161results about "Nuclear targets" 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.

An ion implantation system has a first linear accelerator for accelerating ions of an ion beam to a first energy along a beam path. A second linear accelerator positioned downstream of the first linear accelerator along the beam path accelerates the ions to a second energy. A charge stripper has a stripper tube with a passageway positioned between the first and second linear accelerators. A charge stripping medium is provided in the passageway to strip at least one electron from the ions as the ion beam passes through the charge stripping medium. A focusing apparatus is associated with the stripper tube to control a trajectory of the ions within the passageway of the stripper tube. The focusing apparatus can be two or more quadrupoles and include an electrostatic lens, a magnet, a solenoid, or a Einzel lens.

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 present disclosure relates to an accelerator lead-out window and a preparation method thereof, wherein an overall structure of the accelerator lead-out window is integrally formed by adopting an additive manufacturing method; a window film is made of titanium alloy, and each component ratio is calculated by a weight percentage, wherein Al:4.5-7.5%, Mo:4.1-6.9%, V:4.1-6.9%, Nb:3.1-4.5%, Cr 1.5-3.5%, Ta:0.5-1.5%, and the remaining amount is titanium and other unavoidable elements. A window frame is made of aluminum alloy, and each component ratio is calculated by a weight percentage, wherein Zn:5.1-6.9%, Mg:2.1-3.9%, Cu:1.2-3.9%, Cr:0.18-0.28%, Fe≤0.30%, Si≤0.15%, Ti≤0.15%, Mn≤0.10%, and the remaining amount is Al and other unavoidable elements.

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 quickly assemblable and disassemblable target part connecting structure for BNCT and a method therefor are provided. The target part connecting structure at least includes a target section, a pipeline section and at least one locking device configured to connect the target section and the pipeline section, where the locking device at least includes a lock body, a lock rod and a driving mechanism. The rapid connection and quick disassembly between the target section and the pipeline section can be achieved by driving the lock rod to telescopically move along an axial direction through the driving mechanism, the operation is simple, the assembly and disassembly efficiency is high, and the convenience of replacing the target section and maintaining a vacuum system in a BNCT system is improved.

An irradiation target for the production of radioisotopes comprises a plurality of plates having aligned central openings. First and second elongated central members extend in opposite directions through the aligned central openings of the plates. The first and second elongated central members each have a pair of wings at first and second ends of the plurality of plates, respectively. The first and second elongated central members further have a pair of tabs adjacent to the wings of the other elongated central member. Tabs of the first elongated central member are bent to engage one end face of the plurality of plates. Tabs of the second elongated central member are folded over the wings of the first elongated central member. The plates and the first and second elongated central members are formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.

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).

An irradiation target for the production of radioisotopes, having at least one plate defining a central opening, and a first elongated central member passing through the central opening of the at least one plate so that the at least one plate is retained thereon, wherein the at least one plate and the first elongated central member are both formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.

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 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.

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.

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.

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.

To provide a radioisotope manufacturing system capable of automatically loading a target substrate to a target device, the target substrate, and a target substrate holder.SOLUTION: The target substrate loader 110 places a target substrate 10X to be irradiated among the plurality of target substrates 10 on the target device 101. In this case, when the radiation to one target substrate 10 is completed, the radiation to the 10X portion of the next target substrate to be irradiated may be continuously performed. Therefore, it is possible to eliminate the need for an operator to replace the target substrate 10 each time the target substrate 10 is irradiated. In addition, even when a plurality of types of target substrates 10 are present, the target substrate loading device 110 can specify a target substrate 10 of a target type and perform irradiation.SELECTED DRAWING: Figure 1

To provide a radioactive nuclide production system and a radioactive nuclide production method which improve cooling performance of a target material including a material nuclide, suppress contamination of impurities to the target material, and are capable of efficiently producing a radioactive nuclide.SOLUTION: A radioactive nuclide production system 1 comprises: a particle beam irradiation device 10 which generates a particle beam 11; and a target 20 which generates radioactive nuclide by irradiation of the particle beam 11. In the target 20, a target material 21 including a material nuclide generating the radioactive nuclide is mounted on a target cooling plate 22 cooling the target material 21. In a radioactive nuclide production method, the target material 21 including the material nuclide forms the target 20 mounted on the target cooling plate 22 cooling the target material 21, and the target 20 is irradiated with the particle beam 11 or bremsstrahlung while cooling the target material 21 by the target cooling plate 22 to produce radioactive nuclide.SELECTED DRAWING: Figure 1

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.

The invention discloses a laser neutron yield increasing method based on a composite conversion target, which comprises the following steps of: arranging a plurality of elements to form the composite conversion target, bombarding the composite conversion target by using a deuterium ion beam obtained by interaction of laser and a heavy water liquid film target, and realizing neutron yield increasing through nuclear reaction section optimization; elements in the composite conversion target comprise at least two of T, D, < 7 > Li and < 9 > Be. According to the laser neutron yield increasing method based on the composite conversion target, the neutron yield and the average flux of a repetition frequency laser neutron source method are greatly increased, and the problem of instability in the continuous production process of a heavy water liquid film target is solved.

The present application relates to a gas target system (100) having: a body (110) having a frustoconical chamber; a cooling circuit having at least one channel surrounding at least a portion of the chamber; a window positioned facing the inlet of the chamber to enclose the chamber, the window having a thin plate that is transparent to at least a portion of the particle beam emitted by the particle accelerator and a support grid configured to withstand a pressure difference between an interior of the chamber and an exterior of the gas target system (100), the thin plate positioned between the support grid and the chamber (120); and a flange support (160) holding the window, sealingly secured to the body, having a mechanical fastening interface for fastening to an outlet of a particle accelerator (170).

The embodiment of the invention provides a method for determining the output beam intensity of a standing wave accelerating tube, and the method comprises the steps: building a target digital model corresponding to a target assembly, determining a simulated electron beam energy value according to a theoretical electron beam energy value emitted by the standing wave accelerating tube, and enabling simulated electrons to irradiate the target digital model according to the simulated electron beam energy value, calculating to obtain a first mapping relation between the unit X-ray dose rate of the first position and the simulated electron beam energy value; acquiring an actual electron beam energy value emitted by the standing wave accelerating tube and measuring an actual X-ray dose rate of the second position; and obtaining an actual unit X-ray dose rate according to the actual electron beam energy value and the first mapping relation, and calculating the ratio of the actual X-ray dose rate to the actual unit X-ray dose rate to obtain the beam intensity. According to the determination method in the embodiment of the invention, the influence of the material and structural characteristics of the target assembly on the X-ray dose rate is considered, the calculation precision of the beam intensity is improved, and a more accurate reference basis is provided for the design and debugging of the standing wave accelerating tube.

Passivation regions and device configurations are described herein. The passivation regions can be configured to seal against diffusion of an objective material from an underlying region into and / or through the passivation region. The passivation regions can also be configured to seal against diffusion of an externally sourced or ambient substance into and / or through the passivation region towards the underlying region.