16 results about "Neutron activation analysis" patented technology

This invention relates to the field of extraterrestrial resource exploration technology, and discloses a high-resolution reconstruction method for elemental distribution images based on PGNAA technology. This method divides the overall detection area into several sub-regions of equal area, measures the types and abundance of elements within the overall detection area using transient gamma-ray neutron activation analysis (PGNAA), and uses the neutron flux information of each sub-region as a boundary condition, combined with the neutron cross-sectional information of each element, to perform inversion calculations on the types and abundance of elements within each sub-region, thereby achieving high-resolution reconstruction of the elemental distribution image within the overall detection area. The method proposed in this invention can reconstruct elemental distribution images from low resolution to high resolution within the detection area. Furthermore, by registering and aligning the obtained high-resolution elemental distribution image with a high-resolution image of the Earth's surface topography, it can obtain the "coloring" information fusion of the surface elemental distribution image of extraterrestrial objects, providing data support for the exploration of the distribution of extraterrestrial resources.

The utility model relates to the technical field of radiation detection, in particular to a shielding structure and a neutron activation analyser, the shielding structure comprises an outer shell and a partition plate, a hollow cavity is formed in the outer shell, the partition plate is arranged in the hollow cavity to divide the hollow cavity into two shielding cavities arranged along the length direction of the outer shell, and the shielding cavities are arranged in the outer shell. Each shielding cavity is filled with the shielding filler, the hollow cavity is divided into the two independent small shielding cavities through the partition plate, and by means of the arrangement, when the shielding structure is subjected to external physical interference, offset of the shielding filler is limited in each independent shielding cavity through the physical blocking effect of the partition plate; and the filler void ratio of the shielding filler of each shielding cavity only slightly fluctuates without obvious difference, so that the shielding effectiveness of the shielding structure is improved.

Systems and methods for sorting metal scrap such as but not limited to aluminum scrap includes a transport system for transporting the metal scrap to a prompt gamma neutron activation analysis device and / or with a prompt gamma neutron activation analysis device integrated into the transport system. A method of sorting metal scrap may include receiving metal scrap of an aluminum alloy and determining composition information of the metal scrap based on gamma radiation emitted by the metal scrap as a result of neutron irradiation. The method includes assigning the metal scrap to a class of a plurality of predetermined classes of the aluminum alloy based on the determined composition information and sorting the metal scrap based on the assigned class.

A method of non-destructive testing (NDT) using prompt gamma neutron activation analysis (PGAA) and a suite of algorithms based on various mathematical algorithms, includes: analyzing stored spectra for net peak areas; determining aggregate type from the analyzed stored spectra; calculating dominant element ratios; solving for dominant element mass fractions; calculating elemental mass fractions; solving a linear equations system including a coefficient matrix; and determining material components.

The invention discloses a coal quality multi-element nondestructive analysis method based on a compact D-D neutron source, relates to the technical field of nondestructive detection, and solves the technical problem that the existing neutron activation analysis technology based on a nuclear reactor cannot quickly and accurately detect the content of each element in a coal sample due to high equipment cost, large volume and complex operation. The method comprises the following steps: preparing a simple substance sample of each element, acquiring a pure gamma-ray energy spectrum of the simple substance sample by using a gamma-ray detector, and constructing a single element spectrum matrix; preparing a simulated coal sample, and obtaining a pure gamma-ray energy spectrum of the simulated coal sample; based on the single-element spectrum matrix and the pure gamma-ray energy spectrum of the simulated coal sample, analyzing the element content of the simulated coal sample; comparing the element content of the simulated coal sample during preparation with the element content of the simulated coal sample obtained by analysis, and determining a test method of coal element information in reality; according to the method, the content of various elements in the coal sample can be rapidly and accurately detected, and the method is crucial to development and utilization of coal resources.

The utility model discloses a neutron generator with a shielding body. The neutron generator comprises a shell, a neutron tube and the shielding body, wherein the front end of the shell is connected with a detector; in the first direction from the front end of the shell to the rear end of the shell, the shielding body and the neutron tube are sequentially located in the shell, so that the shielding body is used for shielding gamma rays generated by neutrons directly emitted to the detector from the neutron tube, interference to the detector is reduced, and the detection efficiency is improved. The accuracy of detection data of the detector is improved, and the accuracy of neutron activation analysis data is ensured.

The application discloses a coal quality multi-element nondestructive analysis method based on a compact D-D neutron source, relates to the technical field of nondestructive testing, and solves the technical problem that the existing neutron activation analysis technology based on a nuclear reactor cannot quickly and accurately detect the content of each element in a coal sample due to high equipment cost, large size and complicated operation; the application prepares elemental samples of each element, collects pure gamma energy spectrum of the elemental samples by using a gamma detector, and constructs a single-element spectrum matrix; a simulated coal sample is prepared, and its pure gamma energy spectrum is obtained; based on the single-element spectrum matrix and the pure gamma energy spectrum of the simulated coal sample, the content of elements in the simulated coal sample is analyzed; the content of elements when the simulated coal sample is prepared is compared with the content of elements in the simulated coal sample obtained through analysis, and a test method for coal quality element information in reality is determined; and the application realizes quick and accurate detection of the content of multiple elements in a coal sample, which is crucial for the development and utilization of coal resources.

The invention relates to the technical field of extraterrestrial celestial body resource exploration, and discloses an element distribution image high-resolution reconstruction method based on a PGNAA technology. The method comprises the following steps: measuring the types and contents of elements in a whole detection region based on a prompt gamma ray neutron activation analysis technology, and carrying out inversion calculation on the types and contents of the elements in each sub-region by taking sub-region neutron flux information as a boundary condition and combining neutron cross section information of each element; and high-resolution reconstruction of the element distribution image in the whole detection area is realized. According to the method provided by the invention, the reconstruction of the element distribution image in the detection area from low resolution to high resolution can be realized, the obtained high-resolution element distribution image is further registered and aligned with the surface landform high image, and the coloring information fusion of the surface element distribution image of the extraterrestrial celestial body can be obtained; and data support is provided for distribution exploration of extraterrestrial celestial body resources.

Resonant Spectral Selectors (RSS), configurations, components, and arrangements for selective radiative transmutation (n,g) and fission (n,f) in nuclide-target holders (69), useful for decontamination of radioactive waste, burning of fission products, production of radioisotopes and neutron activation analysis. RSS consists of support (58,59), peripheral reflector (10), primary source (20), pre-moderator (15), dynamic modulators (13,24-30) with magnetic suspension (28-30), peripheral compartment (11), target-holder (69), heating (53) and cooling systems (65), and pressure control (64), ion generation (51), instrumentation (71), neutron source (20), permanent magnet motors (54,55) and rotation sensors (17,18). RSS produces optimized rates of fission and radioactive capture reactions in nuclides with Z from 1 to 110, achieved through selective interactions in the cross-sections XS(n,g) or XS(n,f) exhibiting a 1 / v behavior at ~1meV or in resonances ranging from ~10-3 to ~105 eV. This is accomplished by a spectra of collective neutron distributions with precise mean energies and restricted standard deviations.

This invention relates to the field of automatic control design technology, and in particular to a control system for a neutron activation analyzer. The technical solution includes a control core module, an electrical isolation module, a power supply module, a communication module, an auxiliary protection module, a host computer module, and a database module. The electrical isolation module includes digital isolation units and analog isolation units. The digital isolation units are used to achieve electrical isolation and conversion between control signals and load signals based on a physical disconnect structure. This invention avoids the impact of voltage spikes and surge currents, protects the PLC module, and improves system stability. It integrates the PLC core control architecture, host computer, and database to achieve integrated management and control of peripheral devices and full-process acquisition, storage, and traceability of operational data. It is equipped with auxiliary protection and maintenance units to ensure safe equipment operation, while simplifying operation and deployment and adapting to on-site testing needs.

The utility model relates to the technical field of sample detection, particularly provides a sample element component detection system based on neutron activation analysis, and aims to solve the problem that the detection precision is influenced by low signal-to-interference ratio in a signal acquisition process in an existing element component detection mode. In order to achieve the purpose, the detection system comprises a neutron source used for generating a neutron beam; the gamma detector is provided with a detection probe, and the gamma detector is located in front of the emission port of the neutron source, so that characteristic gamma rays generated after the neutron beam bombards the sample to be detected can be incident to the detection probe, and therefore a gamma energy spectrum is formed; the shielding device comprises a first shielding layer surrounding the outer side of the detection probe, the first shielding layer is used for absorbing secondary gamma rays and environmental background gamma rays around the detection probe, and a collimation channel allowing characteristic gamma rays to enter is reserved in the shielding device. According to the invention, the signal-to-interference ratio in the sampling process can be improved, and the accuracy and reliability of the detection result are improved.

This invention relates to the field of transient gamma neutron activation analysis and non-destructive testing technology for industrial materials, and particularly to a multi-element gamma spectral quantitative inversion algorithm based on polynomial forward modeling and Newton's iteration. The technical solution includes the following steps: acquiring the gamma spectrum obtained from neutron activation measurement, extracting gamma detection feature values ​​corresponding one-to-one with each element; establishing a primary polynomial forward model based on the primary gamma detection feature values ​​and the true mass fraction of the corresponding element; and establishing a primary direct polynomial inverse model based on the gamma detection feature values ​​and the true mass fraction of the element. This invention effectively improves the accuracy of multi-element gamma spectral quantitative inversion, enhances the robustness and convergence stability of the algorithm under complex materials, improves the model's generalization ability to different matrix environments, and possesses good engineering practicality.

Method for analyzing a specimen by neutron activation. This method comprises: - activating (110) several samples of the specimen using, for each sample, a traversed thickness of moderator material different from the traversed thickness used to activate the other samples, and - for each activated sample, establishing (132) a Ni(R) concentration of a radioisotope of the component sought in that activated sample using only the ionizing radiation measured from that sample, where the exponent i is an identifier of the traversed thickness used to activate that sample and R is an identifier of the radioisotope of the component sought.then - the determination (134) of an Nc(C) concentration of the target component in the specimen from the various established Ni(R) concentrations and predetermined fluences of thermal neutrons and fast neutrons for each of the thicknesses of the moderator material used to activate the samples. Fig. 4,

The present application relates to the technical field of prompt gamma neutron activation analysis and non-destructive testing of industrial materials, and particularly relates to a multi-element gamma spectrum quantitative inversion algorithm based on polynomial forward and Newton iteration. The technical scheme comprises the following steps: obtaining a gamma spectrum obtained by neutron activation measurement, and extracting a plurality of gamma detection characteristic values corresponding to a plurality of elements; based on the plurality of gamma detection characteristic values and the true mass fraction of the corresponding sample elements, a polynomial forward model is established, and based on the gamma detection characteristic values and the true mass fraction of the elements, a direct polynomial inverse model is established. The present application effectively improves the accuracy of multi-element gamma spectrum quantitative inversion, enhances the robustness and convergence stability of the algorithm under complex materials, improves the generalization ability of the model to different matrix environments, and has good engineering practicability.

A mobile picking system for picking waste bulk material, comprising a measurement system to perform a chemical characterization of the material, wherein said measurement system is based on the Neutron Activation Analysis (NAA) technique, and in that said mobile picking system comprises a mobile crane with a clamshell bucket able to open the shells and pick the selected bulk material. Said mobile picking system is configured to instantly analyze, classify and then move the waste to an appropriate storage location / area.

The invention discloses an energy spectrum peak position linear compensation method, which comprises the following steps of: receiving a ray signal generated by a standard sample by using a detector, converting a detector pulse into a trapezoidal forming pulse, converting the amplitude of the trapezoidal forming pulse into a channel address, and forming original energy spectrum data of the standard sample; calculating a linear relation of energy spectrum peak positions according to the original energy spectrum data of the standard sample to obtain a slope and an intercept in a linear relation function; and adjusting the conversion parameter from the detector pulse to the trapezoidal shaping pulse through the corresponding relation between the slope and the intercept and the gain and the baseline value of the trapezoidal shaping pulse, thereby changing the actual value of the channel address corresponding to the detector pulse, and obtaining the energy spectrum data after linear compensation. According to the energy spectrum peak position linear compensation method disclosed by the invention, before neutron activation analysis spectrum unfolding, it can be ensured that the energy spectrum element peak position is consistent with the standard spectrum, and the energy spectrum analysis precision is improved.