51 results about "Nuclear detection" patented technology

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

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

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

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

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

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

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

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

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

The invention 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.

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

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

The invention is suitable for the technical field of nuclear detection and embedded systems, and provides an embedded fission chamber assembly and a method for monitoring delayed neutrons thereof.The embedded fission chamber assembly comprises an outer cylinder, the outer cylinder serves as a shell structure of the assembly, a fission chamber body is arranged in the outer cylinder and fixedly installed in the outer cylinder, and the fission chamber body is arranged in the outer cylinder; and the fission chamber main body forms a basic framework of the detection core chamber. The fission chamber main body is internally provided with a gas filling chamber, and the gas filling chamber is used for filling working gas; a collecting electrode and a high-voltage electrode penetrating through the head and the tail are assembled on the collecting electrode in the gas filling chamber, the high-voltage electrode serves as an electric field applying end, and the collecting electrode serves as a signal output end; the outer wall of the collecting electrode and the inner wall of the high-voltage electrode are plated with high-concentration uranium 235 layers; the uranium plating layer serves as a fission material coating and directly participates in nuclear fission reaction caused by neutrons, a large number of fission fragments are generated, and ionization signals are remarkably enhanced. The design of the uranium plating layer can reduce the covering effect of the gamma-ray background on the neutron signal and improve the signal-to-noise ratio of the signal. Double electromagnetic shielding is achieved through the staggered design of the inner shielding layer and the outer shielding layer, external radiation interference and electromagnetic noise are restrained, and the signal distortion rate is reduced.

The invention provides a multi-layer scintillator probe, detector and method based on scintillation fiber, and belongs to the technical field of nuclear detection, the probe comprises a probe main body, the probe main body comprises a first scintillation fiber layer, a second scintillator layer and a third scintillator layer, the second scintillator layer is arranged between the first scintillation optical fiber layer and the third scintillator layer, the first scintillation optical fiber layer is used for discriminating gamma particles and beta particles, the second scintillator layer is used for absorbing the beta particles penetrating through the first scintillation optical fiber layer, and the third scintillator layer is used for measuring the gamma particles. The beta particles and the gamma particles in the beta-gamma mixed field can be identified, and the beta particle energy spectrum and the gamma particle energy spectrum in the beta-gamma mixed field can be accurately measured at the same time.

The invention discloses a current detection method, device and equipment for a nuclear detector, a medium and a program product, and the method comprises the steps: adjusting the temperature of an environment where the nuclear detector is located to a first temperature, so as to control a detection assembly to be switched to a superconducting state; wherein a pickup coil of the nuclear detector is subjected to current injection operation in advance; the detection assembly is electrically connected to the two ends of the pickup coil; detecting a magnetic flux change state of the pickup coil through a detection assembly in a superconducting state; and detecting whether the current injection operation successfully injects the current or not based on the magnetic flux change state.

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 utility model relates to a nuclear detection pre-amplifier signal self-adaptive preprocessing circuit structure, and solves the technical problems that the switching efficiency is low, the noise before and after switching is inconsistent, the operation error is easy to occur and the intelligence cannot be realized because the existing nuclear detection energy disperse spectroscopy needs to manually set an output signal adaptive to a pre-amplifier. The circuit comprises a driver, a rectifier, a differentiator, a limiter and a baseline shifter connected with an ADC (Analog to Digital Converter), which are sequentially connected along a signal transmission path, the rectifier converts the pre-amplification signal after driving into a positive signal with an unchanged amplitude absolute value, and outputs the positive signal to the differentiator; and the limiter limits the differentiated positive signal and outputs the differentiated positive signal to the baseline shifter. According to the self-adaptive preprocessing circuit structure for the pre-amplification signal of the nuclear detection, the pre-amplification signal is converted into a positive signal with an unchanged amplitude absolute value and limited, and unified preprocessing operation of the positive signal and the negative signal is realized. And a user does not need to care about the positive and negative polarities of the signal and the type of the pre-amplifier, so that the problems existing in manual switching are avoided.