364results 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.

A nuclear reactor is discussed herein. In some examples, the nuclear reactor may comprise an inner-core region, including liquid fuel, coolant / moderator, and a hydrogen vapor space, an out-of-core region surrounding the inner-core region, the out-of-core region including, an inner reflector adjacent to the inner-core region, the inner reflector including a first irradiation facility, and an outer reflector adjacent to the inner reflector, the outer reflector including a second irradiation facility.

An electrically inactive betavoltaic battery, an electrically active betavoltaic battery, and methods of making the same are provided. In implementations, a method of making an electrically active betavoltaic battery includes: providing an electrically inactive betavoltaic battery device having one or more diodes incorporating a semiconductor material layer having a stable non-radioactive isotope; and irradiating the electrically inactive betavoltaic battery device with thermal neutrons, thereby causing the conversion of at least a portion of the stable non-radioactive isotope to a radionuclide and creating the electrically active betavoltaic battery, wherein the semiconductor material layer acts as both an electron emitter and an electron absorber simultaneously.

The invention relates to a closed circulation 226Ra solution target system for producing 225Ac. The closed circulation 226Ra solution target system comprises a solution type 226Ra target, an isotope target bin, a valve, a 226Ra solution circulation structure, a radium actinide separation structure, a radium lead separation structure, a photon detection system I, a photon detection system II, a heat exchange system, a pressure reduction radon evaporator and a radon treatment system, and the solution type 226Ra target comprises a solution circulation pipeline and a radium-containing solution. The radium-containing solution is contained in the closed solution circulating pipeline; the solution circulating pipeline comprises a main loop pipeline and two branch pipelines; the photon detection system I, the 226Ra solution circulation structure, the pressure reduction radon evaporator, the heat exchange system, the valve and the photon detection system II are sequentially arranged on the main loop pipeline; and the radium actinide separation structure and the radium lead separation structure are respectively arranged on the two branch pipelines. The system can improve the preparation efficiency and yield of 225Ac.

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 present invention relates to a production 225 Closed cycle of Ac 226 Ra solution target system. The closed cycle 226 Ra solution target system includes solution type 226 Ra target, isotope target chamber, valve, 226 Ra solution circulation structure, radium-actinium separation structure, radium-lead separation structure, photon detection system I, photon detection system II, heat exchange system, vacuum radon evaporator and radon treatment system, among which, solution type 226 The Ra target includes a solution circulation pipeline and a radium-containing solution, and the radium-containing solution is contained in a closed solution circulation pipeline; the solution circulation pipeline includes a main loop pipeline and two branch pipelines; the photon detection system I, 226 The Ra solution circulation structure, vacuum radon evaporator, heat exchange system, valve and photon detection system II are sequentially arranged on the main loop pipeline; the radium-actinium separation structure and the radium-lead separation structure are respectively arranged on the two branch pipelines. 225 Preparation efficiency and yield of Ac.

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

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.

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

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 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).

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

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.

A method and apparatus for producing radioisotopes. The method includes generating fast neutrons by irradiating a neutron producing target with a deuteron beam from a deuteron accelerator. These fast neutrons directly irradiate a first sample. The fast neutrons that pass through the first sample undergo multiple-scattering by a neutron scattering material made of a light element positioned around both the neutron producing target and the first sample. This arrangement generates various radioisotopes simultaneously in large amounts from both the first sample and a second sample through nuclear reactions. The method enables production of multiple radioisotopes in a single process for applications in medicine, research, education, agriculture, and industry.

To extract technetium-99m from low-specific-activity molybdenum-99 in a short time without being influenced by the volume of molybdenum solution.The method for recovering technetium-99m from low-specific-activity molybdenum-99 is a method in which the daughter nuclide technetium-99m produced through the decay of molybdenum-99 with a low specific activity contained in a high-concentration molybdenum solution containing the molybdenum-99 with a low specific activity is separated by using activated charcoal and recovered, and the method is characterized in that the activated charcoal is immersed into the molybdenum solution and selectively adsorbs a trace amount of technetium-99m in the solution, even when molybdenum-99 is present 1016 times or more abundantly in terms of the ratio of the number of atoms.

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).

The present invention provides a radionuclide production system and a radionuclide production method with which it is possible to produce radionuclides efficiently by improving the cooling of a target material containing a raw material nuclide and reducing contamination of the target material with impurities. A radionuclide production system comprises a particle beam irradiation device that generates a particle beam, and a target that generates radionuclides through irradiation with the particle beam. In the target, a target material containing a raw material nuclide that generates radionuclides is mounted on a target cooling plate for cooling the target material. The radionuclide production method comprises: forming a target in which a target material containing a raw material nuclide is mounted on a target cooling plate for cooling the target material; and producing radionuclides by irradiating the target with a particle beam or bremsstrahlung radiation while cooling the target material using the target cooling plate.

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.

The present invention relates to an RI manufacturing apparatus including an accelerator, a target irradiated with a particle beam of an accelerated particle emitted from the accelerator, and an incident angle adjustment mechanism that adjusts an incident angle of the particle beam to the target. The apparatus further comprises a target attachment and detachment device attached to the accelerator.

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).

A system and method for producing radioisotopes such as molybdenum-99. The system comprises a first accelerator, a second accelerator, a first beamline, a second beamline, and a target. Using a pair of accelerators, beamlines are preferably fired at a target from opposite directions, thereby irradiating the target from both sides. The system can further comprise a target cooling system utilizing gaseous helium, a modular local target shielding comprised of boxes of either metal shot with liquid coolant or steel with concrete, and a hot cell for loading and unloading target disks.

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