181results about "Direct voltage accelerators" patented technology

The invention discloses a gas target device for isotope production, and the gas target device comprises a seat body which is provided with a channel; the water-cooled jacket body is mounted on the seat body, and the water-cooled jacket body is provided with a water-cooled cavity for circulating a water-cooled medium; the target body is installed on the base body and comprises a target body, the target body is located in the water cooling cavity and is provided with a target cavity, and the target cavity, the channel and the accelerator beam leading-out port are sequentially arranged in the set direction. According to the gas target device for isotope production disclosed by the embodiment of the invention, the water-cooled jacket body is arranged for cooling the target body, so that the target body is prevented from being damaged due to overhigh temperature of the target gas, the target gas can receive beam irradiation with higher flow intensity, and the isotope yield is improved.

The invention discloses a method for efficiently generating high-brightness gamma radiation, and belongs to the technical field of radiation. A relativistic electron beam is injected into the porous microstructure foam target material, and high-brightness gamma ray radiation is generated. According to the method, the used device is simple, only the single relativistic electron beam and the porous microstructure foam target material are needed to interact, compared with a traditional uniform-density solid material, the energy conversion efficiency in the interaction process of the electron beam and a substance can be remarkably improved, and the energy conversion efficiency can be remarkably improved through the effective constraint effect of a high-intensity magnetic field. And the problems of low energy conversion rate, low light source brightness, poor radiation directivity, complex device or difficulty in experiment implementation and the like of the existing high-energy gamma ray radiation source are solved.

The invention provides a rotating target for generating monoenergetic neutrons, which comprises a target chamber, a target sheet, a sealing flange and a vacuum system, the target sheet is composed of a TiD / TiT target material and a substrate, a deviation distance of 5-10mm exists between the center of the target material and the center of the substrate, the substrate is connected with a motor outside the target chamber through a fixed connecting rod, and the target chamber is driven by the motor to rotate at a speed of 3-5min / r. The target material is designed to be the eccentric target rotating slowly, so that the utilization rate of the target material can be improved, and the phenomena that the temperature of a single point is too high, a coating layer penetrates or falls off, enriched gas escapes and neutron yield fluctuation is caused due to the fact that beam bombards one position of the target material for a long time can be avoided. The energy width of neutrons generated by the rotating target is lower than 5%, the rotating target has good monochromaticity and low energy loss, the design precision requirement of the fourth-generation nuclear reactor can be met, and a possible guarantee is provided for commercialized popularization and application of the fourth-generation nuclear reactor.

A dual-radionuclide production target includes a first radionuclide target that produces a first radionuclide when irradiated by a particle beam from a radionuclide production system, and a second radionuclide target that produces a second radionuclide when irradiated by the particle beam that has passed through, and been degraded by, the first radionuclide target. With this design, the first radionuclide target serves two purposes: it reduces the beam energy to a suitable energy for isotope production on the second radionuclide target, and in-doing so becomes activated with a medically relevant radionuclide that can be easily extracted. In this way, in a single production run can produce two or more radionuclides.

The invention discloses a device for assisting installation and calibration of main parts of a serial accelerator, and relates to the technical field of installation and calibration, the device comprises a first base, the top of the first base is fixedly connected with a track, the top of the track is provided with a plurality of second bases, the tops of the second bases are provided with assembling assemblies, and the assembling assemblies are internally provided with accelerators. A first accelerating tube, a second accelerating tube, an adapter flange and a corrugated tube are arranged in the accelerator, and a driving assembly is arranged at the top of the second base; the assembly assembly includes a support ring. The first clamping plate and the second clamping plate can be attached to the outer wall of the accelerator all the time, the first clamping plate and the second clamping plate are connected and limited through the rubber plate, the rubber plate can be well attached to the outer wall of the accelerator in a deformation mode, and the effects of self-centering of the accelerating tube and convenient rotary installation are achieved; the problem that calibration is tedious due to the fact that a plurality of tools need to be used in cooperation is solved, and accelerator installation convenience is improved.

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.

Provided herein are high energy ion beam generator systems and methods that provide low cost, high performance, robust, consistent, uniform, low gas consumption and high current / high-moderate voltage generation of neutrons and protons. Such systems and methods find use for the commercial-scale generation of neutrons and protons for a wide variety of research, medical, security, and industrial processes.

A plasma focus system for neutron production is disclosed that includes an electrode assembly having an inner electrode extending along a pinch axis from a discharge end to a focus end, and an outer electrode surrounding the inner electrode to define a plasma channel for receiving a gas containing neutronic fusion fuel. The system also includes a power supply unit for applying a discharge driving signal to the electrodes, which causes the gas to be ionized into a plasma current sheath at the discharge end that flows along the plasma channel to reach the focus end where the sheath collapses toward the pinch axis to form a plasma pinch that generates fusion neutrons. The inner electrode has a tapered tip at the focus end that is configured to increase a speed of the sheath sufficiently to reach a pinch temperature at which the fusion neutrons are predominantly of thermonuclear origin.

An irradiation station for producing a radioisotope, having a cyclotron (32) for emitting a proton beam (B) against a solid target material (M) placed in a container (1) and a cooling system (33) for cooling the container (1). The container (1) has a wall (4) for supporting the solid target material (M) and a cavity (12), which borders the wall (4) and has an opening (14) transverse to the axis of the container (1). The cooling system (33) has a connection head (34) which is couplable to the opening (14) for circulating a cooling fluid in the cavity (12) and comprises a flow diverter (37), a tip (47) protruding from a hole (46) of the flow diverter (37) and movable along the hole (46) against the action of a spring (48) in contact with the tip (47), and an electrical connector (52) in contact with the spring (48). When the connection head (34) is coupled to the opening (14) the flow diverter (37) enters the cavity (12) coaxially with the container (1) and the tip (47) presses against the wall (4).

Systems, devices, and methods for converting a raw neutron beam to a specified deliverable format having a targeted energy range, size, and direction are described. Embodiments of a neutron beam converter can include numerous regions based on location, function, dimension, and / or constituent material. The regions can include a central region, an intermediate region, a peripheral region, and a frontal region. Materials are also described.

The present disclosure provides a neutron target device for boron neutron capture therapy, comprising: a container having a containing cavity; a neutron target component arranged in the containing cavity, the neutron target component comprising a target disc and a target sheet detachably connected with the target disc; a rotating component connected with the target disc for driving the neutron target component to rotate; a driving component connected with the rotating component for driving the rotating component to rotate; and a cooling component arranged at an end of the rotating component away from the neutron target component for supplying a cooling liquid; wherein the rotating component is provided with a liquid inlet cavity and a liquid outlet cavity, the target disc is provided with a liquid inlet flow channel and a liquid outlet flow channel, and the target sheet is provided with a liquid inlet hole and a liquid outlet hole; the liquid inlet flow channel is in communication with the liquid inlet cavity and the liquid inlet hole, and the liquid outlet flow channel is in communication with the liquid outlet cavity and the liquid outlet hole. The flow path structure of the neutron target device of the present disclosure is conducive to improving the cooling rate of the target sheet; and the target sheet is detachably connected with the target disc, which is conducive to the convenience of replacing the target sheet.

The present application relates to the technical field of isotope production equipment, and particularly relates to a target capsule facilitating replacement of target material and a target material replacement method. The target capsule comprises: a first shell provided with a first recess, the opening of the first recess being located at the first end face of the first shell; a second shell provided with a second recess, the opening of the second recess being located at the first end face of the second shell; and a target material for receiving bombardment of high-energy particles to generate isotopes; wherein the first shell is embedded in the second recess and is threadedly connected with the second shell, the target material is installed in the first recess, and the bottom wall of the second recess covers the opening of the first recess. In the present application, the sealing structure of the target capsule is optimized to be the first shell and the second shell connected through a threaded structure, so that workers can conveniently assemble, disassemble and replace the target material of the target capsule, the sealing structure can be repeatedly used, and the production efficiency of isotopes is improved.

The present disclosure relates to a low-stress thin film comprising a number of bilayers, wherein a bilayer comprises a first layer comprising M, and a second layer comprising X; and wherein at least one of the first layer and the second layer comprises at least one of 11B4C, 10B4C, B4C, 11B, 10B, B and C. The present disclosure 5 also relates to use and a method of producing said low-stress thin film.

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 invention discloses a method for realizing an ultra-compact self-moderation neutron generator. The ultra-compact self-moderation neutron generator comprises an ion source system, a vacuum system and a target system, according to the method, a high-voltage base is introduced into the ultra-compact self-moderation neutron generator, and the high-voltage base is fixedly connected with a target base of the target system. According to the ultra-compact self-moderation neutron generator, by introducing the high-pressure base made of the polyethylene material, on one hand, the device has the neutron moderation capacity, and the requirement of the outside for neutron moderation is lowered; on the other hand, the high-pressure base directly participates in vacuum sealing, so that the device is more compact The shielding layer structure plays a role in preventing neutrons from diffusing all around. The device has the advantages of small overall size, high integration level, high moderation efficiency, high neutron utilization rate and the like.

The invention relates to a nested high-voltage generator and a high-voltage generation method thereof. The nested high-voltage generator comprises an independent sub-power supply, a capacitor, an electrode plate and a conductive shell, the independent sub-power supply is connected in series with the electrode plate and connected in parallel with the capacitor to form a high-voltage generating circuit; the conductive shell surrounds the outer side of the high-voltage generating circuit to form a Faraday cage, and the independent sub power supply and the capacitor are arranged in the conductive shell; a plurality of Faraday cages exist, the plurality of Faraday cages are nested, and the Faraday cage nested in the inner layer is placed in the conductive shell nested in the Faraday cage nested in the outer layer; the independent sub-power supply of the nested inner layer is connected in series with the independent power supply of the nested outer layer, and the capacitor of the nested inner layer is connected in series with the capacitor of the nested outer layer. The nested high-voltage generating circuit is provided with a plurality of independent sub-power supplies, each independent sub-power supply can independently supply power, when any one of the independent sub-power supplies is damaged, the other high-voltage generating circuits can work independently, normal use is not affected, and the technical effect of reducing regular maintenance cost and repair cost of the high-voltage generator is achieved.

Provided herein are neutron imaging systems (e.g., radiography and tomography) systems and methods that provide, for example, high-quality, high throughput 2D and 3D fast or thermal neutron and / or X-ray images. Such systems and methods find use for the commercial-scale imaging of industrial components. In certain embodiments, provided herein are system comprising a plurality of independent neutron absorber-lined collimators (e.g., 4 or more collimators) extending outwards from a central neutron source assembly.

This invention discloses a gas target device for isotope production. The gas target device includes: a base having a channel; a water-cooled jacket mounted on the base, the water-cooled jacket having a water-cooled cavity for circulating a water-cooling medium; and a target body mounted on the base and including a target body located within the water-cooled cavity and having a target cavity. The target cavity, the channel, and the accelerator beam outlet are arranged sequentially along a predetermined direction. According to the gas target device for isotope production according to embodiments of this invention, by providing a water-cooled jacket for cooling the target body, damage to the target body caused by excessively high target gas temperature is avoided. Furthermore, the target gas can receive beam irradiation with a higher flow rate, thereby increasing isotope yield.

The invention provides a composite target material for producing astatine-211 through a cyclotron and an active cooling system of the composite target material, and relates to the technical field of radionuclide preparation. The composite target material comprises a working part and a connecting part which are integrally formed, the upper surface of the working part is provided with an inclined surface or a concave curved surface used for depositing a bismuth layer, and a plurality of liquid cooling runners communicated with one another are integrated in the connecting part; the active cooling system further comprises a supporting cooling base detachably connected with the composite target material, and the supporting cooling base and the composite target material jointly form a closed circulating cooling loop. The thermal load distribution can be optimized by changing the geometric configuration of the working surface, and the integrated liquid cooling and modular assembly and disassembly design is combined, so that efficient heat dissipation is realized, and meanwhile, rapid replacement of the target material is supported. According to the system, the anti-meltdown capability and the operation stability of the target material are remarkably improved, and the system is suitable for large-scale high-yield preparation of astatine-211.

A substrate processing device includes a plasma chamber, a power voltage source, a process chamber, a grid structure, and a reflector. The power voltage source is arranged in the plasma chamber for generating plasma. The process chamber defines a processing region for processing a substrate, and arranged below the plasma chamber. The grid structure is arranged between the process chamber and the plasma chamber for receiving the plasma and supplying ions or radicals to the substrate The reflector is for forming neutrons from the ions or the radicals and supplying the neutrons to the substrate.

The invention relates to an accelerator thermal neutron radiation field double-target beam automatic adjusting device and method, and the device is characterized in that a particle transmitting end is used for transmitting an ion beam; the particle receiving end is arranged on the emission axis of the ion beam; the particle receiving end comprises two semicircular beryllium targets and a tantalum target, the projections of the two semicircular beryllium targets form a complete circle on the ion beam emission axis, the tantalum target is arranged at the outermost side line of the two semicircular beryllium targets, and the area of the tantalum target is smaller than one third of the area of the two semicircular beryllium targets; and the xy guider is arranged between the particle transmitting end and the particle receiving end, a deflection electric field is arranged in the xy guider, and the xy guider is used for acquiring the quantity of ions received by the two semicircular beryllium targets and the quantity of ions received by the tantalum targets respectively, adjusting the electric field intensity of the deflection electric field based on the quantity of ions and changing the shooting direction of the ion beam. The technical effects that manual adjustment is not needed, the monitoring efficiency is improved, and meanwhile the experience degree needed by adjustment is reduced are achieved.

This invention belongs to the field of vacuum electronic device control technology, specifically relating to a closed-loop control method and system for the internal gas pressure of a neutron tube. The method includes the following steps: S1, constructing a multi-dimensional parameter synchronous acquisition and preprocessing link, establishing a high-frequency synchronous acquisition mechanism, and acquiring the real-time operating status parameters of the neutron tube system, including ion source current, anode high voltage, and tube temperature; S2, performing soft measurement of the actual gas pressure based on the Penning discharge equation, constructing a decoupled observer based on the real-time operating status parameters, eliminating the interference of anode high voltage fluctuations and tube temperature changes on the ion source current, and calculating the actual observed gas pressure value inside the neutron tube. This invention achieves rapid gas pressure response with no overshoot throughout, significantly reducing the risk of neutron tube high-voltage breakdown and ensuring consistent control across the entire temperature range.

Provided herein are neutron imaging systems (e.g., radiography and tomography) systems and methods that provide, for example, high-quality, high throughput 2D and 3D fast or thermal neutron and / or X-ray images. Such systems and methods find use for the commercial-scale imaging of industrial components. In certain embodiments, provided herein are system comprising a plurality of independent neutron absorber-lined collimators (e.g., 4 or more collimators) extending outwards from a central neutron source assembly.

The invention discloses a spallation neutron source reflector maintenance tool, and relates to the technical field of reflector maintenance tools, the spallation neutron source reflector maintenance tool comprises a ceramic anti-radiation shell, a cleaning assembly and an impurity collection box, and the top of the ceramic anti-radiation shell is symmetrically provided with driving motors. According to the maintenance tool for the spallation neutron source reflector, through the arranged electric telescopic rod, the electric telescopic rod can drive the auxiliary moving mechanism to ascend and descend along the outer surface of the ceramic anti-radiation shell during operation; when the height of the auxiliary moving mechanism is lower than the lowest end of the ceramic anti-radiation shell, the auxiliary moving mechanism can assist the ceramic anti-radiation shell to move, and when the ceramic anti-radiation shell completely covers the spallation neutron source reflector to be maintained, the electric telescopic rod is opened. The auxiliary moving mechanism moves upwards along the outer surface of the ceramic anti-radiation shell, and then through mutual cooperation of a fixing block, a fastening bolt and a hinge mechanism, the arc-shaped ceramic sealing door is conveniently and rapidly closed by a worker.

Reactor target assemblies are provided that can include a housing defining a perimeter of at least one volume and Np or Am spheres within the one volume. Reactor assemblies are provided that can include a reactor vessel and a bundle of target assemblies within the reactor vessel, at least one of the target assemblies comprising a housing defining a volume with Np or Am spheres being within the volume. Irradiation methods are also provided that can include irradiating Np or Am spheres within a nuclear reactor, then removing the irradiated spheres from the reactor and treating the irradiated spheres.

Disclosed is a neutron beam generation system for neutron capture therapy. According to an embodiment of the present disclosure, provided is a neutron beam generation system comprising: an injector which generates proton beams; an RF linear accelerator connected to the injector to accelerate the proton beams; a beamline which transmits the proton beams accelerated by the RF linear accelerator; a target which generates fast neutrons by colliding with the proton beams transmitted by the beamline; and a beam shaping assembly provided on one side of the beamline and configured to decelerate the fast neutrons into epithermal neutrons.

Systems and methods are provided for operating and constructing a neutron generator. In some examples, an ion source within a neutron generator may include a hot cathode; at least one cylindrical sleeve coupled to an exterior surface of the hot cathode; at least one electrode coupled to an interior surface of the neutron generator; and at least one mounting flange, wherein a proximal end of the at least one mounting flange is coupled to the at least one cylindrical sleeve and a distal end of the at least one mounting flange is coupled to the at least one electrode.

This application provides a high-acceptance gas charge stripper for a gas target, the main body of which is a vacuum differential structure. The stripping gas enters the stripping tube from the inlet pipe, and the charged particle beam achieves charge stripping through collision reactions as it passes through the stripping tube. Gas resistance tubes are installed at both ends of the stripping tube to restrict the stripping gas from entering the vacuum pipes at both ends of the vacuum chamber. The inner wall of the stripping tube has a variable aperture structure, with the aperture gradually increasing from the center to both ends, thereby achieving efficient charge exchange. The inner wall of the gas resistance tube also has a variable aperture structure, with the aperture gradually decreasing from inside the vacuum chamber to outside, thereby reducing the impact of the stripping gas on the vacuum level in the vacuum pipes on both sides. By setting the variable-diameter gas resistance tubes, the vacuum system can withstand a higher intake volume of stripping gas, allowing the aperture of the stripping tube to be designed to be larger, thus improving the beam acceptance of the gas charge stripper, increasing beam transmission efficiency, and ensuring the efficient and stable operation of the electrostatic tandem accelerator.