163 results about "Counting rate" patented technology

The invention discloses a high-speed multi-photon detection system and method. The system comprises a detector and a signal processing circuit, wherein the detector is composed of a window plated with a photoelectric cathode, a micro-channel plate stack and an anode; a plurality of incident photons are converted into a plurality of photoelectrons by the photoelectric cathode, and the photoelectrons are converted into electron cloud by the micro-channel plate stack; the incident electron cloud is divided into multiple paths by three layers of staggered metal strip electrodes of the anode, and charge collection is carried out to obtain charge short pulses of each layer of electrode; the signal processing circuit converts the charge short pulses transmitted by the three layers of electrodes into digital pulse signals, obtains the centroid coordinates of the electron cloud from the digital pulse signals as the abscissa value, the ordinate value and the verification value of the incident photon position, combines the abscissa value, the ordinate value and the verification value based on the screening condition to obtain the target two-dimensional coordinates, and finally obtains the target two-dimensional coordinates. And transmitting to a terminal for imaging display. According to the invention, a plurality of synchronous photons can be detected, the overall counting rate of the detector is greatly improved, and the detection efficiency is improved.

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 invention relates to the field of crystal detection, and discloses a multifunctional comprehensive scintillation crystal and semiconductor material energy spectrum test system, which comprises a crystal adaptation module for judging the type and size of a placed crystal through an optical identification and parameter matching mechanism, and a signal acquisition module for amplifying, filtering and digitally processing an acquired signal, the signal correction module is used for correcting waveform distortion and baseline drift through a dynamic gain adjustment algorithm of a low-noise pre-amplifier and a multi-channel pulse analyzer; the data analysis module is used for generating an energy spectrum curve according to input signals and calculating energy resolution, counting rate, light attenuation time or carrier mobility, and the environment calibration module is used for dynamically evaluating shading degree, environment light, temperature and electromagnetic interference through an optical sensor and a temperature and humidity detector in the camera obscura and outputting updated calibration parameters. The method has the advantages of improving the detection efficiency, precision and consistency.

The invention relates to the technical field of single-photon detection, in particular to a single-photon detector performance parameter measurement method, device and equipment and a storage medium, and the method comprises the steps: building a statistical histogram of time domain interval data, and building the statistical distribution characteristics of the photon counting rate and dark counting of a single-photon detector; the probability of no photon detection event in the duration of the optical pulse and the ideal probability of no dark pulse in a preset time window are defined based on the statistical distribution characteristics, and then the probability of generating a single photon signal by the periodic optical pulse is calculated based on the obtained parameters; and finally, determining a periodic statistical peak count value based on the statistical histogram and the probability of generating the single photon signal by the periodic light pulse, and calculating an average detection photon number and a dark count rate so as to obtain the dead zone time, so that information such as the average detection photon number, the dark count rate and the dead zone time of the single photon detector is simultaneously represented through one-time data acquisition, and the detection accuracy of the single photon detector is improved. The problems that in a traditional method, the data storage amount is large, and cost is high are solved.

The invention discloses a two-photon N00N quantum state intelligent regulation and control device and method, and the device comprises an intelligent regulation and control module, and an entangled photon pair generation module, an HOM interferometer and a data collection module which are connected in sequence, and the entangled photon pair generation module transmits polarized orthogonal entangled photon pairs to two light paths in the HOM interferometer respectively; the data acquisition module is used for detecting and counting photons output by the two light paths respectively; the intelligent regulation and control module controls the first electric control time delay line on one light path and the electric control polarization controller on the corresponding light path so as to regulate the light path difference of the two light paths and the polarization state of photons output by the corresponding light path; every time control is completed, a second electric control time delay line on the other light path is controlled to carry out time delay scanning according to a set rule, and a coincidence counting rate and HOM visibility are obtained; and according to the coincidence counting rate and the HOM visibility, determining whether the two-photon N00N quantum state generated under the control is good or bad. According to the invention, intelligent regulation and control of the two-photon N00N quantum state quality can be realized.

A method of determining downhole formation oil saturation and three-phase holdup is described. The method includes lowering a pulsed-neutron logging tool downhole with a near detector and a far detector. The method further includes measuring a carbon to oxygen ratio from the near detector, measuring a carbon to oxygen ratio from the far detector, measuring a ratio of inelastic count rates, and plotting the measured ratios in a prismatic grid. The method further includes visualizing the fluid volumetrics around the pulsed-neutron logging tool.

The invention discloses a muon detector with variable scintillator spacing, which comprises a supporting base, and a bottom plate is arranged at the upper end part of the supporting base; the lower-layer detection part is fixedly arranged at the end part of the bottom plate, a multi-stage mechanical telescopic mechanism is arranged on the bottom plate, and an upper-layer detection part is arranged at the end part of the multi-stage mechanical telescopic mechanism; the main control data acquisition system is electrically connected with the multi-stage mechanical telescopic mechanism, the upper-layer detection part and the lower-layer detection part, and is used for setting and acquiring a distance value between the upper-layer detection part and the lower-layer detection part; and calculating according to the collected real-time spacing value, and performing corresponding data correction and image reconstruction according to the effective detection range and the optimal detection area under the current configuration. According to the method, the spatial resolution and the counting rate can be dynamically adjusted, so that the performance limitation caused by a fixed spacing design is broken through, and the comprehensive efficiency in a complex detection task is remarkably improved.

The invention provides a flow cytometer light path calibration method, which belongs to the technical field of flow cytometers, and comprises the following steps: firstly, collecting light path detection original data of standard fluorescent microspheres, including laser spot position coordinates, detector output voltage value, dark counting rate and signal counting rate; then establishing a detection channel conversion cost matrix, and calculating an optimal light path detection sequence by using a traveling salesman problem optimization algorithm; adjusting the positions of a laser, an optical filter and a detector according to the optimal sequence, and obtaining optical path calibration data; the collected parameters are substituted into an optical path parameter optimization equation set to be solved, and an optical path collimation coefficient, a detector response coefficient, a signal crosstalk coefficient and an optimal gain value are obtained; and finally, respectively adjusting the position of the laser, the working voltage of the detector, the position of the optical filter and the voltage of the photomultiplier according to the coefficients to finish the accurate calibration of the optical path. The problems that an existing method depending on artificial experience is low in efficiency and overall optimization of a system level is difficult to achieve are solved.

A nanoscale temperature detector comprising a diamond sensing probe (1) having a lateral dimension of at least 200 nanometers and having a sensing tip (2) with a radius of curvature (R) of less than 100 nanometers, less than 10 nanometers or less than 1 nanometer and a plurality of color centers (5) showing temperature sensitive features in the emission count rate. The diamond sensing probe (1) has a lateral dimension of at least 200 nanometers and is connected to a detector system (13) by a mounting structure (6). A thermal isolation barrier (3) thermally separates the sensing probe (1) from the detector system (13).

The invention discloses a medical image coincidence event processing method, system and device, equipment and a medium. The coincidence event processing method for the medical image comprises the steps that an original event is obtained, and the original event is an event composed of single photons and obtained by collecting photons generated by decay of a radioactive tracer through a detector; based on the energy information and the time information of the original events, the original events are discriminated, effective events are obtained, the effective events comprise true coincidence events and random coincidence events, and the true coincidence events are used for medical image reconstruction; determining a time window for the detector to collect photons, and dynamically adjusting the window width of the time window based on the change trend of the event counting rate; the valid events are processed based on the time window to reduce random coincidence events in the valid events.

The application discloses a kind of arbitrary waveform nuclear pulse conversion methods, for the trapezoidal shaping of arbitrary waveform nuclear pulse signal.First, the arbitrary waveform nuclear pulse signal is regarded as the impulse response of rational fraction transfer function system.Second, rational fraction transfer function is decomposed into multiple first-order inertia link and the form of sum, then, multiple first-order inertia link and the form of sum is carried out Laplace inverse transformation into time domain expression, and then its time domain expression is discretized and transformed, then the parameter of discretized expression is obtained using particle swarm algorithm, finally, the transfer function of trapezoidal shaping and shaping recurrence formula are obtained, the trapezoidal shaping of arbitrary waveform nuclear pulse signal is realized to a certain extent, the symmetry of trapezoidal pulse is improved, the accurate acquisition of pulse amplitude is facilitated, the energy resolution of system is improved and the counting rate is improved, which has great significance for improving the precision of radioactivity measurement.

The invention provides an online diagnosis and repair method for a uranium mine gamma ray monitoring device, and the method comprises the steps: determining the respective counting rate correction values of a plurality of detectors based on the current working temperature of the uranium mine gamma ray monitoring device, a preset temperature compensation model, and the counting rate detection values of the plurality of detectors; based on the respective counting rate correction values of the plurality of detectors, the detection efficiency of each detector is determined, and the detection efficiency comprises static detection efficiency and dynamic detection efficiency; and if the detection efficiency of any first detector in the plurality of detectors is deviated from the detection efficiency of a specified second detector in the plurality of detectors, circuit parameters of the first detector are adjusted based on the deviation, so that the detection efficiency of the first detector after the circuit parameters are adjusted is consistent with the detection efficiency of the second detector. According to the technical scheme, the measurement precision and the detection efficiency of the uranium ore gamma ray monitoring device in continuous operation are improved, and the uranium ore sorting energy efficiency is improved.

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 invention discloses an anti-interference measurement system of an out-of-pile pulse type detector, which comprises an FPGA (Field Programmable Gate Array), and the FPGA is characterized in that in a normal working state, a test module controls a channel selection module to be switched to a measurement channel; the signal processing module performs validity detection on the signal waveform, generates a fault information data packet and sends the fault information data packet to the fault management module if the signal waveform fails, performs three-path parallel processing on the signal if the signal waveform is valid to obtain the signal waveform, timestamp information and a signal type, and obtains counting rate information of the signal according to the signal type and the timestamp information; an interference signal data packet and a nuclear signal data packet are generated and sent to the communication module, the signal processing module detects the validity of signal waveforms and timestamps in real time, and when the signal waveforms and the timestamps fail, a fault information data packet is generated and sent to the fault management module; the parameter module carries out self-recovery processing, and the test module and the signal processing module verify the self-recovery effect. The system improves the anti-interference capability, accuracy and reliability of measurement.

The invention relates to a method for radiation detection chip angle response compensation. The method comprises the following steps: step 1, testing the counting rate of deposition of each channel of array SiPM when gamma rays have different incident angles; 2, according to a standard dose rate value and the counting rate of each channel of the array type SiPM at different incident angles obtained in the step 1, constructing a linear equation set; 3, solving the system of linear equations in the step 2 to obtain an angle response correction matrix; and 4, correcting the angle response of the chip according to the angle response correction matrix in the step 3. According to the invention, the angle response compensation of the thin-layer scintillator radiation detection chip on the directional dose rate of different incident angles is realized, and the problem of measurement deviation of the radiation detection chip caused by the change of the incident angle of the radiation source is solved.

The invention provides a runner chamber wall thickness and void synchronous detection method, and relates to the technical field of hydro-power engineering nondestructive testing, S1, modular calibration: preparing a combined simulation block of a metal standard plate and an organic material plate, establishing a concrete water content inversion model and a void depth model segmented according to the thickness of a steel lining, and outputting calibration parameters; s2, field data acquisition: arranging measuring lines along a vertical welding seam and a longitudinal rib plate of the runner chamber, acquiring ultrasonic echo time and a thermal neutron counting rate, correcting the wall thickness in combination with the temperature of a steel lining, performing secondary verification on an abnormal measuring point, and outputting an original data set S = {}; and S3, machine learning signal processing: performing wavelet packet decomposition to extract energy ratio characteristics, and calculating thermal neutron counting rate fluctuation characteristics. Precise collaborative detection of the wall thickness and the void is realized through a link-by-link process of modular calibration, field data acquisition, machine learning signal processing, segmented collaborative modeling and Internet of Things data management.

To provide a radioactive material monitoring device capable of accurately detecting the concentration of radioactive materials in a liquid to be detected. [Solution] A radioactive material monitoring device comprising a flow channel through which a liquid to be detected flows, a counter unit that counts signals based on radiation generated from within the flow channel, and an analysis unit that calculates the concentration of radioactive material in the liquid to be detected based on the radiation count rate obtained from the counter unit, wherein the analysis unit includes a background correction unit that calculates a background value from the count rate based on the volume of the liquid to be detected in the flow channel and the count rate obtained from the counter unit, and a concentration calculation unit that calculates the concentration of radioactive material in the liquid to be detected based on the background value calculated by the background correction unit and the count rate obtained from the counter unit.

The invention relates to a method and a system for determining working parameters of a nuclear reactor fission chamber detector. The method comprises the following steps: acquiring output current relation information of a detected detector; determining a working voltage test range of the detected detector according to the output current relation information; and sequentially setting the working gas pressure of the detected detector as a plurality of preset gas pressure values, and controlling the detected detector to work based on the working voltage test range after setting the working gas pressure each time. Obtaining and determining counting rate data corresponding to each predetermined air pressure value according to the output current when the neutron beam is injected into the detected detector; and determining ideal working parameters of the detected detector according to the counting rate data. The method can help a worker determine ideal working parameters of the fission chamber detector, and improves the working stability and reliability of the detector.

The invention relates to the field of laser welding quality detection, in particular to a multi-modal fusion identification method and system for laser welding defects of copper-aluminum heterogeneous materials. Molten pool images, temperature fields and acoustic emission signals are synchronously collected through a visible light high-speed camera, a thermal infrared imager and an acoustic emission sensor which are coaxially integrated; the width oscillation amplitude, the trailing edge solidification angle, the interface temperature gradient, the acoustic emission characteristic frequency band energy ratio and the burst signal counting rate of the molten pool are extracted; constructing a fusion vector input adaptive weighted deep neural network model, and identifying four types of defects of pores, cracks, incomplete fusion and interface brittle compound layer standard exceeding in real time; and the identification result triggers laser power modulation or protective gas proportion adjustment. The problems that in the prior art, multi-physical field perception is insufficient, the feature adaptability of heterogeneous materials is poor, and real-time control is lack are solved, the defect detection rate reaches 98.2%, and control response delay lt is achieved; and 50ms.

According to the method for regulating and controlling the current density of the superconducting micron wire, the hole shape with a certain size is designed in the linear area of the winding superconducting micron wire, so that the current density of the superconducting micron wire is redistributed, the current density at the corner of the winding superconducting micron wire is reduced, and the current crowding effect of the superconducting micron wire is effectively relieved. According to the current density regulation and control method, the superconducting micron wire is allowed to work under higher overall bias current without causing too high dark counting, so that the photon counting rate upper limit of the detector is improved. According to the invention, the detection efficiency of the superconducting micron wire can be improved, dark counting and time jitter are reduced, the structure is simple, the current density is flexible to regulate and control, meanwhile, the device is easy to expand to the development of a large photosensitive area detector, and the device has a wide application prospect in the fields of quantum communication, bioluminescence imaging, dark substance detection and the like.

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 invention provides an improved camera for electron diffraction pattern analysis, and particularly relates to a device for detecting a Kikuchi diffraction pattern. The apparatus comprises: an electron column adapted to provide, in use, an electron beam directed toward the sample, the electron beam having an energy in the range of 2 keV to 50 keV, and; an imaging detector for receiving and counting electrons from the sample due to the interaction of the electron beam with the sample, the detector comprising an array of pixels and having a count rate capability of at least 2000 electrons per second for each pixel wherein: the imaging detector is adapted to provide electron energy filtering of the received electrons, the particle detector has an active region and a diffraction pattern for counting received electrons representing said diffraction pattern, and the particle detector has an inert layer on a surface on which electrons enter towards the active region of the detector, where the inert layer disperses the detection energy of 20 keV incident electrons having an energy dispersion of a full width at half maximum of less than 3.2 keV. The invention also provides a method for detecting the Kikuchi diffraction pattern.

The application provides a parameterized real-time measurement method for field neutron energy spectrum and dose, which comprises the following steps: using a three-section function model to represent the field neutron energy spectrum; constructing simulated field neutron energy spectrums of multiple moderation levels, and using a detector to measure and calculate a thermal-fast ratio; simulating and calculating the simulated field neutron energy spectrum of a test point by using a Monte Carlo model to obtain model parameters; establishing a corresponding relationship between the model parameters and the thermal-fast ratio; measuring the fast neutron pulse count rate and the thermal neutron pulse count rate by using the detector in the field, determining the value of the model parameters by looking up a table or interpolation, and the like according to the corresponding relationship between the model parameters and the thermal-fast ratio; calculating the field neutron energy spectrum according to the model parameters, and calculating the field neutron dose by using the field neutron energy spectrum and a neutron fluence-dose conversion coefficient.

The invention discloses a monitoring system and method for the cross state of in-loop reaction beam targets, and relates to the technical field of particle physical experiments. The system comprises a signal source module which is used for taking delta electrons generated by collision of a medium-high energy ion beam and a gas inner target as a signal source for monitoring a beam-target crossing state; the detection equipment module is used for adopting a customized ultrahigh vacuum compatible silicon detector as delta electron detection equipment; and the monitoring module is used for tracking the delta electronic normalization counting rate and monitoring the cross state of the reaction beam target in the ring in real time. The technical scheme has universality, real-time performance, safety and accuracy, and adapts to various beam target combinations.

The invention discloses a wide-range neutron measurement method, and belongs to the technical field of neutron detection and measurement, and the method comprises the steps: selecting a wide bandgap semiconductor material, an electrode metal material, a neutron conversion material and a neutron conversion material coating method, obtaining a wide bandgap semiconductor radiation detector coated with the neutron conversion material, and taking the wide bandgap semiconductor radiation detector as a neutron detector; a neutron detector is connected with a pre-amplifier, the pre-amplifier is connected with a rear-end digital sampling circuit, the rear-end digital sampling circuit processes pulse waveforms output by the pre-amplifier, and digital pulse signals are output; processing the digital pulse signal by using a pulse counting method and a Campbell method in upper computer software to obtain a pulse counting rate value and a Campbell value, and calculating neutron fluence rates obtained by the two methods; and obtaining the neutron fluence rate as an output result by adopting different methods according to the size of the neutron fluence rate. According to the invention, a neutron fluence rate measurement system with a small size, high temperature resistance, radiation resistance and a wide range can be obtained, and real-time accurate measurement under the condition of large-range change of the neutron fluence rate is realized.

The invention discloses a neutron gamma detector with a high dynamic range and time resolution. The neutron gamma detector comprises a plurality of layers of detection units, a plurality of neutron moderation bodies and a detector shell, each detection unit is arranged along the axis of the detector shell, a neutron moderator is arranged between every two detection units, each detection unit comprises a neutron / gamma sensitive scintillator array, a photomultiplier array and a pre-amplifier array, and each layer of neutron / gamma sensitive scintillator array is matched with one layer of photomultiplier array and one layer of pre-amplifier array. According to the detector, multiple layers of neutron slowing-down bodies are utilized to form gradients of neutron and gamma ray detection efficiency of each layer of scintillators, and a pulse counting matrix can be measured and obtained after the neutron / gamma sensitive scintillator array is matched with the photomultiplier tube array and the pre-amplifier array. And then neutron and gamma counting rates at each layer of detector are extracted. Meanwhile, based on the structural design of the detector, the time resolution and the dynamic range are improved.

The application relates to a stable spectrum method for underwater gamma spectrum measurement, belonging to the technical field of gamma spectrum measurement. The stable spectrum method is characterized in that the stable spectrum step is as follows: a channel address of a compound peak is set, a full spectrum is saved as a first spectrum at an interval of 0.5min to 2min; whether there is a peak is determined at 200 channels on the left and right of the preset compound peak channel address; when there is a peak, whether the preset compound peak count rate range is met is determined; the channel address of a La-138 compound peak peak position is compared with the preset compound peak channel address, and a channel address difference is calculated; the working voltage is adjusted by using a channel address and working voltage relationship function, and a spectrum in a second time period is recorded; the working voltage is adjusted by repeatedly using the channel address and working voltage relationship function until the channel address of the compound peak peak position coincides with the preset compound peak channel address; and thus, the automatic stable spectrum of the start-up measurement is completed. The application can adapt to the stable spectrum of most ordinary detectors, and can better adapt to the temperature effect problem caused by the underwater gamma spectrum detector after entering water.

The present application relates to tailings disposal technical field, disclose a kind of for thickener underflow concentration detection system, comprising: data acquisition module, logarithmic counting rate is obtained by calculation, and mother liquor density and solid true density are synchronously obtained;Data calculation module, obtains the deposition slope in section and baseline drift rate by calculation;Logarithmic counting rate purification module, deposition cumulative term and wear baseline term are obtained according to the deposition slope in section and baseline drift rate by calculation, and logarithmic counting rate after purification is obtained according to this;Underflow slurry density conversion module, logarithmic counting rate after purification is converted into underflow slurry density;Concentration detection module, according to mother liquor density and solid true density, underflow slurry density is converted into underflow solid mass fraction.The present application is through systematic signal processing and data conversion mechanism, effectively eliminate the interference of pipe wall wear, deposition in pipe and other geometric factors to detection signal, greatly improve the accuracy and reliability of thickener underflow concentration detection.

The invention relates to the technical field of radiation detection, in particular to a gamma ray detector and a gamma ray detection system. The detector comprises a substrate, a shading shell, a scintillation crystal, a silicon photomultiplier tube array, a first reflecting layer and a second reflecting layer, the shading shell is connected with the substrate so as to define an open inner cavity with the substrate; the scintillation crystal is located in the open inner cavity; the silicon photomultiplier tube array is located in the open inner cavity and is coupled with the scintillation crystal through an adhesive, and the silicon photomultiplier tube array is connected with the substrate to obtain electric energy; the first reflecting layer is arranged around the scintillation crystal; and the second reflecting layer is connected with a cavity opening of the open inner cavity to form a sealing structure. The invention has the advantages of magnetic interference resistance, miniaturization and high counting rate.