65 results about "Nuclear detection" patented technology

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 toeffectively 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.

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 invention discloses a beta < + >-gamma-gamma coincidence positron annihilation lifetime-momentum correlation spectrometer, and belongs to the technical field of nuclear detection. The spectrometer comprises a positron annihilation life detection module, a positron annihilation gamma photon energy detection module, a signal acquisition module and a control and analysis module, and the positron annihilation life detection module is used for acquiring a life part in an AMOC spectrum; the positron annihilation gamma photon energy detection module is used for acquiring a momentum part in an AMOC spectrum by detecting gamma photons generated by positron annihilation; the signal acquisition module is used for acquiring signals generated by the positron annihilation life detection module and the positron annihilation gamma photon energy detection module; the control and analysis module is used for controlling the signal acquisition module and obtaining an AMOC spectrum based on signals acquired by the signal acquisition module. According to the method, the coincidence counting rate can be effectively improved, good coincidence time resolution and extremely low source components are achieved, and the construction cost of a spectrometer can be reduced.

The invention discloses an ex-core nuclear detection device and system and a detection data processing method thereof.The ex-core nuclear detection device comprises a plurality of source range detector assemblies, a plurality of middle range detector assemblies and a plurality of power range detector assemblies which can be fixed to the boundary of a pressure vessel of a reactor to be detected; the plurality of source range detector assemblies, the plurality of middle range detector assemblies and the plurality of power range detector assemblies all comprise multi-layer detection structures; wherein the multi-layer detection structure comprises a detector body, a moderated material structural body and an aluminum shell which are arranged layer by layer from inside to outside. According to the out-of-pile nuclear detection device, not only can the detection sensitivity of various types of detector assemblies be improved by additionally arranging the moderated material structural body and the aluminum shell on the detector assembly, but also the aluminum shell can prevent the moderated material of the moderated material structural body from deforming in a high-irradiation environment.

The nuclide identification method, system and electronic device disclosed in the present invention relate to the field of nuclide identification. Based on the Bayesian method and sequential posterior probability, the present invention greatly improves the universality of the method by setting the value range of the time interval on the decision function instead of directly giving a preset time interval parameter; the background probability density function and the Compton probability density function in the ROI area are determined according to statistical characteristics, and the energy Bayes factor and the time Bayes factor are determined based on the energy and time interval information in the nuclear detection event sequence obtained by measurement. Combining the two factors, effective identification and differentiation of Compton plateau can be achieved. Under the same identification conditions and when the same confidence level is set, the nuclide identification method provided by the present invention can effectively identify the existence and type of radioactive nuclides faster than the energy spectrum decomposition analysis-characteristic peak matching method; compared with the existing nuclide identification methods, the nuclide identification method provided by the present invention is more universal.

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 invention discloses an SPECT imaging device, an SPECT imaging system and a diagnosis combination. The SPECT imaging device comprises a rack and a nuclear detector group. The rack is provided with a through hole for a detected object to pass through. The through hole has a central axis. The nuclear detector group is arranged on the end face of the rack and comprises a plurality of longitudinal detectors arranged on the upper side and the lower side of the central axis and a plurality of transverse detectors arranged on the left side and the right side of the central axis, and the longitudinal detectors are used for obtaining longitudinal images of a detected object; the plurality of transverse detectors are used for acquiring a transverse image of the detected object, and the distance between the longitudinal detector and the central axis is smaller than that between the transverse detectors and the central axis. According to the SPECT imaging device, the collection efficiency is improved, the sensitivity is improved, and the resolution ratio of a detection image is improved.

The invention discloses a positron annihilation coincidence Doppler broadening spectrometer based on beta +-gamma-gamma coincidence, which belongs to the technical field of nuclear detection and comprises a coincidence signal generation module, an annihilation gamma photon detection module, a signal acquisition module and a control and analysis module, the coincidence signal generation module is used for detecting positron generated by decay of the positron source and generating coincidence signals for case judgment and selection; the annihilation gamma photon detection module is used for detecting gamma photons generated by positron annihilation and generating pulse signals containing energy information; the signal acquisition module is used for acquiring coincidence signals and pulse signals; and the control and analysis module is used for controlling the signal acquisition module and acquiring a positron annihilation coincidence Doppler broadening spectrum from the acquired coincidence signal and the pulse signal. According to the positron annihilation coincidence Doppler broadening spectrometer, the extremely low source component proportion can be achieved, and then the accuracy of a test result is improved.

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.

The present invention relates to the field of plasma physics nuclear detection technology, and in particular provides a short-pulse X-ray source polarization measuring instrument and a polarization measuring method. The measuring method includes: the incident X-ray falls on a scatterer through a collimation component to generate scattered photons, and the scattered photon signals are detected by a semiconductor pixel detector; the measured value E1 of the energy of the scattered photons is obtained by using the semiconductor pixel detector, and the energy E0 of the X-ray photons is calculated based on the measured value E1; the pixel position of the scattered photons is obtained by using the semiconductor pixel detector; based on the pixel position of the scattered photons, the polarization direction and polarization degree of the X-ray are obtained by data fitting. The purpose is to solve the problem that the existing polarization measuring instrument cannot quickly measure the polarization degree and realize the measurement of the energy of the incident X-ray without knowing the polarization direction of the X-ray, and realize the single-shot measurement function of the polarization degree and energy spectrum of the short-pulse X-ray source.

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 invention discloses a vehicle-mounted portable small particle detection device and detection system, and relates to the technical field of particle detectors, and the device comprises a radiation shielding layer, a radioactive source, a small hole, HDPE, an EJ-276 plastic scintillator, a light guide, an XP3232PMT, a packaging clamp, a BNC signal interface, an SHV high-voltage interface, a BNC coaxial signal line, an SHV high-voltage line, a negative high-voltage power supply, a DAQ, a USB data line and an upper computer. Accurate signal discrimination can be provided under high sensitivity, the peak sensitivity is matched with the emission spectrum of PMT, the signal detection accuracy is ensured, and effective discrimination of neutrons and gamma rays has extremely high application value in the fields of nuclear reactor safety monitoring, nuclear detection and the like.

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.

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.

The present invention relates to a readout electronics circuit system for a heavy ion beam telescope and a method of using the same. The system includes a front-end readout control module, a data aggregation module, a trigger and clock module, and a computer. The front-end readout control module is used to receive the control signal from the data aggregation module and the clock and trigger signals provided by the trigger and clock module, and amplify and digitize the voltage pulse signals output by the corresponding silicon pixel chips in the heavy ion beam telescope to obtain processed data frames. The data aggregation module is used to aggregate and process the data frames processed by several front-end readout control modules to determine the track of the particle. The trigger and clock module is used to generate multiple trigger signals and multiple clock signals. The computer is used to control the front-end readout control module, the data aggregation module, and the trigger and clock module. The present invention can be widely applied to the fields of high-energy physics experiments and nuclear detection technologies.

The invention relates to a self-checking system, method and device for portable nuclear detection equipment, and the system comprises a scintillator which is used for transmitting an optical signal when receiving nuclear radiation; the photomultiplier circuit is used for carrying out photoelectric conversion on the light emitted by the scintillator crystal; the multichannel analyzer is used for detecting a response signal of the photomultiplier circuit and carrying out quantitative analysis on the signal; the LED lamp is embedded between the scintillator and the photomultiplier tube circuit; and the LED lamp is connected with the FPGA chip. The self-checking method comprises the steps of starting a self-checking mode, adjusting the high-level time of the LED lamp to adapt to system gain, detecting and analyzing a response signal of the photomultiplier circuit, and adjusting self-checking parameters in time. The portable nuclear detection equipment is integrated with the self-checking system, and the processor and the memory are used for processing signals and storing data, so that the accurate monitoring and recording of the running state of the equipment are ensured. According to the invention, the self-checking efficiency and precision of the nuclear detection equipment are effectively improved, and the stability and reliability of the equipment in various environments are guaranteed.

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 invention discloses an intelligent detection terminal for radiation dose in a nuclear medicine diagnosis and treatment area and a method thereof. The terminal comprises: a nuclear detection module, a central control module and a peripheral module; the nuclear detection module is used for detecting the radiation dose in the nuclear medicine diagnosis and treatment area, and sending the detected electrical signal to the central control module; the central control module is used for processing and analyzing the electrical signal data, and generating corresponding control instructions according to the analysis results; the peripheral module is used for receiving the control instructions sent by the central control module, and completing corresponding operations according to the control instructions; the method for processing data is to perform intelligent smoothing processing on the count rate through a sliding window; the invention can effectively realize dynamic monitoring of the radiation dose in the nuclear medicine diagnosis and treatment area and radiation safety early warning, and the method can achieve the purpose of dynamically elastically increasing and decreasing sample data, effectively filter the instantaneous distortion value, and improve the corresponding sensitivity of the detection data.

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 belongs to the technical field of halide semiconductor nuclear detection, and particularly relates to a bipolar charge transfer halide semiconductor single crystal for high-energy radiation detection and a preparation method and application thereof. The general formula of the crystal is Cs1-xAxPb1-yByBr3-zXz, A is one or more of Na, K, Rb, Cu, Tl and H3O, B is one or more of Si, Ge, Sn, Mg, Ca, Sr, Ba, Zn, Cd and Hg, X is one or more of F, Cl, I, BF4, HCOO, OH, CN, SCN, NCS, SH, NO3 and H2POO, 0 < = x < = 1, 0 < = y < = 1, and 0 < = z < = 3. Zone-melting purification is combined with the vertical Bridgman method, the crack-free large-size high-quality single crystal is prepared, the crystal yield and the device uniformity are improved, bipolar charge transfer is achieved, the device structure is simplified, and the method can be widely applied to the field of nuclear detection.

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 present invention relates to a geological advance prediction method and device based on cosmic ray muons, belonging to the field of nuclear detection technology, and solves the problems of complex operation, low detection efficiency and accuracy, small detection range, and high cost of existing geological detection methods. The method includes directly detecting cosmic ray muons by using a muon detection device to obtain the first flux information of muons and the first set of scattering angles of muon scattering; placing the muon detection device inside the geological target to be measured to obtain the second flux information of muons and the second set of scattering angles of muon scattering; obtaining the scattering density length of the geological target to be measured according to the first set of scattering angles and the second set of scattering angles, and obtaining the material density length of the geological target to be measured according to the first flux information and the second flux information; and performing geological advance prediction on the geological target to be measured according to the scattering density length and the material density length. The method is simple to operate, has high detection efficiency and accuracy, a large detection range and low cost.

The utility model discloses a special five-core detection probe for nuclear magnetic resonance, which comprises a probe main body, a first switch is arranged on one side above the probe main body, a second switch is arranged on the other side above the probe main body, a carbon phosphorus interface is arranged on the front side of the probe main body, a deuterium interface is arranged on one side of the carbon phosphorus interface, and a deuterium interface is arranged on the other side of the deuterium interface. A hydrogen-fluorine interface is mounted on one side of the deuterium interface; according to the five-nuclear detection probe special for nuclear magnetic resonance, through cooperative use of the first switch, the second switch, the carbon-phosphorus interface, the deuterium interface and the hydrogen-fluorine interface, the high-frequency detection interface is the hydrogen-fluorine interface for hydrogen-fluorine switching and is controlled by the second switch, and the intermediate-frequency interface channel is the carbon-phosphorus interface for carbon-phosphorus switching and is controlled by the first switch and is controlled by the deuterium interface and the hydrogen-fluorine interface. The low-frequency interface channel is a deuterium interface, the three channels work at the same time to observe the quantum coupling relation between nuclear magnetic resonance, multiple atomic nucleuses can be detected at the same time, and the experiment efficiency and accuracy are greatly improved.