23 results about "Counting rate" patented technology

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 provides a signal source progressive search and positioning method and device based on an unmanned vehicle, relates to the field of unmanned vehicle autonomous navigation and signal source positioning, and gradually updates a counting rate data to accurately detect a source signal by filtering a collected counting rate through a sliding sampling window, updating a sampling window in real time through a FIFO principle to obtain an updated source signal strength value, preparing for calculating an optimal source search path; a global planner comprehensively evaluates a global path, a local planner plans an optimal path, and a target point is searched by the unmanned vehicle; after the target point is searched by the unmanned vehicle, a signal source detection limit value is set, a counting rate filtered after rotation is cyclically obtained, and then the signal source is positioned; the application gradually and in real time avoids obstacles and dynamically adjusts a search path, a path planning and path optimization closed-loop control process is formed through a termination judgment rule of a detection signal source limit value, and the autonomy and efficiency of the unmanned vehicle source positioning are improved.

A method of measuring input count rate λ of radiation impinging on a radiation detector. A detector signal is received as a digital or analogue function of an independent signal parameter (such as time). The detector signal comprises or is derived from a series of radiation pulses from the detector. A plurality of signal thresholds θ is defined. For each θ a set of durations d of the independent signal parameter is calculated relating to a comparison between the signal threshold θ and the detector signal. For each signal threshold θ a frequency distribution of the durations d is calculated. A frequency surface F(θ, d) is then calculated as a function of at least signal threshold θ and duration d. The input count rate λ is determined by calculating a count rate estimator φ incorporating a characteristic feature of F(θ,d) that is sensitive to input count rate λ.

The present disclosure provides a backscatter detector, including: a plurality of detector modules arranged at different positions, where ray signal channels are independent of each other, where detection region areas of at least two first detection modules among the plurality of detector modules are different from each other, and the detection region area of each of the at least two first detection modules is adapted to a respective target first count rate. The present disclosure further provides a backscatter detection apparatus.

The present application belongs to the technical field of digital signal processing, and specifically provides a nuclear pulse amplitude extraction method based on parameter identification and a nuclear pulse analysis system, to solve the problem of the decrease in the accuracy of the energy spectrum diagram caused by the baseline drift and pulse pile-up rejection of the nuclear pulse signal, so as to improve the energy resolution and count rate of the nuclear pulse energy spectrum diagram. The present application can realize accurate capture and processing of the nuclear pulse signal, first uses a filtering method to process the original sampling sequence signal, reduces the influence of the baseline drift, then uses a parameter identification model to identify parameters and extract amplitudes of the pile-up pulses processed by the joint filtering method, and generates a high-precision spectrum diagram, so as to improve the energy resolution and count rate of the system, and provide strong technical support for the fields of nuclear physics research, nuclear energy application, and nuclear radiation detection.

This invention discloses a dynamic control method for adaptive bias voltage in the energy region of a CZT photon counting detector, belonging to the field of radiation detection and photon counting control technology. The method acquires energy events of incident photons within a fast sliding time window and forms an energy spectrum histogram, extracting energy region composition information and flux status information for low, medium, and high energy regions. Within a slow sliding time window, it acquires count rate change information, energy peak drift information, pulse tail change information, leakage current status information, temperature status information, and current operating bias voltage information. Based on the energy region composition information, flux status information, flux change trend, and current operating bias voltage information, it matches them with a preset energy region bias voltage mapping relationship to generate candidate operating bias voltages. A polarization risk index is constructed based on count rate change, energy peak drift, pulse tail change, leakage current status, and temperature status, and a bias voltage compensation amount is generated based on the level and trend of the polarization risk index.

The utility model belongs to radiation monitoring technical field discloses an online radiation monitoring device for carrying out online monitoring to gamma radionuclide activity concentration in the pipeline to be measured, including support frame, detection component and lead shielding component, support frame includes support frame body and mounting panel, support frame body includes two support plates that are arranged in parallel along the length direction of the pipeline to be measured and is spaced, and two connecting plates that are arranged in parallel and are spaced between the two support plates, the support groove is set up on two support plates, the pipeline to be measured can be supported in the support groove, the both ends of mounting panel are connected with two connecting plates respectively, and detection component is detachably connected on mounting panel, lead shielding component is detachably connected with support frame, lead shielding component is formed around the circumference of the pipeline to be measured and is provided with shielding cavity, and the pipeline to be measured can penetrate the shielding cavity. The online radiation monitoring device has strong anti-interference ability, low background counting rate and high detection efficiency for radiation.

The present application relates to the field of particle physics experiment data acquisition and processing, and specifically discloses an online AI triggering and data compression method and device for particle detector readout electronics, wherein the method realizes real-time feature extraction on the output pulse signal of the detector, uses a pre-trained fully connected neural network model to realize high-precision triggering decision, adopts a compression strategy combining adaptive quantization and entropy coding to compress effective event data, and simultaneously introduces a quality feedback mechanism based on peak signal-to-noise ratio to form a closed-loop control. The present application realizes intelligent collaborative processing of triggering decision and data compression, significantly improves the event selection efficiency and data compression quality under the premise of ensuring data physical integrity, and provides an efficient real-time data processing solution for high-count-rate particle physics experiments.

The application discloses a system for rapidly identifying artificial radiation, and relates to the technical field of nuclear radiation protection. The system comprises an organic scintillator, a photomultiplier, a threshold comparison circuit and a processing module. The organic scintillator is used for absorbing gamma rays of a current environment and emitting photons when excited atoms and molecules are de-excited. The photomultiplier is used for converting the emitted photons into electric pulse signals. The threshold comparison circuit is used for comparing the amplified electric pulse signals with four voltage thresholds respectively through four comparators to obtain four count rates. The processing module is used for obtaining count rates between different voltage thresholds according to the four count rates, and obtaining corresponding weights according to the count rates between the different voltage thresholds. The absolute values of the differences between the multiple weights and a pulse radiation distribution characteristic factor in a natural background radiation environment are summed to obtain a summation result. Whether artificial radiation exists is determined according to the summation result. Through the multi-threshold pulse counting and weight distribution analysis method, whether an artificial radiation source exists can be rapidly judged within 100 ms.

This technology provides a way to measure the moisture content and water content of fuel debris storage containers. [Solution] The measurement system comprises a neutron generator that irradiates the object to be measured with neutrons, a neutron detector that detects neutrons in different energy bands, and a measuring device that generates a neutron spectrum based on the neutron count rate detected by the neutron detector and measures the amount of water and / or hydrogen in the object to be measured based on the spectral information of the medium velocity group and above in the neutron spectrum.

The application discloses a neutron gamma detector with high dynamic range and time resolution, comprising: a plurality of layers of detection units, a plurality of neutron moderators and a detector shell; each detection unit is arranged along the axis of the detector shell, and a neutron moderator is arranged between each detection unit; the detection unit comprises a neutron / gamma sensitive scintillator array, a photomultiplier tube array and a preamplifier array, and each layer of neutron / gamma sensitive scintillator array is matched with one layer of photomultiplier tube array and one layer of preamplifier array. The detector utilizes the multiple layers of neutron moderators to form the gradient of the neutron and gamma ray detection efficiency of each layer of scintillator, the neutron / gamma sensitive scintillator array matched with the photomultiplier tube array and the preamplifier array can measure and obtain a pulse count matrix, and then the neutron and gamma count rate at each layer of detector can be extracted. Meanwhile, the time resolution and dynamic range are improved based on the structural design of the detector.

The application discloses a kind of cognitive radio spectrum sensing device and method based on quantum compressed sensing, belong to cognitive radio technical field.Aiming at the problems in prior art, by designing a kind of cognitive radio spectrum sensing device based on quantum compressed sensing, the device includes broadband antenna module, electro-optic modulation microwave photon conversion module, data acquisition module and cognitive radio signal detection algorithm module, each module is sequentially connected, and the whole process from signal reception to spectrum analysis is completed jointly;The present application utilizes quantum compressed sensing to realize sub-Nyquist sampling and high compression ratio broadband multi-frequency microwave signal spectrum measurement, while achieving a detection probability approaching 100% when the photon counting rate is increased to 2 Mcps and the integration time is 40 ms, providing a new strategy for cognitive radio spectrum sensing, decision-making and switching.

This invention relates to the field of intelligent bearing monitoring technology, and discloses a method, device, equipment, and storage medium for detecting bearing wear status. The method provided by this invention separates and extracts long-term trend components and short-term fluctuation components over a time scale, quantifying the remaining lubricant thickness and interface stress fluctuations respectively, thus decoupling wear accumulation from transient friction behavior. Further statistical analysis of short-term variance and pulse count rate reflects the uniformity of stress distribution and the frequency of direct metal-to-metal contact. Normalized variance is used to eliminate the influence of operating conditions such as load and speed on luminescence intensity, avoiding misjudgments caused by changes in operating conditions. Finally, by combining the above parameters and using a wear stage discrimination model, the wear stage discrimination result of the target bearing at the current moment can be accurately identified. This not only achieves non-invasive online monitoring of bearing wear status in sealed, confined spaces, but also accurately identifies the bearing wear status using changes in light intensity in the original triboluminescence signal of the target bearing.

This invention provides a method and system for measuring the activity of low- and intermediate-level radioactive waste bins using gamma scanning based on neural networks, comprising: Step S1: The waste bin is vertically divided into several segments; Step S2: Radioactive point sources within each segment are assumed to be ring-shaped line sources, and all ring sources within the same segment are equivalent to one equivalent ring source relative to the detector; Step S3: A segment is scanned at the same height and three different eccentricity positions using a gamma spectrometer to obtain the corresponding count rates at the three detection positions; Step S4: The equivalent ring source radius and its detection efficiency are calculated using the count rates at the three detection positions combined with a neural network algorithm; Step S5: The nucleon activity of the current segment is calculated based on the equivalent ring source radius and its corresponding detection efficiency; Steps S1 to S5 are repeated to obtain the nucleon activity of each segment; Step S6: The total activity of the waste bin is obtained by summing the nucleon activities of each segment.

A method of calibrating a pixelated radiation detector containing a plurality of pixel detectors electrically connected to a plurality of respective read-out channels of detector read-out circuitry includes determining a sensor material deadtime, τsensor, for each of the plurality of pixel detectors, and adjusting the respective read-out channel deadtime, τASIC, based on the determined sensor material deadtime, τsensor, of the respective one of the plurality of pixel detectors, such that a total deadtime, τtotal of each pixel detector including a sum of the respective sensor material deadtime, τsensor, and the respective read-out channel deadtime, τASIC, varies by less than ±5% from each other.

The application provides a kind of nuclear radiation field fast inversion method and system, it is related to nuclear radiation field inversion technical field, and the three-dimensional space model of target nuclear radiation field is constructed and the energy spectrum data of multiple observation positions are obtained in the present application, standard count rate data set is generated after pre-processing;Then by the discrete processing of radiation field, the initial radiation intensity is obtained based on the data between each potential point source and observation position;Further, for any target point, the relative contribution weight of each potential point source and the radiation attenuation factor are aggregated, the field intensity response factor of target point under multiple energy channels is calculated and the field intensity response vector is formed;Finally, the energy fluence mapping model with field intensity response vector as input and energy fluence as output is constructed and trained, the fast and high-precision inversion of energy fluence at any position of nuclear radiation field is realized, and the efficiency and accuracy of multi-energy channel nuclear radiation field inversion in complex medium environment are effectively improved.

The application discloses a photon counting detector correction method and device. The method comprises the following steps: determining the count rate of each energy interval of photon counting data according to the photon counting data output by a photon counting detector; determining the corresponding theoretical count rate according to the pulse pile-up model of the photon counting detector and the count rate sum of each energy interval; the pulse pile-up model represents a first corresponding relationship between the actual count rate and the theoretical count rate; determining the first pile-up compensation amount of each energy interval according to the count rate of each energy interval and the theoretical count rate; and correcting the count rate of the corresponding energy interval by using the first pile-up compensation amount of each energy interval. The application calculates the pile-up compensation amount based on the pulse pile-up model representing the first corresponding relationship between the actual count rate and the theoretical count rate, and corrects the count rate, so that the actual operation is simple, the calculation amount is small, the correction is more accurate, and the correction effect can meet the clinical use requirements.

A method for adaptive secondary ion mass spectroscopy, the method may include (a) adaptively setting a detection parameter that impacts an instantaneous count rate of a detector; (b) scanning an evaluated sample with a focused primary ion beam; (c) sensing, by the detector, secondary ions ejected due to the scanning, to provide detection signals; and (d) analyzing a composition of the evaluated sample based on (i) the detection signals, and (ii) a mapping between values of the detection parameter and the instantaneous count rate of the detector.

The present application belongs to the single photon imaging detection technical field, especially relates to a kind of photon detection system based on discrete wedge strip anode, including the vacuum seal tube formed by the window coated with photoelectric cathode, microchannel plate stack and germanium film substrate, discrete wedge strip anode placed outside the vacuum seal tube and signal processor.The present application divides the wedge or strip connected together by existing four-electrode wedge strip anode or four-wedge anode, forms independent wedge and strip, then each wedge and strip is connected to independent preamplifier circuit, and the coordinates of incident photon are obtained by the decoding algorithm of four-electrode wedge strip anode or four-wedge anode.Because wedge and strip are independent, multiple incident photons synchronously arrived can be detected in the direction perpendicular to wedge or strip, and the count rate of detector is also improved.

The application discloses a kind of annular coding gamma imaging method and system.The method is:1) a circular code board is placed between a gamma detector and several radioactive sources;The circular code board is made of multiple concentric circles, and the coding mode of each concentric circle on the circular code board is set according to the principle of coding mode unrelated;2) rotate the circular code board during imaging, modulate the gamma ray flux of the gamma ray emitted by the radioactive source to reach the gamma detector;The gamma detector converts the gamma ray received during the rotation of the circular code board into count rate and sends it to the data processing unit;After the circular code board rotates a cycle, the data processing unit obtains a projection matrix D with the change of rotation angle;3) the data processing unit decodes and reconstructs to obtain the position distribution image O of the radioactive source according to the projection matrix D.The imaging flexibility of the application is greatly increased, and the cost and failure rate are also greatly reduced.