145results about "Conversion outside reactor/accelerators" patented technology

The invention relates to a capsule for a pneumatic rabbit system to produce medical isotopes, which comprises a capsule shell, a plurality of hemispherical limiting blocks, a heat dissipation hole channel, an isotope target fixing structure, an annular driving fan blade and a target cabin, the positioning device is used for being matched with a limiting groove in the end of a conveying pipeline in the pneumatic rabbit system for positioning. The heat dissipation hole channel penetrates through the capsule shell in the radial direction and is in a circular truncated cone shape, and the diameter of the front end of the heat dissipation hole channel is smaller than that of the rear end of the heat dissipation hole channel. The isotope target fixing structure is arranged inside or on the surface of the capsule shell; the annular driving fan blade is composed of a plurality of fan-shaped fan blades, and the fan-shaped fan blades are annularly distributed in the heat dissipation hole channel; the isotope target fixing structure and the annular driving fan blade are arranged in a staggered manner; the target cabin is fixedly connected to the isotope target fixing structure and is used for sealing the isotope target. The capsule can achieve posture balance and self-positioning in the pneumatic transmission process, and has efficient heat dissipation performance.

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 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 application relates to radionuclide separation and purification technical field, specifically disclose a kind of separation and purification method for preparing lead-212 and actinium-225 by photo nuclear reaction method.It includes the following steps: radium target solution is sequentially passed through lead resin column and DGA resin column, and recovery liquid is obtained;First eluent is used to elute lead resin column, and lead-212 first purification liquid is obtained;Second eluent is used to elute DGA resin column, and actinium-225 first purification liquid is obtained;Lead-212 first purification liquid is introduced into first LN resin column, and third eluent is used to elute first LN resin column, then third desorption liquid is introduced into first LN resin column, and lead-212 second purification liquid is obtained;Actinium-225 first purification liquid is introduced into second LN resin column, and fourth eluent is used to elute second LN resin column, then fourth desorption liquid is introduced into second LN resin column, and actinium-225 second purification product solution is obtained.The present application effectively avoids the cumbersome operation steps such as medium conversion, improves the separation and purification efficiency of lead-212 and actinium-225 in radium target.

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.

Provided is a method for producing a solution of atropine with improved recovery. A method for producing a solution of atropine-211, comprising the steps of: irradiating bismuth with alpha rays, generating atropine-211 in the bismuth, and distilling the bismuth irradiated with the alpha rays, separating and purifying atropine-211, and dissolving it in an aqueous sodium bicarbonate solution.

The application relates to a capsule for producing medical isotopes by using a pneumatic rabbit system, which comprises a capsule shell, a plurality of hemispherical limiting blocks, a heat dissipation channel, an isotope target fixing structure, an annular driving fan blade and a target cabin, the hemispherical limiting blocks are arranged on the front end face of the capsule shell and used for matching and positioning with limiting grooves at the end of a transmission pipeline in the pneumatic rabbit system, the heat dissipation channel penetrates the capsule shell in the radial direction, the heat dissipation channel is in the shape of a circular truncated cone, the diameter of the front end of the heat dissipation channel is smaller than that of the rear end, the isotope target fixing structure is arranged inside or on the surface of the capsule shell, the annular driving fan blade is composed of a plurality of fan-shaped fan blades which are annularly distributed inside the heat dissipation channel, the isotope target fixing structure and the annular driving fan blade are arranged in a staggered mode, and the target cabin is fixedly connected to the isotope target fixing structure and used for sealing the isotope target. The capsule can realize posture balance and self-positioning during pneumatic transmission and has high heat dissipation performance.

This invention relates to the field of medical radioisotope manufacturing technology, and more particularly to a method based on proton beam irradiation. 232 Th target production 212 The method for Pb. The present invention provides a method based on proton beam irradiation. 232 Th target production 212 The method for treating Pb includes the following steps: irradiation with a proton beam. 232 Th target production 228 Th; Dissolved using a mixture of acid and water 232 Th target, allowed to stand, yields the first Th solution; separation from the first Th solution or the pretreated first Th solution... 212 Pb. This invention employs proton beam irradiation. 232 The Th target material method will significantly improve 228 The content of Th was thus significantly increased. 212 The increased production efficiency of Pb fundamentally solves the problems of low output and high cost associated with traditional methods.

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 present invention relates to a remotely operated system (200) to deploy and recover materials (25) into and from a nuclear fusion device (100), for the purpose of exposing said materials (25) to neutron radiation, which will cause the generation of radioactive isotopes, comprising at least one loop made of pipes (14) with constant inner diameter, a plurality of capsules (23) with an outer diameter slightly smaller than the inner diameter of the at least one loop (14), wherein the capsules (23) are adapted to contain the material (25) to be irradiated by the neutron radiation, a propulsion system for circulating the capsules (23) through the at least one loop (14), a remotely operated capsule filling system (18) for filling said capsules (23) into the at least one loop (14), and a remotely operated capsule recovery system (19) for recovering said capsules (23) from the at least one loop (14).

The invention relates to a cyclotron which enables the production of α- or β-emitting radionuclides. The cyclotron, with a magnetic periodicity of 3, comprises three accelerating cavities connected to the centre, thus not requiring phase control between the cavities, forming a single high-frequency resonator. The six accelerating gaps per turn enable rapid acceleration (the angle ϕ between the accelerating gaps of each cavity being approximately 30°) which is essential for acceleration at the third and sixth harmonics. This cyclotron preferably has an injection system (31) supplied by different types of ion sources, making it possible to efficiently accelerate charged particles having Z / A ratios equal to 1 / 2 and to 1 / 4. The cyclotron may also have stripping extraction means positioned in the cyclotron so as to extract the charged particles and double their state of charge. These particles enable a set of nuclear reactions for producing α-emitting radionuclides.

The present disclosure provides various methods, systems, and devices for producing actinium-225 (Ac-225). In one aspect of the disclosure, a method for producing Ac-225 includes inserting an irradiation target assembly into a commercial nuclear reactor. The irradiation target assembly comprises a radium-226 (Ra-226) material. The method further includes producing electricity using the commercial nuclear reactor by generating a neutron flux in the commercial nuclear reactor. The method further includes irradiating the Ra-226 material with the neutron flux generated in the in the commercial nuclear reactor to produce a radium-225 (Ra-225) material. The Ra-225 material decays to produce an Ac-225 material.

In an embodiment of the present disclosure provided is a method of producing radionuclides that includes the installation, irradiation, transport, and trapping steps. In the installation step, a target material containing a target nuclide is placed inside a target chamber. In the irradiation step, at least a portion of the target material is irradiated with a quantum beam. In the transport stage, a carrier gas is supplied to the inside of the target chamber and an ambient gas around the target material is sent to the outside of the target chamber through an exhaust pipe. In the trapping step, a trap device connected to the exhaust pipe is configured to trap the radionuclides produced from the target nuclide from the ambient gas. In the present embodiment of the present disclosure, the target nuclide is bismuth 209 and the produced radionuclide is astatine 211. In an embodiment of the present disclosure, a target holding device 100 for quantum beam irradiation comprising a target material container 3 and a rotational drive mechanism 5 is also provided, as well as a quantum beam irradiation system 1000. An example target material container is rotatable.

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.

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 relates to the technical field of radioactive isotope preparation, and provides dissolving and alkali adjusting equipment which comprises a melting device, a dissolving device, an alkali adjusting device, a pumping device and a control system, and the melting device is used for melting a target material in a sealed capsule target piece; a dissolving cavity and an opening communicated with the dissolving cavity are formed in the dissolving device, and the molten target material can enter the dissolving cavity from the opening and is dissolved in the dissolving cavity; an alkali adjusting cavity communicated with the dissolving cavity is formed in the alkali adjusting device, and a dissolving solution of the target material can be adjusted to be alkaline in the alkali adjusting cavity; the pumping device is used for pumping a dissolving agent to the dissolving cavity, pumping an alkaline agent to the alkali adjusting cavity and pumping a dissolving solution of a target material to the alkali adjusting cavity; the control system is configured to be capable of adjusting melting parameters of the melting device, dissolving parameters of the dissolving device, alkali adjusting parameters of the alkali adjusting device and pumping parameters of the pumping device. According to the dissolution and alkali adjustment equipment provided by the invention, irradiation damage to operators can be reduced.

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 application discloses a method and device for preparing elements on demand by means of controllable nuclear fusion-nuclear transmutation with deuterium (hydrogen isotope) as the only raw material, belonging to the technical field of controllable nuclear physics and element synthesis, and suitable for laboratory small-batch research scenarios. The core is that under controllable conditions in the laboratory, 10-15 MeV high-energy neutrons are generated by deuterium nuclear fusion, and low-radioactivity / stable target materials are directionally bombarded, and stable products such as noble metals and rare earth elements are directionally prepared through nuclear transmutation and decay (1-50g per single preparation), the reaction by-products can be recycled, the fusion energy recovery rate is greater than or equal to 30%, and the external power supply accounts for less than or equal to 70%, which does not constitute unlimited energy output. The total floor area of the device is less than or equal to 10 m2, and the total power is less than or equal to 200 kW, and the device has the advantages of wide raw material sources, environmental friendliness, strong controllability and the like, and can be applied to the fields of noble metal preparation, new energy material synthesis, harmless treatment simulation of nuclear waste and the like, and fills the technical gap of global laboratory-level deuterium-based element preparation on demand.

Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.

To provide a radioisotope manufacturing technology that can manufacture radioisotope according to customer request.SOLUTION: The radioisotope manufacturing apparatus 1 includes an electron gun 2 that generates an electron beam E, an accelerator 3 that accelerates the electron beam E, a bending electromagnet 4 that distributes the electron beam E accelerated by the accelerator 3, and at least two manufacturing ports 5 that are provided on the tip branching off from the bending electromagnet 4 and in which radioisotope is manufactured by the incidence of the electron beam E.SELECTED DRAWING: Figure 1

In particular, methods and systems for the periodic enrichment of rare earth elements and isotopes are provided. A crucible, or a tube or ampoule which may have two coaxially opposing crucibles in fluid communication, is used to hold a source material in a vacuum and irradiate the source material to enrich it with respect to a product material. Source material (e.g., 176 Irradiating with Yb-enriched Yb to produce a product (for example, 177 After obtaining Lu), the mixture may be sublimated to remove most of the source material and concentrate the product material by, for example, heating the lower part of the tube and cooling the upper part of the tube to condense the sublimated source material at the top of the tube. Subsequently, the concentrated product material may be purified, or the solidified source structure may be reused in an irradiation / sublimation cycle to further enrich and concentrate the product material.

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

The inventors have developed technology to improve the generation of daughter isotopes for clinical treatments. The technology includes systems and methods for using a liquid target to deliver parent isotopes to a reactor for neutron bombardment and subsequently separating desired daughter isotopes from the liquid target. According to an aspect of the technology described herein, a method of obtaining desired daughter isotopes comprises pumping a liquid target solution comprising a parent isotope through a fluid path that includes a first portion that passes through a fission reactor, a second portion that passes through a pump, and a third portion that passes through an isotope capture device.

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

The present invention relates to a remote handling system (200) for the introduction and recovery of a material (25) into and from a nuclear fusion device (100) with the aim of exposing said material (25) to neutron radiation, which will cause the production of radioisotopes, the system comprising at least one loop made of a pipe (14) with a constant internal diameter, a plurality of target boxes (23) with an external diameter slightly smaller than the internal diameter of the at least one loop (14), wherein the target boxes (23) are adapted to contain the material (25) to be irradiated by the neutron radiation; a propulsion system for circulating the target boxes (23) through the at least one loop (14); a remotely operated target box filling system (18) for filling said target boxes (23) into the at least one loop (14), and a remotely operated target box recovery system (19) for recovering said target boxes (23) from the at least one loop (14).

Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.