263results about "Nuclear targets" patented technology

The invention relates to the technical field of isotope production, in particular to a welding-free target capsule for isotope production and a manufacturing method of the welding-free target capsule. The welding-free target capsule comprises a target material used for generating isotopes under bombardment of high-energy particles; the first metal film covers one side of the target material; the second metal film covers the other side of the target material; wherein the first metal film and the second metal film are made of materials with ductility; the edge of the first metal film and the edge of the second metal film are attached to each other on the peripheral side of the target material and are folded into an annular sealing structure. In the invention, the metal film with good ductility is used as a coating material of the target material, and the sealing structure is formed by folding the connecting part of the metal film, so that the target capsule can be ensured to efficiently dissipate heat in a water-cooling environment, the manufacturing mode of the sealing structure can be improved, the manufacturing steps of the sealing structure are simple and easy to implement, and the manufacturing cost of the target capsule is further reduced.

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.

A radioisotope target station, including a target housing. The target housing includes a target material, and a target backing material. The radioisotope target station includes a loader mechanism comprising at least one jaw configured to secure the target housing, a loading position comprising a magazine, wherein the magazine is configured to hold two or more target housings, an irradiation position comprising a beam, where the beam is configured to irradiate the target housing orthogonally, a cooling fluid source fluidly coupled to the loader mechanism, where the cooling fluid source is configured to cool the target housing as the target housing is irradiated, and an ejection position comprising an ejector and an ejection chute, where the ejector is configured to detach the target housing from the loader mechanism and the ejection chute is configured to receive the target housing when detached.

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.

A radiation device comprises at least a vacuum chamber (1), an electromagnetic accelerator (8) for generating a primary energy beam of ions inside the vacuum chamber (1), and a layer of material (S) carried by a support (4) rotating in the vacuum chamber (1) to generate a flow of particles when a series of nuclear fusion reactions are triggered on the material (S) thanks to the energy of said beam, and wherein the support (4) is hollow and sealed defining a rotating three-dimensional surface that surrounds a containment volume for a cooling liquid in heat exchange with the layer of material (S), such rotating three-dimensional surface defining a heat exchange surface wetted by the liquid, and wherein a level of the free surface of the liquid on the heat exchange surface moves upwards in use due to the action of the centrifugal acceleration generated by the rotation of the support (4).

The invention relates to an isotropic thermal neutron radiation field angle distribution uniformity control device and method, and the device is characterized in that a particle accelerator is used for emitting a high-energy charged particle beam with a beam position; the beryllium target is placed along the emission line of the high-energy charged particle beam, and the high-energy charged particle beam bombards the beryllium target to generate charges; the insulation isolation gasket is wound on the outer side of the beryllium target and prevents the charges from being led out from the outside through the beryllium target; and the adjusting assembly is connected with the beryllium target and used for acquiring the electric charge quantity on the beryllium target, and is connected with the particle accelerator and used for adjusting the angle of the high-energy charged particle beam irradiating to the beryllium target. According to the invention, the purposes of preventing the charges from being exported outwards based on the insulation isolation gasket and obtaining the charge quantity by the adjusting assembly to adjust the particle accelerator are achieved, so that after the insulation isolation gasket with low cost is used for isolation, the charge quantity is detected to adjust the particle accelerator, and the technical effect of effectively saving the cost is achieved.

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.

The invention discloses an accelerator neutron source solid-state lithium target cooling device, and relates to the technical field of accelerator neutron source medical application. An annular heat pipe is arranged on the outer ring of the side portion of an oxygen-free copper substrate, a plurality of liquid absorption cores are arranged on the inner wall of the heat pipe, and meanwhile an inner cavity of the heat pipe is filled with a working medium; when heat is generated, the heat is firstly transferred to the oxygen-free copper substrate, the evaporation section of the heat pipe is heated, the working medium in the wick is quickly evaporated and gasified, the generated steam flows to the condensation section under the driving of differential pressure and is condensed into liquid in the condensation section and releases heat, and the liquid generated by condensation returns to the evaporation section again under the capillary action of the wick. The space of the arranged heat pipe is large, and in the aspect of heat dissipation, the working medium is subjected to gas-liquid phase change in the heat pipe under the action of the liquid absorption core, so that the accelerator is rapidly dissipated, heat on the solid target material film can be rapidly taken away, and the cooling effect on the accelerator is greatly improved.

This invention discloses a conveniently detachable, actively water-cooled solid-state deuterium target based on a compact neutron source, comprising a micron-sized solid titanium film, a titanium film carrier, and a water-cooled substrate. Deuterium is deposited in the solid titanium film by bombarding it with a deuterium ion beam, and neutrons are generated by collisions with the subsequent deuterium ion beam. Oxygen-free copper, with its high thermal conductivity, is used as the carrier for the titanium film. The threaded structure on the side of the titanium film carrier allows for convenient installation and removal from the water-cooled substrate. The oxygen-free copper substrate, with multiple annular water-cooling structures inside, enables rapid and effective removal of heat flux from the target, preventing deuterium particles deposited in the solid titanium film from desorbing due to excessive temperature, thus avoiding impact on neutron yield. This invention provides a conveniently detachable, actively water-cooled solid-state deuterium target suitable for compact deuterium-deuterium neutron generators, providing a sound technical foundation for the widespread application of compact accelerator neutron source systems in production and daily life.

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 in-situ cartridge comprises a substrate for holding a sample wherein said substrate comprises an electron transparent window for receiving said sample and at least one optical waveguide for illuminating said sample wherein a first edge of the at least one optical waveguide is optically couplable with a light source, wherein the at least one optical waveguide is integrated in the substrate and is extended from an edge of the substrate towards the electron transparent window. In this configuration, only the substrate carrying the sample needs to be modified. Bringing the optical waveguide in the vicinity of the sample allows for various additional light sensing techniques, as well as heating and application of electric fields.

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).

The invention relates to a device (10) for generating a burst in secondary radiation (12), comprising a primary source (14) for generating primary radiation (16) and a secondary source (18) for generating the secondary radiation (12), wherein the device (10) is configured such that the primary radiation (16) strikes the secondary source (18) and thereby generates the secondary radiation (12), wherein the primary source (14) is configured for burst-mode operation in which several pulse-burst sequences (20), each consisting of several individual pulses (22), are generated, wherein the pulse-burst sequences (20) each have a duration in the range between 0.1 ms and 1 s. The invention further relates to a method for generating a burst in secondary radiation (12).

The utility model provides a BNCT neutron target system, which comprises a continuous band-shaped functional assembly, a continuous band-shaped active layer and a continuous bearing layer, the continuous band-shaped functional assembly comprises a continuous or intermittent band-shaped active layer and the continuous bearing layer is used for bearing the active layer, and the continuous band-shaped active layer comprises a continuous band-shaped active layer and a continuous band-shaped active layer. One end of the functional assembly is mounted on the unwinding assembly, the other end of the functional assembly is mounted on the winding assembly, and a working area is formed between the unwinding assembly and the winding assembly; the intercepting assembly has the width and the length which are not smaller than those of the working area, the intercepting assembly comprises a heat dissipation layer and a hydrogen storage layer which are arranged in a mutual contact mode, and the hydrogen storage layer is arranged opposite to one side of the bearing layer in the functional assembly and makes contact with the bearing layer in a non-fixed mode. The utility model solves the problems that the service life of the conventional fixed BNCT neutron target material is short, and the target material is scrapped due to the separation of an action layer caused by the defects of bubbling and the like in the use process.

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.

A process for producing technetium-99m from a molybdenum-100 metal powder, comprising the steps of:(i) irradiating in a substantially oxygen-free environment, a hardened sintered target plate coated with a Mo-100 metal, with protons produced by a cyclotron;(ii) dissolving molybdenum ions and technetium ions from the irradiated target plate with an H2O2 solution to form an oxide solution;(iv) raising the pH of the oxide solution to about 14;(v) flowing the pH-adjusted oxide solution through a resin column to immobilize K[TcO4] ions thereon and to elute K2[MoO4] ions therefrom;(vi) eluting the bound K[TcO4] ions from the resin column;(vii) flowing the eluted K[TcO4] ions through an alumina column to immobilize K[TcO4] ions thereon;(viii) washing the immobilized K[TcO4] ions with water;(ix) eluting the immobilized K[TcO4] ions with a saline solution; and(x) recovering the eluted Na[TcO4] ions.

SOLUTION: A quickly assemblable and disassemblable target connecting structure for BNCT and a method therefor are disclosed, at least including a target section, a pipeline section, and at least one locking device configured to connect the target section and the pipeline section, wherein the locking device at least includes a lock body, a lock lever, and a driving mechanism.EFFECT: By driving a lock lever to telescopically move along an axial direction through the driving mechanism, rapid connection and rapid disassembly between the target section and the pipeline section can be achieved, the operation is simple, the assembly and disassembly efficiency is high, the convenience of replacing the target section and maintaining a vacuum system in a BNCT system is improved, and furthermore, based on a positional change of a slider, locking and unlocking are realized by telescopic movement of the lock lever along the axial direction, the structure is simplified, the concept is ingenious, and the conventional locking and unlocking modes are changed.SELECTED DRAWING: Figure 1

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.

To provide a radioactive nuclide producing system and radioactive nuclide producing method in which a radioactive nuclide can be produced safely and efficiently by a compact and light-weight apparatus.SOLUTION: A radioactive nuclide producing system S according to the present invention comprises: an electron beam accelerator 1 which irradiates electron beam 20; a target 10 for generating Bremsstrahlung radiation which generates Bremsstrahlung radiation 30 by the irradiated electron beam 20; and a target 40 for producing radioactive nuclide which includes a raw material that is irradiated with the generated Bremsstrahlung radiation 30 to produce a radioactive nuclide, where the thickness of the target 10 for generating Bremsstrahlung radiation is set within a range where a production rate of the radioactive nuclide peaks and in a condition that an irradiation dose of the electron beam 20 to the target 40 for producing radioactive nuclide becomes the smallest in the range.SELECTED DRAWING: Figure 1