474results 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.

The invention relates to the technical field of isotope production equipment, in particular to a target device for isotope production, which comprises a target chamber and a target assembly, the target chamber is provided with an inner cavity, and a plurality of beam holes arranged in an array are formed in the face, facing beam current, of the target chamber. The beam holes are covered with target windows. The target assembly is inserted into the target chamber and comprises a target frame and a target capsule; the target frames and the target windows are arranged in a one-to-one correspondence manner, and at least one mounting position for mounting the target capsule is arranged in each target frame in the axial direction of the beam hole; openings are formed in the two sides of each target frame, the side openings of the multiple target frames correspond to one another and define an independent cooling liquid flow channel with the inner wall of the target chamber, and gaps are formed in the two sides, in the axial direction of the beam hole, of each target capsule and used for allowing cooling liquid to flow through. A detachable cover plate assembly is arranged at the top of the target chamber, and the target assembly is integrally sealed in the target chamber in an assembling state. The scheme is used for solving the defects that the target assembly is inconvenient to disassemble and assemble, the safety is low and the cooling water sealing is difficult to guarantee in a high-radiation dose environment.

The invention belongs to the technical field of isotope production, and particularly relates to a 177Lu irradiation production method based on a pressurized water reactor. Comprising the following steps: step 1, packaging Lu2O3 powder in a target box, performing sealing treatment, and storing the target box in a storage tank of a rabbit system outside a reactor core; 2, during the operation period of the pressurized water reactor, transporting the target piece box into the reactor core through a running rabbit system; 3, the target piece box receives neutron irradiation at the axial middle position of the central instrument pipe, and 176Lu reacts to generate 177Lu; 4, when the 177Lu generated by the irradiation of the 176Lu in the target box reaches the designed saturation specific activity, transporting the target box to a post-irradiation target storage tank outside the reactor core; and 5, during the operation period of the pressurized water reactor, repeating the steps 2-4 until the reactor is shut down. The method has the beneficial effects that the single irradiation time of the target boxes can be controlled through analysis, so that a plurality of target boxes can be irradiated in a single refueling period of the pressurized water reactor, and the yield of 177 Lu is greatly improved.

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.

The invention belongs to the technical field of production of isotopes by a sodium-cooled fast reactor, and aims to solve the problems that the moderation effect is limited, the reactor core disturbance is relatively large and fast neutron energy spectrum is not beneficial to the production of the ultra-uranium isotopes during the production of the ultra-uranium isotopes. The invention provides a method for producing a super-uranium isotope by using a sodium-cooled fast reactor and a sodium-cooled fast reactor core. According to the method, moderator assemblies and super-uranium isotope production assemblies are arranged on a first circle of a radial conversion area in a flower arrangement mode, the super-uranium isotope production assemblies are arranged on a second circle of the radial conversion area, and the side, facing the center of the reactor core, of the first circle is coated with a thermal neutron absorption material; the reactor core is provided with a radial conversion area, moderator assemblies and super-uranium isotope production assemblies are arranged on a first circle of the radial conversion area, the super-uranium isotope production assemblies are arranged on a second circle of the radial conversion area, and thermal neutron absorbing materials are arranged on the side, facing the center of the reactor core, of the first circle. The super-uranium isotope is concentrated in the radial conversion region for production, the moderation effect is good, the disturbance to the reactor core is small, and the productivity is high.

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).

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.

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 method is provided of continuous manufacturing of Actinium-225 from a radium generator by repeating chemical purification is provided.

A system for the safe preparation and injection of a radioactive isotope of H2 15 O for use in positron emission tomography (PET). The invention also relates to a safety valve for controlling the flow rate of H2 15 O used in PET, the use of said safety valve, and a method for preparing and injecting H2 15 O.

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.

A container for a solid target material and a radioisotope produced by proton beam irradiation of the solid target material, the container having: a well, which is suited to support on its own bottom wall a portion of solid target material; a support body, which extends along a longitudinal axis and has a seat for housing the well in such a way that the bottom wall is arranged transversely to the longitudinal axis; and a lid, which comprises a central portion having a degrader foil for degrading the proton beam and can be fitted on the support body so that the central portion is arranged in the well to retain the portion of solid target material on the bottom wall and that the degrader foil is arranged above the portion of solid target material.

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).