20 results about "Nuclear detection" patented technology

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 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 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 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 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.

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.

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 to effectively 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.