34 results about "Nuclear electronics" patented technology

The invention belongs to the technical field of nuclear radiation detection and nuclear electronics, and relates to a nuclear radiation pulse accumulation signal judging and correcting method based on high-speed digital sampling. The method includes the steps of pulse accumulation judgment and pulse accumulation correction and specifically includes the steps of judging pulse accumulation, conducting differential on signals, judging the accumulation type, correcting pulse accumulation, calculating pulse waveform parameters, conducting cutting and correcting accumulated pulses. Compared with the prior art, the method has the advantages that the digitalization method of pulse accumulation judgment is set up, complex hardware equipment in a traditional spectrometer is abandoned, differential and analysis are conducted on collected output pulses through the digitalization method so that the current changes of the pulses can be formed, the method is simple and clear, the physical meaning is clear, the accumulation type can be accurately judged, the correction of pulse accumulation can be conducted, the use ratio of the signals can be effectively improved, energy resolution losses caused by pulse accumulation can be reduced, and meanwhile the pulse passing rate of a system is improved to the largest extent.

The invention relates to high speed parallel multichannel data system for nucleus spectrum and nuclear electronics. It is made up of 4 independent channels, and includes analog circuit, 14 bits ADC, and a 4 channel timer distributor. The analog signal would be transformed to digital quantity and input into large capacity FPGA chip to take online analysis of time, amplitude, sampling points information and relativity, taking effective data selection and inputting into host computer through network or USB2.0 interface.

The utility model relates to a nuclear physics experiment simulation system. The nuclear physics experiment simulation system includes a simulated nuclear radiation source, a simulated nuclear radiation detector and a nuclear electronics processing system; the simulated nuclear radiation detector receives simulated nuclear optical pulses emitted by the simulated nuclear radiation source and photomultiplier tube high voltage emitted by the nuclear electronics processing system; and the nuclear electronics processing system receives simulated nuclear voltage pulses which are emitted by the simulated nuclear radiation detector which is electrically connected with the nuclear electronics processing system. According to the nuclear physics experiment simulation system, the simulated nuclear radiation source generates optical pulses with corresponding nuclear radiation characteristics according to different selected nuclear radiation types through utilizing an electronics method so as to simulate a nuclear radiation source; the simulated nuclear radiation detector receives the optical pulses and processes the received optical pulses according to different selected experiment processes so as to generate nuclear physics experiment data, and generates simulated nuclear voltage pulses according to the nuclear physics experiment data; the nuclear physics experiment data can be provided for the subsequent nuclear electronics processing system so as to be analyzed and processed; and the analyzed and processed data can be available for observation and sensation of learners. The nuclear physics experiment simulation system has the advantages of high simulation of nuclear physics experiments, being more approximate to real nuclear physics experiments, excellent experiment effect and favorable teaching effect.

The invention discloses a spherical multilayer polyethylene moderation body, which is formed by accumulating a plurality of spherical polyethylene moderation bodies with different inner diameters layer by layer from inside to outside, wherein the inner diameter of the first spherical polyethylene moderation body is equal to the diameter of a spherical neutron detector 1, and the inner diameter of ith spherical multilayer polyethylene moderation body is equal to the outer diameter of the (i-1)th ball, wherein i is equal to 2, 3, 4 and so on. A neutron energy spectrum and fluence measurement device of a single probe comprises the spherical multilayer polyethylene moderation body, the spherical neutron detectors, a nuclear electronics circuit, a high and low voltage circuit, and a single chip. The spherical polyethylene moderation body can moderate the neutron, so that the neutron after being moderated can be detected by the neutron detectors. The nuclear electronics circuit can amplify the signals detected by the spherical neutron detectors and can implement n-Gamma screening. The single chip can process the signals and can display final result. The spherical multilayer polyethylene moderation body has the advantage of good consistency. The neutron energy spectrum and fluence information can be obtained by using the device disclosed by the invention.

The invention belongs to the field of signal processing technology and particularly relates to a digital coincidence multi-channel system for nuclear spectroscopy and nuclear electronics. In the system, an ADC is used to sample, a pulse signal waveform acquired by each channel is processed by a signal processor in real time to obtain the amplitude and arrival time of the pulse signal and store the amplitude and the arrival time in the computer; and after measurement, the amplitude and the arrival time of each pulse signal of each channel are read from the data stored in the computer, parameters of a delay time and a coincidence resolving time are selected according to a delay time spectral line, a computer ware is used to select coincidence pulse signals within the coincidence resolving time between a plurality of channels, and thus, a multi-parameter nuclear spectrum is formed. The digital coincidence multi-channel system provided by the invention has the advantages of simple structure, low cost, high signal acquiring and processing efficiency and the like.

The present invention discloses a Kalman filter channel-based pulse stacking correction method which mainly solves the problems in the prior art that the calculation is complex, an energy spectrum distorts, etc. The method comprises the following steps of utilizing a pulse shaper to generate a nuclear pulse signal Sn, obtaining the nuclear pulse signal Sn and then initializing the parameters of the nuclear pulse signal Sn, namely, selecting an initial point where the amplitude X0 of the outputted nuclear pulse signal Sn is 0; carrying out the weak signal removing processing on the nuclear pulse signal Sn, and obtaining the stacked nuclear pulse signals S1n; determining and extracting the stacked nuclear pulse signals S1n; constructing a Kalman filter state and measurement equation, and using a Kalman filter to process the extracted nuclear pulse signals S1n to obtain the nuclear pulse signals S2n; attenuating the nuclear pulse signals S2n, and determining whether to satisfy a removingstandard. By the above scheme, the Kalman filter channel-based pulse stacking correction method of the present invention achieves the purpose of separating the stacked pulse events, and has the very high practical value and popularization value in the nuclear radiation detection, the nuclear electronics technology and the digital signal processing fields.

The invention discloses an on-board radiation source positioning device, which belongs to the field of radioactivity detection. The device comprises gamma ray detection crystals arranged at the top part of a rotation shaft; each gamma ray detection crystal is composed of four plastic scintillators of the same size; the four plastic scintillators are correspondingly connected with four nuclear electronic signal processing units; the four nuclear electronic signal processing units are connected with a computer processing unit; and metal shading layers are arranged between the four plastic scintillators, between the plastic scintillators and the nuclear electronic signal processing units and between the plastic scintillators and the rotation shaft. Differences between deposited gamma rays of the four gamma ray detection crystals shaded by a lead plate are used, according to the dose rate ratio of the deposited gamma rays, a relation between the ratio and the distance between the radiation source and the device is obtained through calculation, and the radiation source can be quickly positioned. The invention also discloses a positioning method by using the above on-board radiation source positioning device.

The invention relates to the isotope measurement technology, in particular to an accelerator mass spectrometer with a simultaneous isotope measurement function. The accelerator mass spectrometer structurally comprises a sputter negative ion source used for generating negative ions and connected with an accelerating tube used for simultaneously accelerating a plurality of isotope ions, wherein the output end of the accelerating tube is connected with an isotope mass resolution system; the isotope mass resolution system is connected with a charge converting analysis and multi-receiving measurement system; the charge converting analysis and multi-receiving measurement system is connected with an ion detection system. The accelerator mass spectrometer can simultaneously accelerate a plurality of isotope negative ions, stable isotope negative ions in the accelerated isotope negative ions are measured by a stable isotope receiver, unstable isotope negative ions are converted into positive ions which are then measured by a detector, and measurement signals are simultaneously transmitted to a nuclear electronics and data acquisition unit after time matching for data operation. The accelerator mass spectrometer is simple in structure, convenient to operate and maintain and high in measuring accuracy.

The preparation method for polyaniline with high conductivity in magnetic field comprises, putting the preparation device for polyaniline in magnetic field environment; with acidic medium, oxidant and dopant, synthezing and doping polyaniline with high orientation and conductivity; using added magnetic field to increase orientation of conjugate conducting high polymer. Compared with existing domestic product, the product has better conductivity and anti-corrosiveness and fit to aeronautical, astronautical, mechanism, and nuclear electronic fields.

The invention relates to a multilayer spherical moderator container. A plurality of concentric hollow spherical shells having different inner diameters are combined with one another layer by layer from inside to outside so as to form the multi-layer spherical moderator container; the number i of the hollow spherical shells can be 1, 2, 3, 4, ..., and n; and if i is equal to 2, 3, 4, ..., n, a space between the i-th hollow spherical shell and the (i-1)-th hollow sphere spherical is communicated with an external liquid moderator loop through a pipeline corresponding to the space. The invention also provides a neutron energy spectrum real-time measuring device. The device includes a spherical neutron detector, a back-end nuclear electronic processing circuit, a multilayer spherical moderatorcontainer and a liquid moderator loop; the multilayer spherical moderator container wraps the spherical neutron detector; and the liquid moderator loop can control a liquid moderator in real time so as to make the liquid moderator fill or discharge from a space between an i-th hollow spherical shell and a (i-1)-th hollow sphere spherical shell provided that the number i of the hollow spherical shells is set to be 2, 3, 4, ..., and n, so that neutrons can be moderated, and can be easily detected by the spherical neutron detector. The neutron energy spectrum real-time measuring device of the invention can measure the energy spectrum of the neutrons in real time, and has the advantages of low cost and convenient use.

The invention relates to an active neutron personal dosimeter based on three silicon detectors, and a measurement method of the active neutron personal dosimeter. The personal dosimeter comprises a main detector, an outer transformant module, and a nuclear electronics system. The main detector and the outer transformant module comprise three passivation injection planar silicon detectors which aresequentially an Open detector, a Fast detector and an Albedo detector from the top to the bottom. A polyethylene layer and a 6LiF coating layer are disposed in front of the Open detector, a polyethylene layer is arranged in front of the Fast detector, and a boron-containing polyethylene layer, a polyethylene layer and a 6LiF coating layer are arranged in front of the Albedo detector. The nuclearelectronics system provides high voltages for all detectors, and obtains detection signals for multichannel analysis. The personal dosimeter provides two measurement modes. A direct reading mode can present the neutron fluence and personal dose equivalent information in real time, and a spectrum unfolding mode can give a more precise neutron field power spectrum. The personal dosimeter is wide inenergy measurement range, has the energy resolution capability, and can be used in an n-gamma mixed field.

The invention discloses a gas-filled detector for measuring 85Kr, which comprises a valve, a stainless steel shell, a reflective isolation film, a plastic scintillator, an optical coupling agent, a photomultiplier tube and an integrated nuclear electronics module. The detector is mounted in a shield and a sample is enriched through a gas processing module and purified to fill a sealed sample chamber. Beta rays emitted by the 85Kr are collected by the plastic scintillator to form scintillation light which is amplified by the photomultiplier tube and then recorded by the integrated nuclear electronics module. After the recorded data are transmitted to a PC terminal, 85Kr activity information in the sample can be obtained by comparison and analysis with the background. Compared with the current gamma spectrometer measurement, the detector can reduce the detection limit of 85Kr by about three orders of magnitude. Compared with a conventional gas detector, the detector is insensitive to a change in the sample composition. The detector can be widely used in quantitative analysis of radioactive 85Kr in gaseous effluents of nuclear power plants.

The present invention relates to the field of radiation measurement and nuclear electronics and provides a detector for high temperature and high radiation environment radioactive nuclide analysis and measurement. The detector comprises a main measurement probe for measuring a detected ray, a compensation probe for measuring an impurity ray in a measured ray surrounding environment and a pre-amplifier. The main measurement probe, the compensation probe and the pre-amplifier are subjected to far processing. According to the pre-amplifier, two paths of completely same pre-amplifier circuits are subjected to differential processing, one path is used for connecting the main measurement probe, and the other path is used for connecting the compensation probe. According to the detector, the remote collection of a weak pulse signal in a high temperature and high radiation environment, and the quantitative analysis and measurement problem of a radioactive nuclide in the high temperature and high radiation environment is solved at the same time.

The invention relates to a nuclear electronics experiment teaching instrument and an experimental method thereof. The teaching instrument comprises a mother board experimental box and multiple child board experimental modules. The teaching instrument is characterized in that the mother board experimental box is provided with a power supply unit and an expandable experimental platform; the expandable experimental platform comprises a power unit, a liquid crystal display unit, a child board installation interface unit, a data transmission unit and a bus unit; the multiple child board experimental modules comprise a pre-amplifier experimental module, a main amplifier experimental module, a single-track experimental module, a multiple-track experimental module, a timing experimental module, an hour converting experimental module, an coincidence and anti-coincidence experimental module, a counter experimental module, a pile-up-rejection experimental module and a data transmission module. The nuclear electronics experiment teaching instrument oriented to be used by students is safe, reliable and strong in operability.

The invention relates to the nuclear electronics technology, in particular to an all-digital two-dimensional coincident Doppler broadening system, comprising a first detector, a second detector , a host computer, a first acquisition channel, a second acquisition channel, an FPGA digital processing platform and a gigabit Ethernet port. The first acquisition channel and the second acquisition channel have the same structures. The first detector and the second detector are connected with the first acquisition channel and the second acquisition channel respectively. The FPGA digital processing platform is respectively connected with the first and second acquisition channels and the gigabit Ethernet port; and the gigabit Ethernet port is connected to the host computer. According to the system, the system design is simplified by using the dual-channel all-digital acquisition circuit; and the pulse extraction, time calibration, and time coincident analysis are realized in the FPGA. The ADC is used directly to carry out pulse sampling and then pulse shaping, baseline recovery, stack identification, amplitude extraction, and time calibration are performed by entering the FPGA digital processing platform, so that the peak-to-background ratio of the Doppler broadening spectrum is increased by 2 to 3 magnitude order.

The invention relates to the technology of nuclear electronics and nuclear detectors and specifically relates to a novel digital beta <+>-gamma coincidence positron annihilation lifetime spectrum system. The system comprises samples, a radioactive source, an avalanche diode, a vacuum chamber, a three-dimensional mobile device, a first coaxial electromagnetic lens, a second coaxial electromagneticlens, a first BaF2 scintillator detector, a second BaF2 scintillator detector, a first high-voltage power supply, a second high-voltage power supply, a third high-voltage power supply, a pre-amplifier, a first constant fraction timing discriminator, a second constant fraction timing discriminator, a third constant fraction timing discriminator, a coincidence device and a digital oscilloscope. Thesystem enables the radioactive source and the samples to be separated, adopts the avalanche diode to replace a plastic scintillator to serve as an initial signal generator, has higher time resolution,is simple in structure and convenient to measure, and can realize real-time in-situ measurement under conditions of high temperature, high stress and changes (stretch, distortion and the like) of sample structures.

The invention relates to the technical field of beam loss monitoring of ion accelerators in the technical field of nuclear electronics, and more particularly to a beam loss detector device for an ionaccelerator. The beam loss detector device comprises upstream and downstream beam position probes arranged on a vacuum tube at intervals, wherein the two beam position probes are connected to a clocktrigger through a front-end circuit; the clock trigger is connected with a high-speed sampling digital circuit board via an analog-to-digital conversion circuit; the upstream and downstream beam position probes acquire the synchronization signal of a particle beam and the high-speed sampling digital circuit board generates a digital signal to be processed. When a difference between the signal andits historical data exceeds a certain threshold or a difference between the upstream and downstream signals exceeds a certain threshold, an alarm signal output is generated. The differential beam intensity loss detection system using the beam position probes has a short response time, does not require a compensation circuit, and achieves high measurement accuracy through reasonable design.

The invention relates to an active detection system for a nuclear fuel rod. The system comprises a neutron source, a moderation shielding body, a scintillator detector array, a multichannel nuclear electronics and data acquisition system, a computer software system, a feeding and discharging frame and an automatic control system; the neutron source is arranged in the moderation shielding body, andthe detector array is arranged at the front end of the scintillator detector array; the scintillator detector array is located on a fuel rod detection channel activated by a fuel rod and is used fordetecting gamma rays emitted by the fuel rod activated by a neutron source, wherein the number of detectors in each channel detector array is greater than 6, and a hole channel for the fuel rod to pass through is formed in a detector crystal. According to the invention, a neutron source with a long half-life period can be used, so the active detection system does not need to replace the radioactive source in the whole life period; or the service time of the 252Cf neutron source arranged in the original active equipment can be prolonged, the frequency of changing the source is reduced, and theequipment operation cost is saved.

The invention discloses a gas-filled detector for measuring 85Kr, which comprises a valve, a stainless steel shell, a reflective isolation film, a plastic scintillator, an optical coupling agent, a photomultiplier tube and an integrated nuclear electronics module. The detector is mounted in a shield and a sample is enriched through a gas processing module and purified to fill a sealed sample chamber. Beta rays emitted by the 85Kr are collected by the plastic scintillator to form scintillation light which is amplified by the photomultiplier tube and then recorded by the integrated nuclear electronics module. After the recorded data are transmitted to a PC terminal, 85Kr activity information in the sample can be obtained by comparison and analysis with the background. Compared with the current gamma spectrometer measurement, the detector can reduce the detection limit of 85Kr by about three orders of magnitude. Compared with a conventional gas detector, the detector is insensitive to a change in the sample composition. The detector can be widely used in quantitative analysis of radioactive 85Kr in gaseous effluents of nuclear power plants.

The invention discloses a neutron radiation dose detection method based on needle-leaf pea dry seeds. The method comprises a neutron detection carrier needle-leaf pea seed placing and sampling method, a key measurement parameter SEI and StEI experimental acquisition method and a neutron absorption dose calculation method. The detection carrier used in the method is the needle-leaf pea seeds, and compared with a traditional detection method using a physical detector, by using the method of the invention, the price is only one hundred thousand or even one million, and the cost is low. The needle-leaf pea seeds belong to green organisms, and compared with a physical detector belonging to an electrical device, the needle-leaf pea seeds are more environment-friendly in subsequent recovery treatment after use. In addition, the needle-leaf pea seeds are high in resistance and easy to obtain, do not need special management, have the effects of reducing management cost and purchase cost, and are convenient to use. Compared with a traditional detection method using a nuclear electronics device, a greenhouse seedling raising experiment method adopted by the invention is easier to learn and master and convenient to popularize.

The invention relates to nuclear electronics technology, in particular to an all-digital two-dimensional coincidence Doppler broadening system, comprising first and second detectors and a host computer; also comprising first and second acquisition channels with the same structure, FPGA digital The processing platform and the Gigabit Ethernet port; the first and second detectors are respectively connected with the first and second acquisition channels, and the FPGA digital processing platform is respectively connected with the first and second acquisition channels and the Gigabit Ethernet port. The Ethernet port is connected with the upper computer. The system simplifies the system design by adopting a dual-channel all-digital acquisition circuit, and implements pulse extraction, time scaling and time coincidence analysis in FPGA. The ADC is directly used to sample the pulse, and then it enters the FPGA digital processing platform for pulse shaping, baseline recovery, stacking identification, amplitude extraction, and time scaling to improve the Doppler broadening spectrum peak-to-book ratio by 2-3 orders of magnitude.

The invention relates to the field of radiation measurement and nuclear electronics, and provides a containment pressure relief and exhaust activity monitoring system, which comprises a safety valve used for active pressure relief, a snakelike segmented cascade filter used for steam-water separation and aerosol filtration, a high-temperature flowmeter used for flow measurement and a detection device used for activity concentration measurement. The safety valve is communicated with a containment vessel, gas is subjected to pressure relief from the containment vessel through the safety valve and flows through the snakelike segmented cascade filter to realize gas-water separation and aerosol filtration, the filtered gas is measured by the flowmeter and then is measured by the detection device through the measuring pipe section, and the detection device gives radioactive activity concentration information. The monitoring system provided by the invention can effectively realize nuclear signal acquisition, processing, uploading and storage in a high-temperature, high-pressure and high-radiation environment, and solves the problems that a radiation monitoring system loses efficacy and radioactivity is difficult to measure in the high-temperature, high-pressure and high-radiation environment in the containment vessel.

The invention belongs to the technical field of nuclear radiation detection and nuclear electronics, and relates to a nuclear radiation pulse accumulation signal judging and correcting method based on high-speed digital sampling. The method includes the steps of pulse accumulation judgment and pulse accumulation correction and specifically includes the steps of judging pulse accumulation, conducting differential on signals, judging the accumulation type, correcting pulse accumulation, calculating pulse waveform parameters, conducting cutting and correcting accumulated pulses. Compared with the prior art, the method has the advantages that the digitalization method of pulse accumulation judgment is set up, complex hardware equipment in a traditional spectrometer is abandoned, differential and analysis are conducted on collected output pulses through the digitalization method so that the current changes of the pulses can be formed, the method is simple and clear, the physical meaning is clear, the accumulation type can be accurately judged, the correction of pulse accumulation can be conducted, the use ratio of the signals can be effectively improved, energy resolution losses caused by pulse accumulation can be reduced, and meanwhile the pulse passing rate of a system is improved to the largest extent.

The utility model relates to a nuclear physics experiment simulation system. The nuclear physics experiment simulation system includes a simulated nuclear radiation source, a simulated nuclear radiation detector and a nuclear electronics processing system; the simulated nuclear radiation detector receives simulated nuclear optical pulses emitted by the simulated nuclear radiation source and photomultiplier tube high voltage emitted by the nuclear electronics processing system; and the nuclear electronics processing system receives simulated nuclear voltage pulses which are emitted by the simulated nuclear radiation detector which is electrically connected with the nuclear electronics processing system. According to the nuclear physics experiment simulation system, the simulated nuclear radiation source generates optical pulses with corresponding nuclear radiation characteristics according to different selected nuclear radiation types through utilizing an electronics method so as to simulate a nuclear radiation source; the simulated nuclear radiation detector receives the optical pulses and processes the received optical pulses according to different selected experiment processes so as to generate nuclear physics experiment data, and generates simulated nuclear voltage pulses according to the nuclear physics experiment data; the nuclear physics experiment data can be provided for the subsequent nuclear electronics processing system so as to be analyzed and processed; and the analyzed and processed data can be available for observation and sensation of learners. The nuclear physics experiment simulation system has the advantages of high simulation of nuclear physics experiments, being more approximate to real nuclear physics experiments, excellent experiment effect and favorable teaching effect.

The invention relates to nuclear electronics technology, in particular to an instruction system and control method for Doppler broadening spectrum measurement, the system includes a programmable amplifier, high-speed ADC, FPGA digital pulse analysis system and host computer; FPGA digital pulse The analysis system includes an instruction set and a controller for executing instructions, a dual-channel filtering and amplitude extraction module connected to the controller, a Gigabit Ethernet sending module, a parameter pool, a data buffer, a sending selector, and a Gigabit Ethernet receiving module. Modules and Instructions Validation Modules. The control of the system guides the controller to complete the control function of the entire FPGA digital pulse analysis system through instructions, replacing the single-chip microcomputer, and at the same time eliminating the bottleneck of the communication rate, so that the FPGA digital pulse analysis system can send various data to the host computer at the same time. Do not interfere with each other. The controller can also receive instructions from the host computer to make real-time and flexible adjustments to any parameters that need to be modified.

The invention discloses a spherical multilayer polyethylene moderation body, which is formed by accumulating a plurality of spherical polyethylene moderation bodies with different inner diameters layer by layer from inside to outside, wherein the inner diameter of the first spherical polyethylene moderation body is equal to the diameter of a spherical neutron detector 1, and the inner diameter of ith spherical multilayer polyethylene moderation body is equal to the outer diameter of the (i-1)th ball, wherein i is equal to 2, 3, 4 and so on. A neutron energy spectrum and fluence measurement device of a single probe comprises the spherical multilayer polyethylene moderation body, the spherical neutron detectors, a nuclear electronics circuit, a high and low voltage circuit, and a single chip. The spherical polyethylene moderation body can moderate the neutron, so that the neutron after being moderated can be detected by the neutron detectors. The nuclear electronics circuit can amplify the signals detected by the spherical neutron detectors and can implement n-Gamma screening. The single chip can process the signals and can display final result. The spherical multilayer polyethylene moderation body has the advantage of good consistency. The neutron energy spectrum and fluence information can be obtained by using the device disclosed by the invention.

The preparation method for polyaniline with high conductivity in magnetic field comprises, putting the preparation device for polyaniline in magnetic field environment; with acidic medium, oxidant and dopant, synthezing and doping polyaniline with high orientation and conductivity; using added magnetic field to increase orientation of conjugate conducting high polymer. Compared with existing domestic product, the product has better conductivity and anti-corrosiveness and fit to aeronautical, astronautical, mechanism, and nuclear electronic fields.

The invention relates to an input end leakage current compensation type charge sensitive pre-amplifier, belongs to the technical field of nuclear electronics, and solves the problem of circuit bias current influence. The amplifier comprises a charge sensitive loop circuit and a compensation bleeder circuit. The charge sensitive loop circuit is connected with the detector and is used for carrying out integration accumulation on the detection current of the detector, converting the detection current into a voltage signal in direct proportion to the charge quantity and outputting the voltage signal to the post-stage circuit; the compensation bleeder circuit is connected between the output end and the input end of the charge sensitive loop circuit; an output voltage value of the charge sensitive loop circuit is monitored, and when the voltage value exceeds the linear amplification area, the accumulated charge quantity is discharged, the output voltage value is reduced, and the output voltage value returns to the linear amplification area; and compensation current is provided to compensate leakage current of the input end of the charge sensitive loop circuit. According to the invention,the charge-sensitive pre-amplifier works in a linear amplification region; and the leakage current of the input end is compensated, so that the effect of improving the energy resolution is achieved.

The invention provides a multichannel nuclear electronics data acquisition instrument, system and method. The instrument comprises a signal processing module, a counting acquisition module and a control module which are connected in sequence, wherein the signal processing module is used for receiving charge signals output by the multi-path detector, converting the multi-path charge signals into digital level signals and sending the digital level signals to the counting acquisition module; the counting acquisition module is used for respectively acquiring the number of pulses in a preset upper threshold value range and a preset lower threshold value range in the multiple paths of digital level signals, and sending the number of the multiple paths of pulses to the control module; and the control module is used for receiving the number of the multiple paths of pulses in sequence and sending the sorted number of the multiple paths of pulses to an upper computer through the network communication module. According to the multichannel nuclear electronics data acquisition instrument, centralized processing, centralized high-precision acquisition and sequential transmission of multichannel nuclear electronics data are realized, and a nuclear electronics instrument is simplified.