603 results about "Gamma ray" patented technology

The invention discloses a nuclear radiation index early warning system based on multi-algorithm fusion, and the system comprises an environment data collection module which is used for collecting gamma-ray dose rate data, wind speed data, wind direction data and geographic position information, and constructing a nuclear radiation environment data set; the dose rate prediction module is used for predicting a future change trend of gamma ray dose rate data based on a sparse recurrent neural network model; the anomaly detection module is used for identifying an abnormal mutation point and positioning the position of a high-risk sensor; the diffusion region modeling module is used for calculating a nuclear radiation diffusion influence region; the grid risk evolution module is used for simulating time sequence evolution of a regular grid risk state based on the multi-state cellular automaton; and the fusion judgment module is used for fusing output results and generating a final early warning grade and a spatial risk distribution result. According to the invention, accurate prediction of the nuclear radiation risk and dynamic space early warning are realized, and the early warning accuracy and response efficiency are significantly improved.

The invention provides an ore grade analysis method. The ore grade analysis method comprises the following steps: generating an X-ray beam by utilizing a radiation source; x-ray beams are utilized to irradiate the ore, target element nuclides in the ore are excited to generate a nuclear resonance fluorescence effect, target characteristic gamma rays are emitted, and the energy of the X-ray beams is higher than the excitation energy of the target element nuclides; when the X-ray beam is utilized to irradiate the ore, a standard sample containing a reference nuclide is irradiated, the reference nuclide is excited to emit a reference characteristic gamma ray, and the reference nuclide is expressed as a nuclide with known content and known characteristic gamma ray energy; detecting the energy of a target characteristic gamma ray and the energy of a reference characteristic gamma ray; and determining the grade of the target element in the ore based on the energy of the target characteristic gamma ray and the energy of the reference characteristic gamma ray.

The invention discloses an element analysis device based on a high-yield DD neutron generator. The device is composed of a neutron source item system, a neutron shielding collimation wall, a detector shielding protection system, a detected sample system, a signal acquisition system and a data analysis system. A neutron beam is generated through (D, D) nuclear reaction and irradiates a sample after passing through a neutron moderation layer and a shielding collimation wall, so that the sample generates instant characteristic gamma rays. A shielding protection system with unique design effectively reduces background gamma ray interference and electromagnetic interference, and ensures that the detector accurately collects sample signals. By matching with an advanced signal acquisition and analysis system, the element components and content of the sample can be analyzed at high precision. In addition, the device can be combined with a neutron imaging system to obtain sample structure information. The method has great application potential in the fields of industrial production, scientific research and detection and the like, and can meet the requirements of high-precision element analysis on small-size samples.

The invention relates to the technical field of CLYC neutron-gamma rays, and provides a CLYC neutron-gamma ray screening detection method and device based on deep learning, and the method comprises the steps: carrying out the preprocessing of an original pulse waveform outputted by a CLYC detector, and obtaining clean standard waveform data; constructing a one-dimensional convolutional neural network model, respectively capturing the features of the waveform at different time scales, and identifying the most discriminative feature region in the waveform through an attention mechanism; performing adaptive adjustment on the original hyper-parameter of the one-dimensional convolutional neural network model to obtain an optimized hyper-parameter; establishing a direct mapping relation from an original pulse waveform to a neutron-gamma particle type to obtain a trained model; and carrying out compression optimization processing on the model, and deploying the model to an embedded platform to carry out neutron-gamma ray discrimination. According to the method, automatic extraction of deep discrimination features of the CLYC pulse waveform and accurate identification of key feature areas are realized, and the discrimination accuracy and noise interference resistance of neutron-gamma rays are improved.

The invention discloses a hybrid neutron gamma detector array and a signal processing method, and relates to the technical field of nuclear physical detection.During detection, eight EJ200 scintillators arranged in an array are used for energy deposition of gamma rays and fast neutrons and generating photons, and meanwhile three EJ426 thermal neutron scintillation screens are used for capturing thermal neutrons and generating photons; the response of gamma rays, fast neutrons and thermal neutrons is realized at the same time, and the detection precision is greatly improved. Meanwhile, if the three EJ426 thermal neutron scintillation screens are alternately stacked front and back, the total reflection of the EJ200 scintillators and the semi-light-proof performance of the EJ426 thermal neutron scintillation screens are utilized to block photon propagation in the X direction and only enable photons to be propagated in the Y direction and the Z direction, and each EJ200 scintillator corresponds to a four-channel photon collection structure to perform high-efficiency collection of the photons, so that the high-efficiency collection of the photons is realized. Therefore, high-precision detection and high-efficiency photon collection are realized, and support is provided for subsequent intense radiation field monitoring or high-precision positioning.

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

The invention relates to a method for detecting a coal seam interface while drilling, relates to the technical field of geological exploration, overcomes the limitation of a single physical field by using multi-modal fusion of electromagnetic waves, sound waves and gamma rays, remarkably improves the detection precision, greatly reduces the identification error of a thin coal seam compared with a traditional method, and improves the identification success rate of a complex structural region (fault and dirt band). Preliminary response within 1s is realized through underground edge calculation, decision lag is compressed to 1.5 s through ground cooperative processing, and leap of data real-time performance and predictive capacity is realized; the front 0.5-1.5 m prediction function gains time for track adjustment, and the risk of penetrating out of the coal seam is reduced. The multi-sensor redundancy design still keeps the signal-to-noise ratio not less than 20dB in a strong noise environment, the detection success rate is greatly improved when mud invasion is serious, and the environmental adaptability is high. The coal seam drilling rate is increased, invalid footage is reduced, the single well comprehensive cost is reduced, and economic benefits are remarkably improved.

The invention belongs to the technical field of special glass preparation, and particularly relates to radiation-proof glass as well as a preparation method and application thereof. The radiation-proof glass is prepared from the following oxides in percentage by mass: 30 to 45 percent by weight of SiO2, 10 to 25 percent by weight of B2O3, 7 to 12 percent by weight of BaO, 1 to 5 percent by weight of ZnO, 1 to 5 percent by weight of CeO2, 15 to 24 percent by weight of La2O3, 5 to 9 percent by weight of Gd2O3, 1 to 5 percent by weight of Ga2O3, 1 to 5 percent by weight of WO3 and 1 to 4.9 percent by weight of HfO2. The radiation-proof glass has the following advantages that the radiation-proof glass does not contain any one of heavy metal oxides such as As2O3, Sb2O3, PbO, Tl2O, CdO, BeO and V2O5 harmful to the environment, the shielding rate of the glass is larger than or equal to 96%, and the radiation-proof glass is excellent in optical uniformity, chemical stability and mechanical performance and good in anti-radiation performance. The invention further provides application of the radiation-proof glass in medical treatment, nuclear power and nuclear physics experiment protection and gamma ray protection.

An apparatus and method are provided to correct for time-walk errors during photon detections (e.g., detecting gamma rays). A time-walk correction is determined using measurements of energy (or charge) that apply different time windows, enabling corrections accounting for variations in the ratio between fast and slow components in the detected pulse. For example, one time window can be used to integrate the leading end of the pulse, thereby predominantly measuring the fast component, while a second window is used to integrate a trailing end of the pulse to predominantly measure the slow component. Alternatively or additionally, low-pass and high-pass filters may select the slow and fast components, respectively. The time-walk correction is a function of multiple measurements representing different components (e.g., fast and slow) of the pulse shape.

The invention relates to the technical field of nuclear radiation detection management, and discloses a nuclear radiation detection management system based on artificial intelligence, comprising: a dynamic sensing module which detects nuclear radiation through quantum sensing to obtain radiation data, captures NV color center fluorescence intensity, analyzes to obtain gamma ray dose rate, constructs a nanoscale olfactory receptor simulation structure, and sends the radiation data to a control module; radioactive gas is detected and cooperatively monitored; the reasoning calculation module is used for analyzing space-time correlation based on radiation data, optimizing algorithm to accelerate result output, adjusting calculation complexity by calculating dynamic weight distillation, and correcting data transmission in real time; the decision management module is used for constructing a four-dimensional causal graph based on the radiation data, performing intervention simulation, evaluating a decision long-term effect, screening an optimal decision, and performing adversarial training based on historical repair case data; and the fusion cooperation module is used for establishing a cross-mechanism federated learning framework, carrying out hash operation on the radiation data, and establishing an NFT (Network Fourier Transform) on a block chain through an intelligent contract for query, verification and transaction.

The invention relates to the technical field of steel smelting scrap steel briquette treatment, and particularly provides a neutron generator-based scrap steel briquette component online detection device and method. Neutrons generated through nuclear reaction of a neutron generator are absorbed and activated with elements such as Fe in the scrap steel, gamma rays with characteristic energy are emitted, then the energy intensity of the gamma rays is observed, contrasted and calibrated from the response of a detector, and therefore the content composition and the content proportion of all the elements, mainly the Fe element, in the scrap steel briquette are calculated, analyzed and determined. The device effectively avoids the low-quality employment risk in the detection of the scrap steel briquettes, solves the problems that the detection of the internal quality of the scrap steel briquettes is difficult, time-consuming and labor-consuming, remarkably improves the working efficiency and effect, and has remarkable economic benefits and popularization prospects.

A detector system for molecular imaging of a radionuclide comprises a 3D semiconductor detector comprising a plurality of sensor stacks of sensors made of a semiconductor material having an average atomic number Z below 40. A read-out circuitry connected to the pixels is configured to output, for each interaction induced by an incident gamma ray in the detector, a signal representative of a time, a position and an energy of the interaction in the detector. The interactions in the detector belonging to a same event induced by the incident gamma ray are predicted based on the output signals and used to estimate a direction of the incident gamma ray and reconstruct an image based on the estimated directions of incident gamma rays.

The invention provides a gamma imaging noise reduction detector based on depth information, which comprises a layered probe, a host and an acquisition circuit, and is characterized in that the layered probe is of a multi-layer structure formed by arranging single-layer position sensitive probes front and back; the acquisition circuit acquires timestamps, positions and amplitude information of the electric pulse signals; the host is responsible for collecting the number of the collection circuit and generating a detector image, forming the same particle event by using the electric pulse signals with the same timestamp, and determining thickness direction information of activated pixel data corresponding to each electric pulse signal through the number of the collection circuit. And only the data of the foremost activation pixel in the thickness direction is accumulated into the detector image. According to the method, a thick detector is divided into layered probes to obtain depth information of particle energy deposition, so that the noise influence caused by scattering in a detector crystal in medium-high energy gamma ray imaging is reduced, a first scattering point is speculated to eliminate secondary scattering noise of medium-high energy gamma rays, and the contradiction between the imaging speed and the imaging quality is solved.

Means and method for photo-enhanced electro-catalytic process using nuclear thermal NTAC-integrated PEEC (PEEC-NTAC) catalytic processes combining ECM with energetic photon sources, such gamma rays, and sono-catalytic driver.

The invention provides a radiation detection device and method for measuring ultra-wide-range gamma rays, and relates to the technical field of radiation detection.The radiation detection device comprises a detection assembly, a radiation shielding assembly and a signal processing assembly, and the signal processing assembly is located in the radiation shielding assembly; the detection assembly comprises three GM counting tubes with different measuring ranges and an acquisition circuit, and the acquisition circuit is used for converting signals output by the GM counting tubes into voltage counting signals; the signal processing assembly comprises a high-voltage control circuit, a power supply processing circuit, a pre-amplification circuit and a processor, the power supply processing circuit is used for converting a direct-current power supply signal and then transmitting the converted direct-current power supply signal to the high-voltage control circuit and the acquisition circuit, and the high-voltage control circuit is used for outputting a high-voltage power supply signal to each GM counting tube; the pre-amplification circuit is used for filtering and amplifying the voltage counting signals, and the processor is used for determining a target radiation dose rate according to the processed voltage signals. The radiation detection device provided by the invention has a relatively wide measuring range and relatively high measurement precision.

The invention discloses a compact high-energy gamma generator for special nuclear material checking and a checking method.The gamma generator comprises a shell and an ion source, the shell is internally provided with a high-pressure vacuum cavity, the ion source is arranged at the left end of the high-pressure vacuum cavity, the right end of the high-pressure vacuum cavity is provided with a high-pressure connector system, and the left end of the high-pressure connector system is connected with a leading-out accelerating electrode; a target holder is arranged in the extraction accelerating electrode, and a boron target sheet is mounted on the target holder; negative high voltage is fed into the extraction accelerating electrode through the high-voltage connector system, an electric field is formed between the extraction accelerating electrode and the anode of the ion source, the proton beam is extracted and accelerated by the electric field and then bombarded on the boron target sheet, 11B (p, gamma) 12C resonance radiation capture reaction is carried out, and high-energy gamma rays are released; the gamma ray and the special nuclear material are subjected to a photofission reaction to emit instant neutrons and delayed neutrons, and the detection of the special nuclear material is realized by measuring the instant neutrons and the delayed neutrons. The device is compact in structure, high in detection sensitivity, short in detection time, low in interference and long in service life, and has very high application value.

A back illuminated sensor is included as a collector component of a detector for use in intraoral and extraoral 2D and 3D dental radiography, digital tomosynthesis, photon-counting computed tomography, positron emission tomography (PET), and single-photon emission computed tomography (SPECT). The disclosed imaging method includes one or more intraoral or extraoral emitters for emitting a low-dose gamma ray or x-ray beam through an examination area; and one or more intraoral or extraoral detectors for receiving the beam, each detector including a back illuminated sensor. Within the detector, the beam is converted into light and then focused and collected at a photocathode layer without passing through the wiring layer of the back illuminated sensor.

The invention relates to a method for detecting boron distribution in an oxidation corrosion product deposition layer. The total mass of boron in the oxidation corrosion product deposition layer is detected by utilizing an instantaneous gamma activation technology; the method comprises the following steps: obtaining a geometric boundary of a deposition layer of a corrosion product according to neutron photography, constructing a Compton cone in the geometric boundary obtained by neutron photography according to instant gamma rays generated by the oxidation corrosion product and Compton scattering information generated by the action of a Compton photography unit, and reconstructing the origin of the gamma rays; and carrying out pixelated image reconstruction by adopting a random origin set algorithm to obtain a distribution image generated by gamma rays so as to obtain the proportional distribution of the boron element in the oxidation corrosion product deposition layer. According to the obtained total boron element concentration and boron element proportion distribution, boron element concentration distribution in the oxidation corrosion product deposition layer is calculated, and the defects that only boron element distribution in the limited depth of the surface of the corrosion product deposition layer can be measured and internal element distribution information cannot be obtained in an existing method are overcome.

The invention discloses a method for efficiently generating high-brightness gamma radiation, and belongs to the technical field of radiation. A relativistic electron beam is injected into the porous microstructure foam target material, and high-brightness gamma ray radiation is generated. According to the method, the used device is simple, only the single relativistic electron beam and the porous microstructure foam target material are needed to interact, compared with a traditional uniform-density solid material, the energy conversion efficiency in the interaction process of the electron beam and a substance can be remarkably improved, and the energy conversion efficiency can be remarkably improved through the effective constraint effect of a high-intensity magnetic field. And the problems of low energy conversion rate, low light source brightness, poor radiation directivity, complex device or difficulty in experiment implementation and the like of the existing high-energy gamma ray radiation source are solved.

Provided are a radiation detection element, a radiation detector, and a production method for the radiation detection element that make it possible to measure the energy of radiation with favorable accuracy. A radiation detection element according to the present invention includes: a compound semiconductor crystal substrate that comprises cadmium zinc telluride to which indium has been added as an impurity; and a metal electrode that is provided on the surface of the compound semiconductor crystal substrate. The energy resolution for gamma rays of 122 keV emitted from 57Co is no more than 7%.

Described herein are systems and techniques for improving the accuracy of computer models that determine properties of subterranean rock formations. Such systems and methods may perform multiple sets of calculations using data collected by different types of sensing devices that may be deployed in a wellbore. For example, a first set of inversions may be made on data collected by an electromagnetic (EM) sensing device and a second set of inversions may be made using EM data and data collected by a gamma ray (GR) sensing device. Such methods may be useful when making determinations regarding subterranean features that include laminated structures. For example, when rock structures include layers of sand and layers of shale.

The invention discloses a radiation shielding method and a radiation shielding body based on a multi-physics field synergistic effect, and the radiation shielding body is used for shielding a neutron-gamma mixed radiation field, and the radiation shielding method based on the multi-physics field synergistic effect comprises the steps: a first stage, absorbing neutrons and gamma rays at a radiation initial position through a first composite material; in the second stage, energy spectrum adaptive attenuation is carried out on the first residual radiation passing through the first stage through a second composite material, and the amount of the second composite material is gradually decreased in a gradient mode in the radiation propagation direction; and a third stage of performing path scattering on the second residual radiation passing through the second stage through a third composite material. According to the invention, the technical problem of insufficient shielding capability caused by difficulty in adapting to the dynamic shielding requirement of a neutron-gamma mixed radiation field when a traditional anti-radiation shielding body faces the neutron-gamma mixed radiation field generated in a BNCT treatment scene is solved.

A system and a method for a pulsed neutron logging tool. The pulsed neutron logging tool may include a pulsed neutron generator for generating one or more neutrons, one or more gamma ray scintillator detectors disposed in a detection area, a shielding block that separates the pulsed neutron generator from the one or more gamma ray scintillator detectors, and a shielding layer. The pulsed neutron logging tool may further comprise an information handling system communicatively connected at least in part to the pulsed neutron logging tool. The information handling system is configured to create a gamma ray spectrum from the one or more gamma rays detected by the one or more gamma ray scintillator detectors, remove a background from the gamma ray spectrum to form a peaks-only spectrum, and compare one or more peaks-only elemental standards to the peaks-only spectrum to determine an elemental weight and yield.

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

The invention belongs to the technical field of nuclear physics and particle accelerators, and relates to a high-precision wide-energy-spectrum neutron source target body structure applied to a spallation neutron source device. The method comprises the following steps: a tungsten target is adopted, and a 6cm thin target design is adopted; the cooling layer contains boron water and the like and can be used for cooling and slowing down neutrons; the moderation layer moderates the neutron energy spectrum to a thermal neutron energy region by using boron-containing water; the shielding layer is made of low-carbon steel and concrete to ensure radiation safety; the tail end of the neutron channel is connected with an experimental terminal; according to the thin target design, the energy resolution is improved, the energy resolution of neutrons below 100 keV is higher than 0.1%, and the energy resolution of neutrons below 1 MeV reaches 0.3%; the boron element reduces the gamma ray background; and the five neutron pore channels meet various requirements. The overall design realizes the effect required by the high-precision neutron experiment and improves the precision of the device.

The invention discloses a composite shielding collimator suitable for a complex mixed radiation field, belongs to the technical field of radiation shielding and measurement, and mainly solves the problems of low signal-to-noise ratio, high space background and mixed energy spectrum caused by the mixed radiation field of high-energy neutrons, gamma rays and the like in a fusion device and the problem that traditional equipment is heavy and difficult to flexibly adjust. The composite shielding collimator adopts a cylindrical shielding structure formed by aluminum oxide, boron-containing polyethylene, boron carbide and lead from outside to inside, and background interference and secondary radiation are remarkably inhibited by moderating and absorbing neutrons step by step and effectively shielding gamma rays; the neutron and gamma ray detector is integrally integrated on a rotatable supporting mechanism, unification of excellent radiation shielding performance and detection flexibility is achieved, and the neutron and gamma ray detector is mainly used for high-precision neutron and gamma ray diagnosis in complex radiation environments such as a magnetic confinement fusion device.

A glass material, and a preparation method therefor and the use thereof in the field of radiation shielding. The glass material comprises or consists of the following components in percentages by mass: 45-60% of SiO2; 0.1-1% of BaO; 10-20% of B2O3; 2-5% of CeO2; 1-2% of Al2O3; 2.7-5% of MgO; 0-20% of Na2O; and 9-15% of K2O. The glass material has good performance of shielding α-rays and β-rays, good gamma irradiation resistance and excellent comprehensive shielding performance, still has good transmission, chemical stability and mechanical performance after being irradiated by high-dose gamma rays multiple times, and is more suitable for practical application.

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 nuclear logging gamma-ray spectrum drift correction method based on multi-element characteristic peaks, and belongs to the technical field of nuclear geochemical logging. The method aims at solving the problems that due to the underground high-temperature and high-pressure environment, short-time measurement statistical errors and stratum lithology changes, drift of the relation between channel addresses and energy is caused, and energy spectrum analysis precision is affected. According to the key points of the technical scheme, the method comprises the following steps: preliminarily identifying characteristic gamma ray peak positions of four elements of H, Fe, Si and Ca; a real peak position is approached through interpolation secondary search; calculating zero-cut drift distances and gain change rates of Fe, Si and Ca peak positions by taking the H peak as a reference; weighting according to each peak standard error to obtain a final correction parameter; and re-graduating the energy spectrum by using the parameter to realize the automatic correction of the relationship between the channel address and the energy. The method is mainly used for improving the spectrum unfolding precision and the automatic processing capacity of the instant gamma-ray energy spectrum in geochemical logging, and is suitable for stratum element analysis in oil-gas exploration.

Systems and methods for generating synthetic borehole image logs include logging rate of penetration (ROP) data, resistivity data, and gamma ray data while drilling a borehole in a subsurface formation to generate logged data. The generating includes determining an effective dip angle of the subsurface formation along the borehole and generating a depth shift table based on the effective dip angle and a well deviation angle, the well deviation angle being between the borehole and a vertical reference. Datasets are generated based on the ROP data, resistivity data, and gamma ray data, the generated datasets having higher sampling rates than the logged data. Synthetic borehole images are generated based on the generated datasets and the depth shift table, and the synthetic borehole images are oriented with respect to a reference point of the borehole.