34 results about "Nuclear electronics" patented technology

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 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 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 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 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 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.