40 results about "Alpha particle" patented technology

The invention discloses a compensation method and system for continuously, rapidly and accurately measuring the radon concentration in air, and the method comprises the steps: taking the number of nuclides in a measurement cavity at the initial moment of a current sampling period as an initial value, and obtaining a time-varying function of the number of nuclides in the measurement cavity in combination with a gas exchange and nuclide decay model; determining the theoretical total count of alpha particles in the current measurement period, and establishing a relational expression between the count of the alpha particles and the number of nuclides; based on the relational expression and the actual measurement count, the number of environmental radon atoms is obtained, and the radon concentration is calculated in combination with a radon decay constant; and finally, combining the number of radon atoms at the current sampling point and a model containing gas exchange and nuclide decay to obtain the nuclide number at the end of sampling, taking the nuclide number as the initial state of the next sampling period, switching the sampling points, and repeating the steps to realize continuous, rapid and accurate sampling. According to the method, through loop iteration, the balance waiting time is effectively saved, and continuous, rapid and accurate measurement of the radon concentration in the environment by a single radon measuring instrument is realized.

This invention relates to the field of neutron source technology, and particularly to a controllable isotope neutron source device based on ion migration and a method for generating neutrons. The device includes a casing, inside which are a target material module, a target ion migration system, a safety module, and an alpha particle source term. The target material module provides target nuclide ions. The alpha particle source term includes alpha radioactive nuclide material and target nuclide intercalation material. The safety module is composed of target nuclide intercalation material. The target ion migration system is connected to an external control field. Target nuclide ions migrate through the target ion migration system within the safety module and the alpha particle source term. This invention enables active controllability of the isotope neutron source, significantly improving safety. By ensuring sufficient contact between alpha particles and target nuclides to form a molecular intercalation structure, the (α,n) reaction efficiency is greatly improved. Furthermore, this neutron source can be used in combination with multiple modules according to application requirements, effectively increasing the neutron output flux.

The present invention discloses a system and method for measuring the deuterium-tritium fuel ratio in plasma, comprising an electron cyclotron radiometer, a microwave reflectometer, a Mirnov probe, electron cyclotron radiation imaging, a first collector, a central processing unit, an interferometer, a dynamic Stark effect spectrometer, a magnetic coil, a charge exchange spectrometer, a second collector, a high-performance computer, and a TAE frequency real-time processor. The deuterium-tritium fuel ratio can be obtained by accurately measuring the frequency of the toroidal Alfvén eigenmode in the burning plasma and accurately calculating the TAE frequency in the deuterium-deuterium plasma under the same conditions. Compared to the existing technology, even if the burning plasma is in an uneven distribution state, it can be measured as a whole, and the deuterium-tritium fuel ratio can be calculated based on the measured data, thereby providing a safe, accurate, and rapid method for measuring the deuterium-tritium fuel ratio for the heating effect of fusion product alpha particles, the high and low confinement mode conversion power thresholds, and the confinement time.

The application provides a fuel and a method for increasing the neutron source intensity of a nuclear reactor, wherein the abundance of O in the fuel is 1% to 50% 18 O is 1% to 50%, and alpha particles and the enriched 18 O can significantly enhance the initial neutron source intensity of a nuclear reactor core in a pressurized water nuclear power plant, and help to improve the start-up performance and reduce the dependence on external neutron sources. In the passive start-up mode without using an external neutron source, the application improves the isotope abundance of O in the fuel, and improves the (alpha, n) reaction neutron source in the nuclear reactor core in the pressurized water nuclear power plant. 18 O in the fuel, and improves the isotope abundance of O in the fuel, and improves the (alpha, n) reaction neutron source in the nuclear reactor core in the pressurized water nuclear power plant.

The invention belongs to the field of neutron tubes, and particularly relates to an alpha particle accompanying neutron tube for security check and a region measurement method based on the neutron tube. The neutron tube comprises a tube shell assembly, an ion source assembly, an acceleration collimation assembly, a deuterium tritium target assembly, a storage and an alpha particle detector, the ion source assembly is mounted at the upper end in the tube shell assembly; the acceleration collimation assembly is installed in the tube shell assembly and located on an output path of the ion source assembly. The deuterium tritium target assembly is installed at the lower end in the tube shell assembly and located on an output path of the acceleration collimation assembly. The storage device is installed at the lower end in the tube shell assembly. A mounting opening is formed in the lower end of the side wall of the tube shell assembly, the alpha particle detector is mounted at the mounting opening of the tube shell assembly, and the receiving surface of the alpha particle detector faces the target surface of the deuterium-tritium target body. According to the invention, the flight direction of neutrons can be determined by detecting the accompanying alpha particles, so that the purpose of regional detection is achieved.

A method of detecting alpha particles may include providing a layer of a scintillating slurry comprising a granular scintillating material in water onto a measurement surface of a sample; positioning the sample having the scintillating slurry within a detection chamber of detection apparatus; detecting photons produced by the granular scintillating material in the scintillating slurry when the granular scintillating material is excited by ionizing alpha radiation emitted by alpha particles within the sample using a photon detector and generating a corresponding output signal; and removing the sample and the scintillating slurry from the detection chamber.

The invention relates to the technical field of positron annihilation lifetime measurement, and provides a positron annihilation lifetime spectrum measurement device, which comprises an alpha particle generation device, an alpha particle detection device, a gamma ray detection device and a lifetime measurement device, and is characterized in that the alpha particle generation device generates alpha particles and first gamma rays through nuclear reaction; the first gamma ray enters a to-be-detected sample, and positron annihilation occurs in the to-be-detected sample to emit a second gamma ray; the alpha particle detection device is used for detecting alpha particles and generating an initial signal; the gamma ray detection device is used for detecting a second gamma ray and generating a termination signal; the lifetime measuring device is used for acquiring a time interval between the start signal and the termination signal to generate a positron annihilation lifetime spectrum. As alpha particles are easy to shield and the detection efficiency is higher than that of gamma rays, the alpha particles are used as initial signals, so that the screening efficiency of effective events and the overall counting rate of the system can be greatly improved, and the positron annihilation lifetime spectrum has good signal-to-noise ratio and measurement accuracy.

The invention discloses a tritium monitor for realizing alpha, beta and gamma background deduction and a tritium activity concentration detection method.The tritium monitor comprises a detector I, a detector II and a signal processing unit, and the detector I is used for detecting alpha particles, beta particles and gamma particles; wherein the beta particles comprise tritium decay beta particles and high-energy beta particles with energy higher than that of the tritium decay beta particles, and the detector II is used for detecting alpha particles, gamma particles and high-energy beta particles and outputting signals II corresponding to counting rates of the particles. The signal processing unit is electrically connected with the detector I and the detector II, and the signal processing unit is configured to be used for receiving the signal I and the signal II, calculating a background equivalent current jointly generated by the alpha particles, the gamma particles and the high-energy beta particles based on the signal II and a preset calibration coefficient, and calculating the total ionization current based on the difference value of the total ionization current and the background equivalent current. And obtaining a net tritium current, and determining the tritium activity concentration based on the net tritium current.

The application discloses a kind of real-time alpha particle detector optimization design method based on air scintillation, with the lowest detection sensitivity as design goal, through Monte Carlo analysis method, carry out multi-parameter optimization design, specifically through detector modeling, threshold and coincidence logic setting, the detection efficiency calculation of alpha particle, cosmic-ray background and the accidental coincidence count rate calculation of PMT and measurement time setting etc. Steps optimize the system parameters of detector, according to the lowest detection sensitivity lower limit principle, determine optimal detector model, threshold and coincidence logic and measurement time etc. The method is simple and easy to understand, high universality, can solve the problem of low detection efficiency of alpha particle and low signal-to-noise ratio of real-time alpha particle detector based on air scintillation due to low air light yield, reach the lowest detection sensitivity lower limit of alpha particle allowed in actual situation, applicable to the efficient real-time measurement of alpha particle concentration / activity under the condition of low radioactivity level with air scintillation.

The present invention discloses a method for obtaining the energy spectrum and angular distribution of a deuterium-tritium neutron source. The method adopts a D-T neutron radiation field measurement system based on a SiC detector, can simultaneously measure the companion particles of the two reactions, can distinguish them in the energy spectrum, and obtain the counting rates of alpha particles and protons; takes into account the influence of the D-D reaction caused by target deposition in the D-T reaction, obtains the energy spectrum and angular distribution of the D-T and D-D neutron sources, and effectively improves the accuracy of the energy spectrum and angular distribution; the method of the present invention has no requirements for target tube-related parameters such as a pipeline and a grating for the companion particles, is simple to operate, only needs to measure a set of data to obtain the energy spectrum distribution in the entire space, does not need to measure different angles one by one, and can measure all D-T neutron sources; and the method of the present invention can be applied to a DC beam or pulsed beam D-T accelerator neutron source with a reserved companion particle channel, especially when there is deuterium beam deposition on the target, and can more accurately obtain the energy spectrum and angular distribution of the D-T neutron source.

The neutron beam detection device of the present application is provided with: a first solar cell type detector, which has a conversion film attached to its surface that converts neutrons into any one of a charged particle beam of a photon, an alpha particle, a proton, a lithium nucleus, a gamma ray, and a beta ray, and generates a current by incident radiation; a radiation detector that generates a current having no sensitivity to neutrons as an output signal due to radiation incident; a current measurer that detects the current generated by the first solar cell type detector and the current generated by the radiation detector due to radiation incident as signals; and a flux calculation section that compares the current signals from the detector detected by the current measurer. The flux calculation section corresponds the detected current signals from the solar cell type detector and the radiation detector to a relationship between the flux of a prescribed kind of incident radiation and the detected current from the solar cell type detector and the radiation detector, which is obtained in advance, and calculates the flux of the neutron beam.

The application relates to an alpha particle measuring device, method, apparatus, storage medium and program product. The device comprises a cavity surrounded by a side wall, a cavity top and a cavity bottom; a collector and a cathode are arranged in the cavity; the collector is arranged on the cavity top and the cathode is arranged on the cavity bottom; the collector is parallel to the cathode; the distance between the collector and the cathode satisfies a first preset distance; the collector comprises a plurality of first anode filaments arranged in a first direction and a plurality of second anode filaments arranged in a second direction; the distance between each first anode filament and each second anode filament in a third direction is a second preset distance; the distance between two adjacent first anode filaments in the first direction is a third preset distance; and the distance between two adjacent second anode filaments in the second direction is a fourth preset distance. The method can improve the accuracy of alpha particle measurement results.

The application discloses a method for measuring surface contamination of long-distance alpha radioactive material, which comprises the steps of measuring long-distance alpha radioactive point source and measuring long-distance alpha surface contamination count rate. The measurement of long-distance alpha radioactive point source comprises intrinsic detection efficiency of alpha particles, collection efficiency calculation and detection efficiency calculation; the measurement of long-distance alpha surface contamination count rate comprises establishing a contamination count rate model, calculating the mean value of point source detection efficiency in each place in a detection area, calculating the expression of the radius R of the detection area D and performing a least square fitting process on the change relation of the radioactive surface source detection efficiency with the opening angle of a shielding body. The application detects fluorescent photons by using a single photon counter, and converts the measured count rate value into the count rate of surface contamination required in the operation intervention level by using the established model.

The application discloses a preparation method of SnBi / B4C radiation shielding composite material. The material selects SnBi alloy with high atomic number, large density, strong processability and corrosion resistance as a matrix, B4C particles with light weight, high strength, good stability and large neutron reaction cross section as reinforcing fillers, and is formed through a powder metallurgy process, so that the composite material with high strength and the ability of shielding thermal neutrons, gamma rays, X rays and alpha particles is obtained. Compared with traditional lead gamma ray shielding materials with single function, the SnBi / B4C radiation shielding composite material solves the problem that neutrons cannot be shielded, and the selected raw materials are non-toxic, so that the composite material is expected to replace lead and be used for radiation shielding in the medical field.

A device for determining radon concentration is provided. The device includes a diffusion chamber, that includes a number of openings that allow radon gas to enter and exit, and a radon sensing arrangement. The radon sensing arrangement includes at least one processing device and one or more detectors, arranged inside the diffusion chamber in such a way that no part of the diffusion chamber is located at a distance, perpendicular to the detector, of more than 20 mm from the closest part of a detector. The at least one processing device is arranged to determine the radon concentration by analyzing and processing the energy spectrum of alpha particles detected by the one or more detectors.

The online alpha combination detector of the application integrates ZnS(Ag) detector and PIPS (ion implantation type passivated silicon) detector; ZnS(Ag) and PIPS are not sensitive to environmental gamma rays, so that the device of the application has a lower background and a lower detection limit without additional shielding device; ZnS(Ag) is also not sensitive to beta rays, and the interference of beta rays on ZnS(Ag) can be ignored by reasonably setting the threshold value; for PIPS, the energy spectrum of beta rays is concentrated in the low energy region, and the interference of beta rays can also be excluded by energy spectrum analysis algorithm or improving the lower limit of the energy spectrum threshold; in this way, the influence of beta and gamma rays on the combination detector for measuring alpha particles is greatly reduced, and the detection accuracy of alpha particles is improved; the ZnS(Ag) detector is coupled with multiple PMTs, which further ensures the detection efficiency; the detection window structure benefits from the unique design and is easy to replace; the window materials such as aluminum foil, titanium foil and gold foil are flexibly adapted; the detector is resistant to strong acid and strong alkali and corrosion, and has a wider use scenario.

A neutron measurement system and method based on a nano-coated pixel sensor, relating to the field of neutron measurement technology. The neutron measurement system based on a nano-coated pixel sensor includes a detector; the detector includes an active pixel sensor; the photosensitive surface of the active pixel sensor is not encapsulated in glass, and the photosensitive surface of the active pixel sensor has a layered neutron conversion material. A neutron measurement method is applied to the neutron measurement system based on a nano-coated pixel sensor; the method is as follows: a neutron undergoes a nuclear reaction with a target element, and the generated alpha rays are incident on the photosensitive surface of the active pixel sensor, causing the active pixel sensor to generate a radiation response signal; the indirect measurement of neutrons is achieved by statistically analyzing the radiation response signal. The advantage of this invention is that by combining a specific neutron conversion material with an active pixel sensor, neutron detection is transformed into alpha particle detection, which is the strength of the active pixel sensor, significantly improving the detection efficiency of neutrons (especially thermal neutrons).

The invention provides an intrinsic measurement method and device for thorium. The intrinsic measurement method comprises the following steps: recording detection time of alpha particles released by decay of to-be-measured < 220 > Rn gas and daughter < 216 > Po in a measurement chamber; performing Bayesian analysis according to the detection time, and calculating a 220Rn-216Po true coincidence count; and according to the < 220 > Rn count, the < 216 > Po count and the < 20 > Rn-< 216 > Po true coincidence count, calculating the activity concentration of the thorium. According to the intrinsic measurement method and device, two alpha particles emitted by successive decay of 220Rn and 216Po are utilized to form an intrinsic characteristic conforming to a signal, so that the detection efficiency is reduced; the detection efficiency is reduced, so that the method and the device do not need to measure the detection efficiency of the standard scale from the outside, and have self-traceability; meanwhile, the influence of the change of the detection efficiency on the measurement accuracy is avoided, and the measurement accuracy is improved.

The invention relates to a DT labeled neutron source transmission CT imaging detection system and method.The DT labeled neutron source transmission CT imaging detection system comprises a neutron source device, a sample table, a ray detector and a data acquisition and analysis system.The neutron source device is a DT neutron source, and the ray detector comprises a neutron detector array and an associated alpha array detector; the neutron detector array and the associated alpha array detector are respectively arranged in two opposite directions of the neutron source device, the sample table is arranged between the neutron source device and the neutron detector array, and the neutron detector array and the associated alpha array detector are respectively connected with the data acquisition and analysis system. According to the method, the transmission neutron counting rate of each neutron detector unit is obtained by using a flight time method according to time-space correlation characteristics of neutrons and alpha, a high-signal-to-noise-ratio transmission neutron image is obtained by using a tomography mode, and a three-dimensional image structure of a detected sample is obtained by using a filtered back projection algorithm.

This invention relates to a method for analyzing the energy spectrum of alpha particles in mixed radiation fields using a CR-39 track detector based on step-by-step etching and energy attenuation. The method first etches the CR-39 with a potassium hydroxide-ethanol-water (PEW) solution, utilizing the significant differences in the tracks revealed by protons, alpha particles, and heavy ions to effectively distinguish alpha particles. To address the problem of a narrow energy window for alpha particle track revealing, this invention proposes a novel etching and identification method. By placing a series of energy-degrading sheets of varying thicknesses in front of the CR-39, the wide-spectrum alpha particles are attenuated to the optimal detection range in the spatial dimension. Simultaneously, through multiple step-by-step etching sessions of varying durations, the measurement window is broadened in the temporal dimension, allowing for the acquisition of the alpha particle energy spectrum in a short time, ultimately achieving accurate reconstruction of the alpha particle energy spectrum. This invention achieves high-purity identification and accurate measurement of alpha particles across a wide energy spectrum in complex mixed radiation fields, offering advantages such as low cost, ease of operation, and reliable results.

The present invention belongs to the field of radioactive environmental protection, and specifically relates to a method for reducing the radioactive intensity of a field work site, comprising: step (1): determining the distribution characteristics of the radioactive field in the field work site; step (2): physically removing easily handled highly radioactive materials; step (3): using a coarse gravel layer to adsorb radon gas and block alpha particles; step (4): using a metal shielding blanket layer to block radon gas and beta rays; and step (5): using a fine-grained sand and gravel protective layer to block gamma rays. The method of the present invention effectively solves the problem of radioactive radiation protection in field work sites during the exploration or mining of radioactive mineral deposits.

The invention provides a device and method for synergistically producing astatine-211 and copper-64 based on a liquid target, and the device comprises a circulating pipeline which is provided with a liquid inlet; a sealing cover capable of being opened and closed is arranged on the liquid inlet; the beam irradiation window is arranged on the outer wall of the circulating pipeline; the circulation driving unit is mounted on the circulation pipeline; the heating evaporation unit is mounted on the circulating pipeline; the condensing unit is communicated with the circulating pipeline and is used for condensing astatine-211 gas; the collecting container is communicated with an outlet of the condensing unit and is used for collecting a final product; and the copper-64 production unit is positioned on the rear side of the irradiation direction of the beam irradiation window and is used for producing copper-64 through nuclear reaction by using secondary neutrons generated by irradiating the liquid lead-bismuth alloy with the alpha particle beam. The astatine-211 and copper-64 two important medical radionuclides are synergistically produced in the same device, and the equipment utilization rate and the production efficiency are remarkably improved.

The invention relates to a device for radiation detection and analysis, in particular to a portable alpha particle sensor suitable for the identification and quantification of the radioactive decay product-alpha particles-. The proposed invention is a battery-powered pulsed ionization chamber alpha particle sensor comprising at least one battery, at least one switch S, a voltage converter DC / DC, a capacitor C, a processor MCU, a current pulse amplifier A and an ionization chamber K in which a zero potential electrode is placed. The ionization chamber K is designed such that an alpha particle source can be placed therein. Furthermore, at least one battery is electrically connected to the voltage converter DC / DC via a switch S, the operation of which can be controlled by the processor MCU. And the voltage converter DC / DC is electrically connected with the capacitor C and the ionization chamber K. And the electrode of the ionization chamber K is electrically connected with the processor MCU through the current pulse amplifier A. Furthermore, the processor MCU is adapted to execute the following instructions: (i) count the electrical pulses N from the K electrode of the ionization chamber and amplified by the amplifier A; (ii) electrically connecting a supply of electrical energy from the at least one battery to the voltage converter DC / DC and other parts of the circuit in a controllable, periodic manner through the at least one switch S; (iii) determining the value of the voltage across the capacitor C and electrically disconnecting the supply of electrical energy from the battery from the voltage converter DC / DC and other parts in the circuit by the switch S when a previously set maximum value of the voltage is reached.

A diagnostic device and method detect target molecules in a liquid sample using radioisotopes that undergo alpha decay. The liquid sample is introduced onto a first portion of a permeable membrane, where its target molecules chemically bind to molecular tags. Each molecular tag includes both an alpha-emitter and a capture molecule designed to bind to the target molecule. The sample, including any bound target molecules, undergoes capillary flow to a second portion of the membrane, where an alpha-particle detector detects any bound alpha-emitters. The alpha-emitters may be radioactive nanoparticles (e.g. polonium-210) coated with an environmental protectant (e.g. gold). The detector may include CMOS diodes or a charge-coupled device. The device may include an indicator that signals when the detector detects alpha-particles above a given threshold in the second portion.

Devices for the radiation detection and analysis, in particular to portable alpha particle sensors adapted for the identification and quantification of radioactive decay products—alpha particles including a battery-powered pulse ionization chamber alpha particle sensor comprising at least one electric battery, at least one switch S, a voltage converter DC / DC, a capacitor C, a processor MCU, a current pulse amplifier A, an ionization chamber K with an electrode of zero potential placed therein. The ionization chamber K is designed with the possibility of placing a source of alpha particles in it. Furthermore at least one electric battery is electrically connected to the voltage converter DC / DC by means of a switch S, the operation of which is controllable by the processor MCU. The voltage converter DC / DC is electrically connected to the capacitor C and the ionization chamber K. The electrode of the ionization chamber K is electrically connected to the processor MCU through the current pulse amplifier A. The processor MCU furthermore is adapted to execute the instructions: (i) count electrical pulses N, which coming from the K electrode of the ionization chamber and which are amplified by the amplifier A; (ii) by means of at least one switch S, controllably periodically electrically connect the supply of electric energy from at least one electric battery to the voltage converter DC / DC and further in the circuit; (iii) determine the voltage value on the capacitor C and, upon reaching the previously set maximum value of the voltage, by means of the switch S, electrically disconnect the supply of electric energy from the electric battery to the voltage converter DC / DC and further in the circuit.

The present disclosure belongs to the technical field of nuclear medicine, and provides a dose calculation method for radiopharmaceuticals. The method adopts organ-cell geometric mapping and S-value index to accurately calculate the self-dose of alpha particles and the cross-fire dose of gamma rays / beta particles; based on the LQ model, dynamic RBE and hypoxic OER correction are realized, and the dose results directly usable in clinics are output, which greatly improves the dose calculation accuracy and efficiency of targeted alpha therapy.

The online alpha particle detector of this invention integrates a ZnS(Ag) detector and a PIPS (ion-implanted passivated silicon) detector. Both ZnS(Ag) and PIPS are insensitive to ambient gamma rays, allowing the device to achieve low background and detection limits without additional shielding. ZnS(Ag) is also insensitive to beta rays; with proper threshold setting, the interference of beta rays on ZnS(Ag) is negligible. For PIPS, the energy spectrum of beta rays is concentrated in the low-energy region; interference from beta rays can be eliminated through energy spectrum analysis algorithms or by increasing the lower limit of the energy spectrum threshold. Thus, the influence of beta and gamma rays on the combined detector's measurement of alpha particles is greatly reduced, improving the detection accuracy of alpha particles. The ZnS(Ag) detector is coupled with multiple PMTs, further ensuring detection efficiency. The detection window structure, thanks to its unique design, is easy to replace, and the window materials—aluminum foil, titanium foil, and gold foil—are flexibly adaptable. The detector is resistant to strong acids and alkalis and corrosion, enabling a wider range of applications.

The application provides a CZT radiation detection device based on a three-dimensional electrode and a particle discrimination method, aiming at discriminating alpha, beta and gamma from the source. The CZT radiation detection device adopts a cathode as a radiation incident window, and shallow layer induction electrodes and deep layer collection electrodes are arranged on the side of the crystal, and an anode is arranged on the surface opposite to the cathode, thereby forming a three-dimensional electrode system. The application utilizes the essential difference in the action depth of alpha, beta and gamma rays in the CZT crystal, and the unique'strong / weak' combination characteristics of the electrode signals, and realizes high-fidelity discrimination of alpha, beta and gamma in the mixed radiation field through the signal distribution characteristics that alpha particles generate strong signals in the shallow layer induction electrodes, the energy deposition depth of beta particles in the CZT crystal has low dispersion, and the energy deposition depth of gamma rays in the CZT crystal has high dispersion.

The invention relates to radiation detection and analysis devices, in particular, to portable alpha particle sensors adapted for the identification and quantification of radioactive decay products - alpha particles. The proposed low-intensity alpha particle detection device ionization chamber with an electric current pulse amplifier contains an electrode placed in the ionization chamber with zero potential and a protective ring placed around the electrode. The electric current pulse amplifier is placed inside the ionization chamber with the possibility of being electrically connected to a power source, as well as with the possibility of being electrically connected to a processor for supplying an amplified electric current pulse to the processor. This design allows avoiding interference caused by an external electric field without additional shielding of the amplifier.