose rate conversion factor database is established, a mean free path solving algorithm is optimized, and a three-dimensional nuclear emergency radiation field is obtained. The geometric types of radioactive sources are expanded, and the dose calculation efficiency is improved through parallel calculation; plane dose rate drawing at a certain height is realized based on a two-dimensional texture mapping method; three-dimensional space dose rate contour surface drawing is realized based on a moving cube algorithm; and three-dimensional space dose rate volume rendering is realized based on a three-dimensional texture volume rendering technology. Radiation field dose calculation, three-dimensional radiation field dose visualization and GIS are integrated, and the system is used as a subsystem of a nuclear emergency aid decision simulation platform. The dose distribution diagram in the area can be judged more visually, and the method has a good help effect on nuclear emergency command.