233results about "Conversion outside reactor/accelerators" 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 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 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 relates to a separation method suitable for At-211 produced by a linear accelerator, which comprises the following steps: performing gradient pressing on bismuth powder and a pore forming agent, and sintering on a porous silicon carbide substrate to form a gradient pore bismuth-silicon carbide composite target material; bombarding the gradient pore bismuth-silicon carbide composite target material through a high-energy particle beam generated by a linear accelerator, and carrying out nuclear reaction on bismuth atoms in the target material to generate At-211; the bombarded target material is pretreated through argon plasma; distilling the pretreated target material under pulse carrier gas to realize volatilization separation of At-211, wherein the carrier gas comprises inert gas, reducing gas and organic acid steam; the distilled gas is subjected to gradient condensation through the micro-channel condenser; and adding an extracting agent into the micro-channel condenser, and dissolving the At-211 in the extracting agent to obtain an At-211 solution. The high-flux separation method of At-211 suitable for linear accelerator production, provided by the invention, is stable, efficient and rapid.

Techniques are described for producing actinium-225 by arranging a converter material at least partially around a target material, where the target material includes radium-226. The converter material comprises a compound of lithium and hydrogen at least partially enriched with lithium-6 and deuterium, and is configured to convert thermal neutrons to fast neutrons, which are then incident on the radium-226. If the fast neutrons have a kinetic energy of at least 6.4 MeV, they will initiate a (n,2n) reaction that converts radium-226 into radium-225, which then decays into actinium-225. The process can desirably be performed within an environment rich in thermal neutrons, such as within a fission 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 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.

A system for the production of a radioisotope comprising a container (1), which has a planar face (4) on which a portion of solid target material (M) is present having an elliptical shape, an irradiation station (35) for emitting a proton beam (B) against the portion of solid target material (M) in the container (1) and a transfer system (37) for transferring the container (1) to the irradiation station (35). The irradiation station (35) has an annular seat (39), which is suitable for coaxially receiving the container (1) from the side of the planar face (4) and is oriented obliquely with respect to the proton beam (B) in such a way that a section (S) of the proton beam (B) along a plane of the annular seat (39) is elliptical. The transfer system (37) comprises a housing (42) for the container (1), a rotation assembly (43) for rotating the container (1) within the housing (42) in order to orient the elliptical shape of the solid target material portion (M) as the elliptical shape of the proton beam section (B), and a handling assembly (45) for grasping the container (1) from the side opposite the planar face (4) and transferring it from the housing (42) to the annular seat (39).

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).

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).

To provide an electron-generating material and electron-generating member, which can reduce a friction coefficient.SOLUTION: An electron-generating material capable of reducing a friction coefficient is provided, the material comprising powder of a natural mineral containing a radioactive substance and powder of an electron-generating material that generates electrons when subjected to alpha rays emitted from the natural mineral, where the powder of the electron-generating material comprises titanium dioxide powder, lanthanum hexaboride, and silicon metal.SELECTED DRAWING: None

Cobalt intermetallic compounds that include cobalt and a second element are provided. The isotopes of the second element in the compounds are present in their natural isotopic abundance or in an enriched isotopic abundance. Methods of making the compounds and methods of using the compounds as targets in the production of radionuclides are further provided.

In some embodiments, provided herein are apparatuses and methods useful for producing radioisotopes. In some embodiments, a system for producing radioisotopes includes a high-energy photon source configured to emit photons, a first target positioned behind the photon source and configured to be illuminated by the photons, and a second target positioned behind the first target and configured to be illuminated by the photons, the second target being a different material than the first target.

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 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.

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.

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.

The application discloses a column tube system and a generator, the column tube system comprising a chromatographic column, elastic plugs and a support, the chromatographic column being provided with two openings at two axial ends thereof; the two elastic plugs are connected with the two ends of the chromatographic column respectively and used for sealing the openings of the chromatographic column; the support comprises a first support leg, two limiting plates being arranged on the first support leg and spaced apart along a first direction, the chromatographic column and the two elastic plugs being located between the two limiting plates, and the two elastic plugs abutting against the two limiting plates respectively. The column tube system disclosed by the application is provided with the support, the support being provided with the two limiting plates which are spaced apart, the chromatographic column is clamped between the two limiting plates when the chromatographic column is installed, the elastic plugs at the two ends of the chromatographic column abut against the two limiting plates respectively, the chromatographic column is extruded and limited by the two limiting plates, the installation stability of the chromatographic column in the production process is improved, and the liquid leakage probability is reduced.

The invention provides a preparation method of a spin-free autonuclear isotope and a quantum bit structure. The preparation method comprises the following steps: providing a substrate; according to the embodiment of the invention, the surface area of the substrate is marked in a partitioned manner to obtain the plurality of first sub-areas, so that the nuclear-free spin isotope can be conveniently and accurately positioned subsequently through the smaller first sub-areas. And performing isotope separation and purification on the elements in each first sub-region through laser to obtain second sub-regions corresponding to each first sub-region, and determining distribution information of the nuclear-free spin isotopes in each second sub-region, the distribution information being used for identifying regions where the nuclear-free spin isotopes are located in the second sub-regions. In a word, low-cost preparation can be achieved due to the fact that a centrifugal machine is not needed when the nuclear-free spin isotope is prepared in the mode, and on the other hand, the specific area where the nuclear-free spin isotope is located can be accurately positioned by conducting positioning marking on the surface area of the substrate, and accurate positioning of the nuclear-free spin isotope is achieved.

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.

The present invention extracts, at a use point such as a hospital: a radiopharmaceutical using radioactive molybdenum-99 having low specific activity as a raw material; and radioactive technetium-99m, which serves as a labeling compound raw material for the radiopharmaceutical.　Activated carbon or alumina is charged into a metal net-like cylindrical container which is not a column in which flow rate is limited. The metal net-like cylindrical container is immersed in a molybdenum solution brought to a low-pH acidic state and kept flowing by stirring, thereby preparing a molybdenum-99-adsorbed column in which the molybdenum-99 is adsorbed on the activated carbon or the alumina. The technetium-99m generated from the molybdenum-99 is eluted out from the molybdenum-99-adsorbed column and is then passed through a technetium-99m purification column filled with aluminum oxide, thereby capturing the technetium-99m. Physiological saline having a neutral pH is passed through the technetium-99m purification column, thereby separating and eluting out the technetium-99m, which is purified and recovered after impurities are removed therefrom.

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.