24 results about "Neutron source" patented technology

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 application discloses a GAN neural network multiple distortion suppression model based on a coordinate attention mechanism, obtains an original neutron radiographic image from a neutron source; proposes a brand-new neutron radiographic image degradation model; adds Gaussian blur, Gaussian noise, Poisson noise and noise obeying gamma distribution to the clear neutron radiographic image; uses real white spot noise to train the GAN neural network, simulates white spot noise and randomly adds the white spot noise to the clear neutron radiographic image; constructs a multiple distortion suppression model of the GAN neural network based on the coordinate attention mechanism; uses Huber loss to train the constructed GAN neural network based on the coordinate attention mechanism; inputs a real neutron radiographic image containing multiple distortions into the trained multiple distortion suppression model as input, predicts the original image of the real neutron radiographic image containing multiple distortions, and obtains a target result.

Maintainability is to be improved. A radio frequency quadrupole linear accelerator includes a tubular housing part having an outer peripheral surface at which two pairs of openings extending in an axial direction are formed facing each other, and a plurality of first vane electrodes inserted into the respective openings of the tubular housing part from outside toward an axial center, detachably attached to the openings, and disposed facing each other.

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 present application relates to a kind of neutron magnetic focusing device control system, system includes front-end sensing unit, for the angle of neutron magnetic focusing device, temperature and so on Data acquisition;Core control unit, based on the data of front-end sensing unit acquisition realizes motor and neutron source T0 Signal synchronous control and temperature protection;Feedback compensation unit, real-time feedback equipment state and dynamically compensates phase deviation;Man-machine interaction unit, support local and remote dual-mode control;Through the collaborative work of multiple units, system can realize high-precision synchronous control, real-time state monitoring and fault alarm, effectively improve the operation stability and efficiency of neutron magnetic focusing device, provide reliable technical support for neutron scattering experiment.

This invention discloses a neutron-gamma dual-mode synchronous imaging method and system based on single-pixel detection, belonging to the field of nuclear imaging technology. The method includes: irradiating the sample under test with modulated neutron beams of different encoding modes, identifying the neutron event count and gamma-ray energy spectrum for each irradiation; dividing the sample under test into several pixel units, reconstructing a neutron transmission structure image based on the neutron event count for each irradiation; obtaining the detection efficiency of the characteristic gamma rays received by each pixel unit of the sample under test, and constructing a gamma response modulation matrix in combination with the neutron transmission structure image; extracting the net count of the characteristic peaks of the target element from the gamma-ray energy spectrum, reconstructing an element distribution image in combination with the gamma response modulation matrix, and fusing it with the neutron transmission structure image for output. This invention achieves synchronous acquisition of structural and elemental information, automatic spatial registration, and joint high-precision reconstruction, and is particularly suitable for the engineering application of miniaturized neutron sources.

The present application relates to the technical fields of nuclear fusion research and neutron source, and particularly relates to a poloidal magnetic field plasma focus device, which comprises a vacuum tube, a coaxial electrode assembly and a poloidal magnetic field generating assembly, the coaxial electrode assembly and the poloidal magnetic field generating assembly are arranged in the vacuum tube; the poloidal magnetic field generating assembly comprises a plurality of bar magnets, each of the bar magnets is distributed in a circumferential array around an axis of the vacuum tube, and each of the bar magnets is arranged at an outer periphery of the coaxial electrode assembly, the magnetization directions of adjacent bar magnets are opposite, so that the N poles of the bar magnets and the S poles of the bar magnets are arranged alternately along the circumference, thereby forming a poloidal magnetic field in a discharge region of the coaxial electrode assembly, and the technical problem of low energy utilization efficiency caused by large parasitic inductance of a discharge loop of a traditional plasma focus device is solved.

The utility model belongs to the field of reactor, concretely relates to a kind of space reactor neutron source assembly and reactor system. Wherein space reactor neutron source assembly includes linear moving mechanism and the neutron source rod body of linear moving mechanism output end being arranged, the neutron source rod body includes neutron source functional area, gap and cladding sequentially arranged from inside to outside;The neutron source functional area includes sequentially arranged heat transfer zone, fuel area I, partition area I, neutron source, partition area II and shutdown area. The space reactor neutron source assembly provided by the utility model better utilizes the important position of reactor core center. It can move up and down on the core center, and the structure is simple and compact, efficiently realizes the functions of fuel auxiliary combustion, neutron source start-up, shutdown and reactivity adjustment.

Neutron shielding. The neutron shielding (600) comprises first (601) and second (602) sections, each comprising boron. The neutron shielding is configured such that in use the first section is between a neutron source (620) and the second section. At least 75% of boron in the first section is boron-11, and at least 70% of boron in the second section is boron-10. Also provided are assemblies incorporating the neutron shielding, a method comprising providing and irradiating the neutron shielding, and a method of designing neutron shielding.

A direct fusion heat exchanger technology allows for the efficient transfer of fusion plasma heat energy to a working fluid for aerospace propulsion and other applications. Aspects of this disclosure also enable the generation of high neutron fluxes for applications like medical isotope production, materials testing, and neutron radiography. The use of a thin-film beam window array allows charged particles from a fusion plasma or accelerator to pass through and directly interact and heat the working fluid or fusion target. The thin-film beam window array offers advantages in efficiency, compactness, and safety compared to traditional fusion reactor designs. The technology also addresses the limitations of existing neutron sources by providing a simpler, cheaper, and more efficient method for generating high neutron fluxes.

The application discloses a nested full-ring quasi-ellipsoid focusing system based on a neutron super mirror and a design method, which comprises an object plane light source, a focusing mirror arranged on one side of the object plane light source, a sample diaphragm arranged on one side of the focusing mirror, a sample arranged in the sample diaphragm and an image plane detector arranged on one side of the sample diaphragm. The focusing mirror comprises a core shaft and a plurality of mirror surface assemblies uniformly fixed on a circle of the outer surface of the core shaft, and each mirror surface assembly is arranged at intervals. A boron carbide light shielding plate is arranged on the side of the focusing mirror close to the object plane light source, and the focusing mirror improves the signal-to-noise ratio of the system through the boron carbide light shielding plate. According to the application, high gain and high resolution are simultaneously realized, and the designed novel focusing system can meet the application requirement of a small-angle neutron scattering spectrometer of a small accelerator neutron source.

The application provides an integrated integrated logging instrument and a logging data acquisition method, and relates to the technical field of oil logging. The integrated integrated logging instrument comprises, in sequence, a motor eccentric, a common circuit section neutron source assembly, a pusher, a caliper assembly and a density sensor assembly, and the neutron source assembly, the pusher, the caliper assembly and the density sensor assembly are further electrically connected with the common circuit section; wherein the neutron signal processing unit of the neutron source assembly, the neutron receiving module of the neutron source assembly and the main processing unit composed of the coding unit of the neutron source assembly and the coding unit of the density sensor assembly are integrally arranged in the common circuit section. The integrated integrated logging instrument and the logging data acquisition method optimize the circuit layout of the logging instrument, shorten the length of the neutron source assembly and the density sensor assembly, and solve the problems of the overall length of the logging instrument being too long and poor reliability in the prior art.

This invention relates to the field of ion source technology and discloses a transmission system for a small negative high-voltage neutron source. The transmission system includes a transmission tube, a plasma electrode, an extraction electrode, a Helmholtz coil, and an aperture. The transmission tube has a vacuum channel, and the plasma electrode and the extraction electrode are located inside the vacuum channel, downstream of the plasma electrode in the beam transmission direction. The Helmholtz coil is located outside the transmission tube. This transmission system can overcome the technical problem of how to achieve 100 mA beam transmission and beam homogenization within a limited structural size for a small negative high-voltage neutron source. The Helmholtz coil and aperture can effectively suppress the space charge effect of the ion source, enhance the beam transmission efficiency, and improve beam homogenization. Simultaneously, it can reduce the target surface heat load, improve neutron yield, and increase the target's service safety and lifespan.

This application relates to the field of neutron sources, specifically to a reactor core and reactor suitable for a neutron source, as well as a neutron source. The core includes multiple first fuel rods and multiple second fuel rods, a control rod assembly for controlling the reactivity of the core, a reactivity adjustment assembly, and a reflection assembly. The multiple first fuel rods and multiple second fuel rods are arranged in a rectangular matrix, with each second fuel rod positioned on either side of the multiple first fuel rods along the width of the rectangular matrix. The enrichment of the second fuel rods is higher than that of the first fuel rods. The control rod assembly is configured to increase the intensity of the neutron beam emitted along the width of the rectangular matrix. The reactivity adjustment assembly is used to adjust for changes in reactivity caused by fuel depletion. The reflection assembly is configured to reflect neutrons to increase the intensity of the neutron beam emitted along the width of the rectangular matrix. The core provided by the embodiments of this application can increase the intensity of the emitted neutron beam.

The utility model belongs to nuclear radiation technical field, specifically discloses a kind of neutron source transmission gas path structure, including the vertically arranged transmission pipeline and be located in the neutron source cup of transmission pipeline, neutron source cup is used to place neutron source;The lower end of transmission pipeline is equipped with sealing plate, transmission pipeline lower end is vertically equipped with gas tube, and total air inlet is set in the center of sealing plate, to communicate gas tube and transmission pipeline;Gas tube includes outer gas tube and the inner gas tube of being located in outer gas tube, and the inner gas tube axis, outer gas tube axis and total air inlet vertical center line are collinear, and the upper end of inner gas tube and outer gas tube is flush with the top surface of sealing plate;First air inlet is equipped in the lower end of inner gas tube, and first air inlet is connected with first air pipe line, and the through-hole for first air pipe line is equipped on outer gas tube;Second air inlet is equipped in the lower end of outer gas tube, and second air inlet is connected with second air pipe line.The utility model can improve the stability in the process of neutron source lifting, avoid that neutron source cup and transmission pipeline rub.

The application relates to the technical field of composite targets, and discloses a composite breeding target system for BNCT, which comprises a Be-Li composite target and a primary breeding system, the primary breeding system is located at the back of the Be-Li composite target, and the two form a composite target structure, wherein the primary breeding system comprises a uranium layer and an aluminum substrate layer, the uranium layer is attached to the aluminum substrate layer, the output efficiency and quality of neutrons can be effectively improved through optimization of a neutron generation and breeding process, thereby providing a more efficient neutron source for BNCT, the composite breeding target system for BNCT can improve the neutron yield after proton targeting, and can also make the neutron energy generated by the Li layer consistent with the neutron energy generated by the Be layer.

The application discloses a kind of detector neutron source test system and test method thereof, it is related to detector neutron source test auxiliary system technical field, including safety detection module before test: for automatically detecting the assembly, debugging and installation sealing of equipment Whether it meets the test standard, check shielding protection performance simultaneously, ensure that the radiation dose meets safety standards, and the detected data is sent to subsequent module and is discriminated processing.It is a kind of detector neutron source test system and test method thereof, by the real-time environmental safety monitoring discrimination module of being set, so that the test system can automatically monitor the various environmental values of the space environment of experimental personnel in real time when equipment is pre-tested and formally tested, to ensure that when the values in the environment appear abnormal trend, can timely send alarm to remind experimental personnel and through the cooperation of secondary protection control module to automatically enable secondary shielding mechanism, greatly improve the safety of experimental personnel when testing.

The application provides a reactor core arrangement method and a reactor pressure device, and the arrangement method is a reactor core arrangement method without a secondary neutron source, and specifically comprises the following steps: loading fuel assemblies and corresponding primary neutron sources in a first cycle core of a reactor; disassembling the primary neutron sources from the irradiated fuel assemblies in the first cycle core, and loading the primary neutron sources into first spent fuel assemblies to form a second cycle core start-up neutron source; disassembling the primary neutron sources from the irradiated fuel assemblies in the second cycle core, and loading the primary neutron sources into second spent fuel assemblies to form a third cycle core start-up neutron source; and disassembling the primary neutron sources from the irradiated fuel assemblies in the third cycle core, and performing a subsequent cycle of the core. The application realizes the purpose of improving the utilization rate of the primary neutron source of the reactor and canceling the setting of the secondary neutron source by reusing the primary neutron source in the first three cycles of the core and combining with the utilization of the neutrons emitted by the spent fuel assemblies in the previous cycle.

The application relates to the technical field of gamma spectrum analysis, and particularly provides a gamma detector activation analysis method and a PGNAA detection system, which aims to solve the technical problem that the gamma rays obtained by detecting the existing gamma detector include rays generated by the activation and decay of crystals in a neutron field, thereby causing the component detection result of a to-be-detected sample to be inaccurate. For this purpose, the gamma detector activation analysis method comprises the following steps: irradiating a to-be-detected sample by using a neutron source; repeatedly collecting multiple groups of gamma spectra of the to-be-detected sample by using a gamma detector; constructing a spectrum signal matrix based on the gamma spectra of the to-be-detected sample, wherein the spectrum signal matrix is a mixed signal composed of prompt gamma rays generated by the neutron activation of the to-be-detected sample, environmental background gamma rays and interference signals generated by the activation of crystals in the gamma detector; and obtaining effective prompt gamma rays based on the spectrum signal matrix. The self-interference influence of the detector is effectively reduced, and the evaluation precision of the target element content of the to-be-detected sample is improved.

The invention belongs to the technical field of nuclear reactor design, and particularly relates to a passive starting method for arranging a source range detector in a reactor reflecting layer. A source range detector is arranged in a reactor reflecting layer, and the source range detector arranged in the reactor reflecting layer monitors introduction of unexpected reactivity in real time in the whole process from reactor charging completion to critical starting, so that a reactor safely and effectively reaches a critical state. When a reactor is started in an initial state, a coolant is at normal temperature, all the control rods are inserted into a reactor core and the boron concentration is shutdown boron concentration, the detector obtains an effective counting rate signal not lower than 0.5 cps. According to the invention, by using the source range detector arranged in the reflecting layer of the reactor, non-blind area monitoring is realized in the whole starting process, and safe and efficient passive starting of the reactor is ensured. According to the invention, the dependence of the reactor starting on the external starting neutron source is avoided, the construction cost is reduced, and the generation of radioactive solid wastes related to the neutron source is eliminated.