77 results about "Neutron source" patented technology

The invention belongs to the technical field of nuclear power plant subcritical degree determination, and particularly relates to a method for determining a subcritical degree by adopting a spatial effect of an external neutron source. Comprising the following steps: 1, obtaining a curve of the ratio of the subcritical degree to near-source and passive neutron detector signals through theoretical calculation; 2, obtaining measurement values of four source range neutron detectors and four intermediate range neutron detectors; 3, calculating a near-source and passive ratio; and 4, according to the ratio calculated in the step 3, searching a ratio curve of the subcritical degree and the signals of the near-source and passive neutron detectors so as to obtain the reactivity of the reactor core. The method has the beneficial effect that the subcritical degree cannot be obtained by directly measuring through an instrument when the power level of the reactor is lower. According to the method, the subcriticality can be quickly obtained in a chart form through the ratio of the near-source neutron detector signals to the passive neutron detector signals or the ratio of the passive neutron detector signals to the near-source neutron detector signals.

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.

The present application relates to the technical field of neutron source, and particularly provides a high-heat-carrying neutron target system, which aims to solve the problem of poor heat dissipation capacity of the neutron target system. To this end, the high-heat-carrying neutron target system comprises a base and a jet cylinder, the base comprises a first end portion and a second end portion; the jet cylinder is wrapped on the outer side of the base; and the high-heat-carrying neutron target system further comprises a turbulence structure, the turbulence structure comprises a first heat dissipation structure and a second heat dissipation structure for flowing cooling medium, the first heat dissipation structure is arranged on the base and penetrates through the base in the direction from the first end portion to the second end portion; and the second heat dissipation structure is arranged on the jet cylinder, the second heat dissipation structure is communicated with the first heat dissipation structure, and the cooling medium in the second heat dissipation structure flows into the first heat dissipation structure in a preset direction to form turbulence for the cooling medium in the first heat dissipation structure. In the present application, the second heat dissipation structure is used to effectively increase the turbulence degree of the cooling medium in the first heat dissipation structure, thereby greatly improving the heat exchange effect of the neutron target system.

The invention relates to the technical field of nondestructive testing of element content and uniformity of fuel elements, and provides a fuel element detection method and system based on neutron imaging and activation analysis. The detection method comprises the following steps: S1, installing a to-be-detected sample, and adjusting an imaging collimation hole to be aligned with a neutron beam current of a neutron source; s2, the thermal neutrons are collimated by the imaging collimation hole and then transmit the to-be-detected sample, and spatial distribution of uranium and poison elements of the to-be-detected sample is obtained through detection of a neutron imaging detector; s3, selecting a specific target area, switching the activation analysis collimation hole to align to a neutron beam of the neutron source, and adjusting the position of the to-be-detected sample, so that the specific target area aligns to the neutron beam of the neutron source; thermal neutrons bombard a specific target area after being collimated by the activation collimation hole, and are received by the gamma ray detector so as to analyze and obtain the element content of the specific target area. According to the method, distribution and content of uranium and toxic elements in the fuel element can be rapidly and accurately determined on the premise of nondestructive testing.

The invention discloses a neutron source assembly which comprises a neutron source rod body, a lower end plug, a composite upper end plug and a guide cylinder, and the neutron source rod body comprises a neutron source rod end plug, a neutron source rod cladding tube, an upper reflecting layer, a lower reflecting layer, a source box and a matched end plug. The neutron source assembly adopts the rod-in-rod design, the possibility of abrasion of the neutron source rod body in the transportation process and the like can be reduced, the neutron source leakage risk is reduced, the counterweight design of the composite upper end plug can counteract the buoyancy of a coolant in a reactor, and it is ensured that the neutron source assembly smoothly falls to the bottom and keeps stable; the neutron source rod body can be used in a pressurized water reactor and can also be used in a liquid heavy metal reactor. Meanwhile, the sealing packaging structure of the neutron source rod body can reduce the risk of neutron source leakage caused by abrasion in the transportation and in-reactor operation process, the arrangement of the guide cylinder provides guidance for the assembly of the neutron source rod body, and the probability of collision damage of the neutron source rod body in the assembly process is reduced.

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 invention discloses a high-thermal-conductivity solid target, which belongs to the technical field of accelerator neutron sources and comprises an insulating PEEK base and an integrated solid target. The integrated solid target is arranged on the insulating PEEK base, and a target body of the integrated solid target is tightly attached and fixed to the insulating PEEK base; a circular positioning groove is formed in the insulation PEEK base and used for fixing the initial position of the integrated solid target, a sealing ring clamping groove is formed in the circular positioning groove, and two water cooling channels are arranged in a base body below the positioning groove in a penetrating mode. The back of the target body of the integrated solid target is integrated with a plurality of groups of radiating fins and an inverted-cone-shaped groove right facing a deuterium beam, so that an efficient radiating channel is formed. According to the high-thermal-conductivity solid target, by arranging the inverted-cone-shaped grooves and the cooling fins, the heat exchange area of beams can be increased, the structural stability of the high-thermal-conductivity solid target can be enhanced, the thermal stress level can be reduced, and the structural integrity and long-term working reliability of the target material can be guaranteed.

The application discloses a mechanical arm for installing a radioactive source of a radioactive logging instrument, and relates to the technical field of low-carbon oil exploitation. The mechanical arm comprises a positioning base plate and a mechanical arm body fixed to the positioning base plate. An installation frame is rotationally connected to the mechanical arm body. The installation frame is provided with circumferentially distributed outlets. Part of the outlets are sealed by sealing blocks. The other part of the outlets is threadedly connected with installation rods. The installation rods are slidably connected with connecting rods. The installation frame, the installation rods and the connecting rods are all provided with cavities in communication. The outer ends of part of the connecting rods are provided with slip type grippers. The mechanical arm can automatically complete all processes from loosening a hexagonal nut, opening a can cover, clamping a neutron source, placing the neutron source into a storage body, closing a storage cover and tightening the nut, without manual intervention, frequent replacement or adjustment of tools, so that operation complexity is reduced, work efficiency is remarkably improved, and radiation exposure risk is reduced.

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.

Neutron shielding. The neutron shielding comprises a first section comprising a first neutron absorbing material comprising tantalum, and a second section comprising a second neutron absorbing material, wherein the second neutron absorbing material substantially lacks tantalum. In use, the first section is between a neutron source and the second section.

The embodiment of the invention provides a neutron source emissivity valuing device and a neutron source emissivity measuring method. The neutron source emissivity valuing device comprises a solution pool, a measuring chamber, a circulating pipeline, a shielding body and a detector. The solution tank is provided with a first accommodating cavity for accommodating an activating solution and a second accommodating cavity for accommodating a neutron radioactive source; the measuring chamber is provided with a third accommodating cavity and a measuring cavity; the shielding body is provided with a fourth accommodating cavity for accommodating the measuring chamber and a communication channel communicated with the outside, and the communication channel is communicated with the measuring cavity; the detector is arranged in the communication channel, and one end of the detector extends into the measuring cavity. According to the neutron source emissivity valuing device, the detector in the measurement chamber can be taken out through the communication channel, so that on one hand, the detector is simpler and more convenient to disassemble and assemble; on the other hand, the detector can be independently packaged and stored, and collision damage of the detector is effectively prevented.

The invention discloses a solid neutron source device with potential diversion and magnetic field screening functions and a control method. The device comprises an ion generation structure, a potential diversion structure, a magnetic field screening structure, a neutron target and an insulating shell, the ion generation structure generates mixed ions under the action of the outside, the mixed ions form regular beams under the action of the potential diversion structure and enter the magnetic field screening structure, and due to the fact that different ions show different motion characteristics in a magnetic field, screening is carried out through an insulation pole plate with long rectangular holes. And finally, ion receiving and neutron excitation are completed under the action of strong potential carried by the neutron target. According to the invention, the loss caused by ion generation is effectively controlled through a potential diversion structure, and the utilization efficiency of ions and the neutron yield are improved by adopting a control method that the potential is continuously adjustable. Meanwhile, through a magnetic field screening structure, effective separation and screening of mixed ions are achieved, a control method with a continuously adjustable magnetic field is adopted, the screening range is wide, and the service life of a neutron source is prolonged.

The application discloses a test device for a converter valve of a hybrid commutation converter, which comprises a high-energy neutron source, a temperature adjusting box, a test host computer, a direct-current voltage source and a control protection circuit; the tested converter valve comprises a plurality of integrated gate commutation thyristors, a test rack is arranged in the temperature adjusting box, and a plurality of non-packaged integrated gate commutation thyristor (IGCT) wafers are arranged on the test rack in sequence; the high-energy neutron source is used for emitting rays to pass through the plurality of IGCT wafers on the test rack; each IGCT wafer corresponds to a control protection circuit, the control protection circuit is used for overvoltage or overcurrent protection of the IGCT wafer, and the control protection circuit at least comprises a protection resistor which is connected in series with the IGCT wafer and then connected between the positive electrode and the negative electrode of the direct-current voltage source; and the test host computer is connected with the control protection circuit and the direct-current voltage source. The test device can simultaneously test a plurality of IGCTs, improves the efficiency, and can repeatedly test, thereby saving the test cost.

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 invention provides a liquid scintillator neutron spectrometer calibration method and system based on a wide-energy-region neutron source, and relates to the technical field of neutron spectrometer calibration algorithms. In order to solve the problems that in the prior art, a large accelerator or a flight time device is relied on, rapid implementation cannot be achieved on site, and a response matrix is inaccurate due to the difference between a laboratory environment and a site condition, an on-site gamma radioactive source is adopted to complete energy calibration, and an on-site wide-energy-spectrum neutron source is adopted to obtain an actual measurement recoil proton spectrum; an ideal recoil proton spectrum is obtained in combination with Monte Carlo simulation, a proton photoresponse and energy resolution parameterized model is constructed, and on-site rapid solving of a response matrix is achieved through an iterative inversion algorithm. The method gets rid of dependence on large fixed facilities, the cost and time are reduced, the obtained response matrix directly contains the comprehensive influence of the field environment, the accuracy and field adaptability of neutron spectrum measurement are remarkably improved, and the method is automatic in process, high in efficiency and convenient to deploy.

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 present disclosure provides a detector, a passive neutron source imaging system and method. Wherein the detector can be applied to passive neutron source imaging, including a plurality of detection unit modules, each detection unit module including a plurality of scintillation crystal units, wherein the plurality of scintillation crystal units include N absorber units and M moderator units. By integrating the neutron deposition energy of each absorber unit in the N absorber units and integrating the neutron deposition energy of each moderator unit in the M moderator units, the total value of the deposition energy of the plurality of scintillation crystal units is obtained to determine the neutron deposition energy distribution of each detection unit module, thereby realizing the positioning imaging of the neutron source in 4π range, not only having high detection efficiency for neutron rays, but also having a wide neutron energy detection range, and realizing the accurate positioning of the radioactive source in 4π space.

The invention relates to an isotope neutron source reference radiation device based on pneumatic transmission, and a radioactive source exchange assembly comprises a radioactive source rotating disc which is in a disc shape, is uniformly provided with a plurality of neutron source storage positions along the circumferential line, and rotates to replace a to-be-detected neutron source; one end of the radioactive source pneumatic transmission pipeline is aligned with the storage position of the to-be-detected neutron source on the radioactive source turntable, and the other end is connected with the irradiation device; the radioactive source pneumatic transmission pipeline is perpendicular to the ground; the pneumatic transmission gas inlet pipeline is arranged below the storage position of the to-be-detected neutron source on the radioactive source turntable, one end of the pneumatic transmission gas inlet pipeline is aligned with the storage position of the to-be-detected neutron source on the radioactive source turntable, and high-pressure gas is introduced into the other end of the pneumatic transmission gas inlet pipeline. The device achieves the purposes of storing a plurality of neutron sources based on the radioactive source turntable, rotating and replacing different neutron sources to align with the radioactive source pneumatic transmission pipeline, and pushing the to-be-detected neutron source through the high-pressure gas, thereby achieving the technical effects that the plurality of neutron sources can be placed in the device, and the pushing speed of the high-pressure gas is relatively high.

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.

The invention relates to the technical field of neutron radiation measurement, discloses a neutron nondestructive testing wide-spectrum moderation device for a laser neutron source and a detection method, and adopts a three-in-one design idea of material function compounding, space structure nesting and energy step matching. An integrated structure formed by concentrically nesting an inner layer, a middle layer and an outer layer in sequence from inside to outside is adopted; the inner layer adopts a high-Z inelastic moderator, the middle layer adopts a low-absorption elastic moderator layer, and the outer layer adopts a thermalization and mechanical constraint shell; through physical combination and space structure optimization of a high atomic number material and a low atomic number material, step-by-step, collaborative and stepped efficient moderation of the neutron spectrum in the laser white light is realized. An integrated moderation structure formed by sequentially and concentrically nesting a high atomic number inelastic moderation layer, a low-absorption elastic moderation layer and a thermalization restraint layer from inside to outside is adopted, and step-by-step, collaborative and stepped efficient moderation and regulation and control of the wide energy spectrum of the laser white light neutron source are achieved.

The utility model relates to the technical field of hash neutron sources, in particular to a chopping plate connecting structure and an assembling tool thereof, and the chopping plate connecting structure comprises a chopping plate, a shaft hub and a tolerance compensation ring, a connecting hole is formed in the center of the chopping disc, a shaft hub is arranged in the connecting hole, and the shaft hub is used for being connected with a rotating shaft; a tolerance compensation ring is arranged between the outer wall of the shaft hub and the inner wall of the connecting hole and used for compensating a gap between the shaft hub and the connecting hole. According to the chopping disc connecting structure, the tolerance compensation ring is arranged, so that loosening between the chopping disc and the shaft hub at a high rotating speed can be prevented, vibration impact is reduced, and the chopping disc can be suitable for a higher rotating speed. The utility model further provides an assembly tool used when the chopping disc connecting structure is assembled, so that the assembly precision of the chopping disc connecting structure is ensured, and the assembly efficiency can also be ensured.

The invention relates to the technical field of space positioning, in particular to a neutron radiation source positioning method based on a sensor array. The method comprises the following steps: acquiring array geometric data and scene structure data; background sub-field measurement is carried out according to the array geometric data and the scene structure data to obtain background sub-field data; performing target monitoring according to the array geometric data and the background sub-field data to obtain target monitoring data; performing neutron feature map construction according to the target monitoring data to obtain neutron feature map data; and performing neutron source position inversion according to the neutron feature map data to obtain neutron source position data. According to the invention, the method can achieve the positioning of the neutron radiation source in a structural scene with shielding, reflection and multi-path propagation, and effectively improves the recognition capability of weak signal interference and the robustness of space matching. Through a source position network model combining array geometry, structure visibility and time sequence characteristics, radiation source positioning reliability in a semi-closed environment is enhanced.

The invention discloses a neutron beam dynamic regulation and control method and system in a BNCT process, and the method comprises the following steps: constructing a neutron beam-out regulation and control model, and obtaining a mapping relation between the intensity of a neutron beam and a neutron dose rate; dynamically monitoring the boron concentration of the tumor tissue and the boron concentration of the normal tissue to obtain a real-time T / N value; converting the T / N value into neutron beam intensity in real time, and substituting the neutron beam intensity into the neutron beam output regulation and control model to obtain a real-time neutron dose rate; comparing the obtained real-time neutron dose rate with a preset neutron dose rate, and if there is a difference between the real-time neutron dose rate and the preset neutron dose rate, adjusting neutron source parameters until the real-time neutron dose rate is consistent with the preset neutron dose rate; and the step S2 to the step S4 are repeated, and neutron beam dynamic regulation and control in the BNCT process are achieved. According to the invention, the technical problem that the neutron outgoing beam regulation and control precision and efficiency are low due to the fact that the real-time change of the boron concentration is not considered in the prior art can be solved.

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.

The invention discloses a neutron source inversion measurement verification tool, and relates to the technical field of neutron source inversion measurement, the neutron source inversion measurement verification tool comprises a servo motor and a neutron source mounting seat, the output end of the servo motor is provided with a rotating shaft, and the end part of the rotating shaft is provided with a major planetary gear; steering assemblies used for assisting steering are installed on the two sides of the outer surface of the large planetary gear correspondingly, each steering assembly comprises an auxiliary disc, a connecting shaft and a small planetary gear, the connecting shaft is arranged on one side of the small planetary gear, the auxiliary disc is installed at the end of the connecting shaft, and a first connecting disc is arranged on the outer surface of the auxiliary disc; connecting frames are annularly distributed on the outer surface of the first connecting disc. According to the neutron source inversion measurement verification tool, through rotation of the lead screw, the sliding seat in threaded connection with the lead screw can be driven to move relative to the horizontal position of the adjusting frame, and the built-in frame connected with the sliding seat moves along with the lead screw, so that position adjustment can be performed again, and multi-dimensional, multi-position and different-number adjustment of detectors and neutron source mounting seats is facilitated.

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.