31 results about "Nuclear detection" patented technology

The invention provides a pulse passing rate improving method based on accumulation signal demodulation, and belongs to the technical field of nuclear electronics digital pulse processing. Comprising the following steps: performing baseline deduction and monopulse screening on a radiation field pulse signal; constructing a nuclear pulse signal model, fitting to obtain model parameters, and constructing a system response matrix; modeling a nuclear detection physical process into a mathematical model; solving a constraint optimization problem by using a non-negative least square method; and demodulating and calculating all the pulse signals including the stacked pulses which are discarded by stacking, so as to obtain delta pulses containing energy information. According to the invention, the accumulation signal which is abandoned by a traditional accumulation abandoning algorithm is demodulated, so that the technical problem of increasing the pulse passing rate is solved, and meanwhile, heavy peaks and high-energy trailing in an energy spectrum are inhibited. Compared with an existing accumulation discarding method, the pulse passing rate effect is remarkably improved on the premise that the energy spectrum accuracy is guaranteed.

The embodiment of the invention relates to the technical field of nuclear detection and measurement, and discloses a double-label nuclide analysis method and device and a program product, and the method comprises the steps: measuring a standard quenching source, and obtaining an external standard source spectrum index of the standard quenching source; drawing a correction curve by taking the external standard source spectrum index as an independent variable; measuring the double-labeled sample under external gamma source high voltage, and obtaining and calculating an external standard source spectrum index of the double-labeled sample through external gamma source spectrum stripping; determining the counting efficiency of low-energy nuclide, the counting efficiency of high-energy nuclide, the spectrum index of the low-energy nuclide sample and the spectrum index value of the high-energy nuclide sample corresponding to the double-labeled sample under the current quenching level according to the external standard source spectrum index of the double-labeled sample and the correction curve; the method comprises the following steps: measuring a double-labeled sample under double-labeled high pressure to obtain a full-spectrum counting rate and a full-spectrum sample spectrum index of the double-labeled sample; the low-energy nuclide activity and the high-energy nuclide activity of the double-labeled sample are calculated based on the parameters, so that the operability is higher, the accuracy is higher, and the application range is wider.

The present invention provides a method for three-dimensional positioning of radioactive materials indoors, comprising: step S1, establishing a UWB positioning system; step S2, establishing a Cartesian coordinate system for the indoor environment; step S3, obtaining positioning information of a nuclear detector and the count rate at that location; step S4, collecting the count rates of two adjacent fixed-angle detectors A and B at the same horizontal location; step S5, collecting the count rates of two adjacent fixed-angle detectors A and C at the same vertical location; step S6, inverting to obtain α; step S7, inverting to obtain α1; step S9, measuring the distance between the detector and the radioactive material; and step S10, calculating the coordinates of the radioactive material. The present invention also provides a three-dimensional positioning system for radioactive materials indoors.

The application discloses an online proton imaging ion spectrometer diagnosis system, relates to the fields of plasma physics and nuclear detection, and comprises an online proton imaging module, an online Thomson ion spectrometer module and a shielding aiming module; the shielding aiming module comprises a shielding cavity and an aiming laser pen; the online proton imaging module comprises a metal filter, a first scintillator and two proton imaging acquisition assemblies; the proton imaging acquisition assembly comprises a first optical fiber panel attached to the first scintillator and a first CMOS sensor attached to the first optical fiber panel; the online Thomson ion spectrometer module comprises an ion beam deflection mechanism and an ion spectrum diagnosis acquisition assembly; the ion spectrum diagnosis acquisition assembly comprises a light-proof aluminum film, a second scintillator, a second optical fiber panel and a second CMOS sensor which are sequentially and superposedly arranged. The application reduces the size of the whole system, can simultaneously carry out online proton imaging and ion energy spectrum diagnosis, and can effectively prevent radiation damage to the CMOS chip.

The invention belongs to the technical field of crack detection, and provides a multifunctional seedless detection method based on linear cracks of an asphalt pavement, which comprises the steps of collecting a large number of asphalt pavement image samples based on multifunctional seedless detection, taking the normalized image samples as input based on a neural network model, and calculating the linear cracks of the asphalt pavement. Outputting a crack region category visual image, wherein the crack region category comprises a linear crack region, a non-linear crack region and a non-crack region; extracting a linear crack region and a crack-free region in the crack region category visual image to carry out coordinate mapping; according to the method, the quantitative correlation model of the scattering attenuation and the crack depth is established by determining the existence condition of the scattering attenuation, the accurate correction of the linear crack depth is finally realized, and the accuracy and the reliability of the detection of the linear crack depth of the asphalt pavement are greatly improved on the whole.

This invention relates to the fields of nuclear detection electronics and radiation signal processing technology, specifically to an intelligent analysis system and method for nuclear radiation data. The system includes: acquiring a discrete voltage sequence output by the detector; marking pulse signals as clean pulses and calculating the real-time decay constant; calculating the net signal amplitude using a digital twin state-space recursive model; determining the real-time count rate based on the net signal amplitude and calculating the dynamic time window width based on the real-time count rate; discretely accumulating the net signal amplitude based on the dynamic time window width to generate a single-particle physical energy value; determining the measured peak position based on the single-particle physical energy value and generating a gain adjustment coefficient by combining the measured peak position with the real-time decay constant; and outputting a gain control signal based on the gain adjustment coefficient. This invention ensures precise synchronization between the subsequent calculation model and the current physical state of the detector, thereby significantly improving the physical authenticity and accuracy of energy spectrum analysis under varying temperature conditions.

The application belongs to the technical field of equipment management, and discloses a nuclear detector fault diagnosis method, device, computer equipment and storage medium. The nuclear detector fault diagnosis method comprises the following steps: acquiring an output signal of the nuclear detector; inputting the output signal into a pre-trained deep belief network for fault identification to obtain a fault parameter corresponding to the output signal; and adopting a generalized likelihood ratio test classification model to perform fault classification on the fault parameter to obtain a fault category corresponding to the output signal, so that the fault of the nuclear detector can be quickly and accurately detected.

This invention relates to the field of nuclear detection technology, and more particularly to a method for improving light output based on different arrangements of conical structures. The method includes: constructing a periodic nanostructure array on a crystal surface to form a refractive index gradient interface to improve light extraction efficiency; the periodic nanostructure array is divided into tetragonal and hexagonal arrangements; establishing a physical model using the FDTD algorithm, while setting boundary conditions and light source types that conform to the physical conditions of perovskite luminescence; analyzing the influence of the two arrangements on transmittance using the scanning function of FDTD under a specific wavelength light source; iteratively optimizing the geometric parameters with a preset light transmittance using FDTD optical simulation combined with a particle swarm optimization algorithm; and evaluating the convergence of the particle swarm optimization. This invention solves the problem of low light extraction efficiency in existing technologies and has the advantages of strong structural inherentness, superior optical performance, and applicability to radiation detectors and other devices.

The application discloses a kind of co-doped Eu 3+ 、Sm 3+ Half of oxide-based red light scintillation crystal material and its preparation method and application, belong to artificial crystal growth technical field.Its chemical formula is (Sm x Eu y R 1‑x‑y )2O3, 0.01≤x≤0.08, 0.01≤y≤0.06, R is selected from any one of Lu, Sc, Y.R is Lu, the performance of crystal is more excellent, and it is more advantageous in the high-energy ray detection of extreme environment.R is Lu, and the crystal is transparent, and the appearance is good, has microsecond level decay time and high light yield, has excellent scintillation performance and extreme environment performance;It can be effectively combined with photoelectric detection equipment, can be used in extreme temperature, strong radiation nuclear radiation detection service environment, widen the application range of scintillation material, make up the application blank of traditional scintillation material in extreme service environment, meet the needs of nuclear detection and other scientific and technological development.

The utility model discloses a device for leading out a cathode nuclear signal of a proportional counter tube, and belongs to the technical field of nuclear detection. In order to solve the technical problem that the measurement precision is influenced by signal distortion easily caused by leading out nuclear signals from the anode of the existing proportional counter tube, the utility model mainly adopts a mode of leading out nuclear signals from the cathode of the proportional counter tube, and is provided with a first signal joint, a second signal joint, a third signal joint and a metal shielding shell in a matched manner. According to the utility model, complete output and electromagnetic interference suppression of nuclear signals can be realized, and signal quality and device stability are improved.

The application discloses an out-of-pile nuclear detection device, a system and a detection data processing method thereof, the out-of-pile nuclear detection device comprises a plurality of source range detector assemblies, a plurality of intermediate range detector assemblies and a plurality of power range detector assemblies, and the assemblies can be fixed at the boundary of the pressure vessel of the reactor to be detected; the source range detector assemblies, the intermediate range detector assemblies and the power range detector assemblies all comprise a multilayer detection structure; wherein the multilayer detection structure comprises a detector body, a moderator material structure and an aluminum shell arranged layer by layer from inside to outside. The out-of-pile nuclear detection device can improve the detection sensitivity of each type of detector assembly by additionally arranging the moderator material structure and the aluminum shell on the detector assembly, and the aluminum shell can prevent the deformation of the moderator material structure of the moderator material in a high radiation environment.

The invention discloses a preparation method of a small pulse broadening drift tube for ultrafast diagnosis and the pulse broadening drift tube thereof. The method comprises the following steps: 1) brazing a front shell and a rear shell, and carrying out indium filling, indium melting and indium turning operation on the front shell; 2) performing spot welding to obtain a first grid mesh assembly, a second grid mesh assembly and a third grid mesh assembly; 3) preparing a substrate, a conductive film layer and a sealing film layer, and assembling to obtain a cathode input window; (4) sealing the metal anode flange, the frit ring and the optical fiber panel at high temperature, and plating a metal layer on the small surface of the optical fiber panel to prepare an anode assembly; (5) the first grid mesh assembly and the second grid mesh assembly are assembled on the front shell to obtain the front shell provided with the front assembly; and 6) preparing a cathode input window and a cathode at the rear end, degassing at high temperature, electronically brushing and sealing indium at high vacuum degree to obtain the small pulse broadening drift tube which can meet the requirements of the technical fields of nuclear detection, high-energy physics and the like on ultrafast diagnosis equipment.

The present disclosure relates to a two-dimensional positron annihilation lifetime spectrum measurement method and system, which relates to the fields of nuclear spectroscopy and nuclear detection technology. This method detects the first stop time and the second stop time of the two annihilation gamma photons generated in the reverse direction when the positron annihilates, respectively. The first lifetime value and the second lifetime value are then calculated from the start time of the initial gamma photon generated by the decay of the radioactive source, respectively. The first lifetime value and the second lifetime value are then subjected to two-dimensional statistics to obtain a two-dimensional positron annihilation lifetime spectrum of the positron annihilation in the sample to be tested. This method performs statistics on the two annihilation gamma photons generated by an annihilation case, which can effectively eliminate background counts, thereby improving the peak-to-valley ratio of the lifetime spectrum, and can improve the utilization rate of the annihilation gamma photon information in the annihilation case, thereby improving the time resolution of the measurement.

The invention discloses a He position sensitive detector and an assembling method thereof, and relates to the technical field of nuclear detection. The detector comprises a tube shell filled with working gas, wherein insulating electrodes consisting of kovar alloy end sockets, insulating ceramics and copper tubes are arranged at two ends of the tube shell. And the two ends of the anode wire coaxially arranged in the tube shell are respectively connected with the inflating tube and the wire penetrating copper needle through an anode wire positioning piece and a spring. According to the invention, high-precision coaxial positioning of the anode wire is realized through small clearance fit between the anode wire positioning piece and the inner wall of the copper pipe; a bilateral spring structure and a unique assembly method are adopted, so that accurate control and reliable maintenance of the tension of the anode wire are ensured; and an inflation tube and a threading copper needle are multiplexed as a signal extraction electrode, so that the functions of inflation, signal extraction and mechanical support are efficiently integrated in a limited space. The problems that an existing detector anode wire is not accurate in positioning, tension maintaining is not reliable, and multifunctional integration is difficult in a compact space are effectively solved.

The invention relates to the technical field of nuclear detection electronics and radiation signal processing, in particular to a nuclear radiation data intelligent analysis system and method, and the method comprises the steps: obtaining a discrete voltage sequence outputted by a detector; marking the pulse signal as a clean pulse, and resolving a real-time attenuation constant; resolving a net signal amplitude through a digital twin state space recursive model; determining a real-time counting rate based on the net signal amplitude, and resolving a dynamic time window width based on the real-time counting rate; performing discrete accumulation on the net signal amplitude based on the dynamic time window width to generate a single-particle physical energy value; determining an actual measurement peak position based on the single-particle physical energy value, and generating a gain adjustment coefficient in combination with the actual measurement peak position and the real-time attenuation constant; outputting a gain control signal according to the gain adjustment coefficient; according to the method, accurate synchronization of a subsequent calculation model and the physical state of the current detector is ensured, so that the physical authenticity and accuracy of energy spectrum analysis in a variable-temperature environment are remarkably improved.

The invention relates to the technical field of power supply systems, in particular to an analog nucleation detection system and method, and the system comprises a data collection module, an equipment detection module, a simulation adaptation module, an analog nucleation detection module, a cyclic feedback module, and a detection evaluation module. Through cooperative operation of all the modules, the problems of insufficient proficiency, low simulation training efficiency and low operation safety in existing nucleation detection personnel training are effectively solved, the professional skills, team cooperation ability and adaptive ability of nucleation detection personnel are comprehensively improved, the high efficiency of training and the safety of practical operation are guaranteed, and the practical training efficiency is improved. And more qualified talents are cultivated for coring detection work.

The invention provides an out-of-pile nuclear detector mounting device, and relates to the technical field of nuclear detection, and the out-of-pile nuclear detector mounting device comprises a fixed frame, a fixed cylinder, a first telescopic cylinder and a second telescopic cylinder; one end of the fixed cylinder is fixedly arranged on the fixed frame, and the other end vertically extends upwards; the first telescopic cylinder is coaxially arranged in the fixed cylinder in a sleeved mode and can slide in the axial direction of the fixed cylinder. The number of the second telescopic cylinders is one or more, the multiple second telescopic cylinders are coaxially arranged in a sleeving mode according to the outer diameter decreasing sequence, the second telescopic cylinder on the outermost layer is coaxially arranged in the first telescopic cylinder in a sleeving mode, and the top end of the second telescopic cylinder on the innermost layer is used for being connected with a nuclear detector; the driving device is used for driving the first telescopic cylinder to stretch out and draw back relative to the fixed cylinder and driving all the second telescopic cylinders to stretch out and draw back synchronously through the first telescopic cylinder. According to the device, the multi-stage telescopic cylinder bodies which are coaxially nested are adopted, the large-range lifting function is achieved while the compact storage size is kept, and the detector can be efficiently installed at the designated position of the upper portion of a reactor cavity.

The invention discloses a modular data acquisition and transmission system, relates to the technical field of radiation measurement equipment, and can realize that one set of data acquisition and transmission device can be applied to different nuclear detectors by using different communication switching modules through modular design. And other modules except the communication switching module can be used for different types of nuclear detectors, so that the cost is greatly reduced, and the maintenance and replacement are more convenient. The problems that an existing data acquisition and transmission device is high in cost and inconvenient to maintain when being used in a plurality of nuclear detectors of different types can be solved. In the combined measurement process of multiple nuclear detectors, the cost of the data acquisition and transmission device can be obviously reduced, and the data of each detector can be more conveniently classified through the Internet of Things module.

The application discloses a real-time nuclear signal identification processing method and system, belongs to the technical field of signal processing, and converts continuous nuclear pulse analog signals conforming to double exponential characteristics into discrete nuclear pulse signals; the attenuation parameters required for corresponding trapezoidal shaping are calculated in real time according to the discrete nuclear pulse signals; and the discrete nuclear pulse signals are transformed into trapezoidal pulse signals according to the attenuation parameters calculated in real time. The application can significantly improve the energy resolution and counting accuracy of a nuclear detection system.

The application discloses a kind of gamma energy spectrum feature extraction method and system based on energy spectrum two-dimensional coding, belong to nuclear detection and energy spectrum signal processing technical field, this method includes: obtaining and pre-processing gamma energy spectrum data;One-dimensional energy spectrum sequence is mapped into two-dimensional energy spectrum matrix by two-dimensional coding;Local structure enhancement is carried out to two-dimensional energy spectrum matrix, multi-scale transformation, space feature compression and statistical feature embedding, and two-dimensional energy spectrum feature map is constructed;High-dimensional spectral feature expression is obtained by using feature extraction model to carry out multilevel processing to two-dimensional energy spectrum feature map;The high-dimensional spectral feature output is used for nuclide identification, element content inversion and other gamma energy spectrum analysis application.The application enhances the energy spectrum structure feature expression ability by two-dimensional coding mode, realizes the efficient, stable and fine use of energy spectrum information.

The invention discloses a nuclear detection signal de-stacking method based on a physical rule neural network. The method comprises the following steps: 1) training an adversarial neural network by using a training set; 2) the ADC acquisition module converts a to-be-processed nuclear signal into a digital signal and sends the digital signal to the FPGA circuit module; 3) the FPGA circuit module performs peak searching on the digital signal to obtain a stacking measurement value and transmits the stacking measurement value to the GPU module; and 4) the GPU module performs reasoning on an input accumulation measurement value by using the trained adversarial neural network to obtain an amplitude value of each nuclear signal. According to the method, physical rule constraints are added on the basis of a traditional neural network, so that the model can better process the accumulation problem caused by a radioactive source, and meanwhile, the interpretability of the model is better.

The invention discloses a real-time nuclear signal identification processing method and system, and belongs to the technical field of signal processing, and the method comprises the steps: converting a continuous nuclear pulse analog signal conforming to a double-index characteristic into a discrete nuclear pulse signal; performing real-time calculation according to the discrete nuclear pulse signals to obtain corresponding attenuation parameters required by trapezoid forming; and converting the discrete nuclear pulse signal into a trapezoidal pulse signal according to an attenuation parameter calculated in real time. According to the invention, the energy resolution and counting accuracy of the nuclear detection system can be significantly improved.

The application relates to the technical field of nuclear radiation environment detection, in particular to a nuclear detection unmanned aerial vehicle load module, which comprises a box body used for bearing internal components, a component support frame is arranged in the box body, a detection assembly used for detecting nuclear radiation is arranged on the component support frame, a control assembly used for processing detection signals and realizing signal transmission is arranged on the component support frame, a quick connection structure used for docking with a main machine of an unmanned aerial vehicle is arranged on the box body, the quick connection structure comprises a positioning assembly arranged on a connecting surface of the box body, a locking assembly used for realizing quick locking, and a quick connection electrical assembly used for realizing electrical connection, the quick connection structure is arranged, the positioning assembly guarantees the position accuracy when the box body is docked with the main machine of the unmanned aerial vehicle, the locking assembly ensures the stability of the connection, the quick connection electrical assembly realizes quick connection of power and signals, the efficiency of module installation and replacement is greatly improved, and the unmanned aerial vehicle can quickly switch task states.

The invention discloses a positron annihilation lifetime spectrometer system with three-dimensional position resolution capability, which belongs to the technical field of nuclear detection and comprises a positron annihilation lifetime measuring device and a high-precision X-Y plane moving device. The positron annihilation life measuring device is used for acquiring annihilation characteristics of positron in different depth intervals within a millimeter depth range from the surface of a material, and comprises a life starting module and a life ending module which are respectively connected with an information acquisition module, and the information acquisition module is connected to a control and processing module; the high-precision X-Y plane moving device is used for moving the detector part of the positron annihilation life measuring device so as to realize scanning test of an X-Y plane, and comprises three servo motors and three sliding rails respectively controlled by the servo motors. According to the invention, three-dimensional space characterization can be carried out on microstructure characteristics of different depth intervals in a millimeter-level depth range from different areas of the surface of the material to the surface.

The invention discloses a load-bearing nuclear detection cable which comprises a cable core, a wrapping layer wrapping the surface of the outer side of the cable core, a first shielding layer arranged on the outer side of the wrapping layer and a sheath arranged on the outer side of the shielding layer in a sleeving mode, and the cable core is formed by twisting a plurality of signal wire cores, a plurality of control wire cores and a central wire core. The central wire core further comprises an inner core layer formed by twisting a plurality of first steel wires and first aramid fibers which are arranged in a staggered mode and an outer sleeve layer wrapping the inner core layer, and the signal wire core and the control wire core are sequentially arranged around the central wire core arranged in the center and are respectively in abutting contact with the outer sleeve layer of the central wire core. A filling rope is arranged in a gap formed among the signal wire core, the control wire core and the wrapping layer; and the filling rope is formed by twisting a second steel wire and a plurality of second aramid fibers arranged on the outer side of the second steel wire. The cable has good bearing capacity, and the situation that the whole cable is too hard and not prone to bending or poor in bending performance, and consequently use is inconvenient can be avoided.

This invention discloses a temperature compensation correction algorithm for a nuclear detector, comprising the following steps: The temperature compensation algorithm mainly determines the left and right boundaries of the characteristic peak, the peak position, peak height, and half-width, locks the channel address corresponding to the drifted characteristic peak, and then uses the spectral data of the known peak region to form complete corrected spectral data using a Gaussian fitting function, thereby achieving temperature compensation. The temperature in this invention has a relatively small impact on the pulse count of the nuclear detector but a significant impact on the energy spectrum data, manifested as a shift in the spectral line data of the characteristic peak.

This invention discloses a β + This invention relates to a γ-γ coincidence positron annihilation lifetime-momentum correlation spectrometer, belonging to the field of nuclear detection technology. The spectrometer includes a positron annihilation lifetime detection module, a positron annihilation γ-photon energy detection module, a signal acquisition module, and a control and analysis module. The positron annihilation lifetime detection module is used to obtain the lifetime component of the AMOC spectrum; the positron annihilation γ-photon energy detection module is used to obtain the momentum component of the AMOC spectrum by detecting γ-photons generated by positron annihilation; the signal acquisition module is used to acquire the signals generated by the positron annihilation lifetime detection module and the positron annihilation γ-photon energy detection module; and the control and analysis module is used to control the signal acquisition module and obtain the AMOC spectrum based on the signals acquired by the signal acquisition module. This invention can effectively improve the coincidence count rate, has good coincidence time resolution and extremely low source composition, and helps to reduce the construction cost of the spectrometer.

This invention relates to the field of oil and gas pipeline inspection technology, and more particularly to a device and method for detecting and locating the radiation dose on the inner wall of an oil and gas pipeline. The device includes a support component, the oil and gas pipeline to be inspected, and a detection component for inspecting the pipeline, all mounted on the support component. A power component for controlling the movement of the detection component is also installed on the support component. The detection component is electrically connected to a control console. The power component includes a cable chain connecting the detection component, and the cable chain is controlled by a motor for winding and extending. By employing a cable chain system and controlling the movement of the cable chain by a motor, rapid and accurate positioning of the detection component is achieved, effectively improving inspection efficiency and data accuracy. Through initial screening and detailed inspection using a nuclear detector, the specific locations where the radiation dose on the inner wall of the pipeline exceeds a set value can be accurately pinpointed, thereby quickly identifying and locating the source of contamination.

The invention discloses a uranium-radium balance coefficient determination method based on geophysical logging, and relates to the technical field of sandstone type uranium ore core detection. Comprising the following steps: determining radium equivalent uranium content of each unit layer in a target drilled hole, and determining an industrial uranium mine hole; a geophysical prospecting parameter hole is constructed at the industrial uranium mine hole, periodic repeated measurement is carried out, a radium radon balance recovery curve is obtained, and a radium radon balance coefficient is determined; the radium equivalent uranium content of the target drill hole is corrected through the radium radon balance coefficient, and the real radium equivalent uranium content is obtained; and respectively accumulating the real radium equivalent uranium content and the stratum rock uranium content within the same depth range as the industrial uranium mine hole, and determining the uranium radium balance coefficient of the target drill hole according to the ratio of the two accumulated values. According to the uranium and radium balance coefficient obtained through the method, existing information of uranium, accumulated information of radium and dynamic balance information of a radium-radon system are fused, and the actual balance state of uranium and radium at the current position after geological historical evolution can be reflected more truly.

The application provides a nuclear detection device and an imaging device which can output light signals and have built-in gain, and mainly solves the technical problem that the existing imaging devices mostly use scintillator materials to convert radiation into light through the characteristics of the scintillator materials; however, the scintillator materials have the defects of low energy resolution, narrow linear range, and poor radiation resistance stability, thereby leading to poor imaging effect of the imaging device. The application comprises a bipolar transistor nuclear detector for converting radiation energy into electric energy and generating electric gain, and an LED light emitter for converting electric energy into light signals; the bipolar transistor nuclear detector comprises a collector, a base, an emitter, and a bottom electrode; the LED light emitter comprises an electron transport layer, an active light-emitting layer, a hole transport layer, a hole injection layer, and a top electrode which are connected in sequence; and the side of the electron transport layer, which is far away from the active light-emitting layer, is connected with the collector.