158results about "Conversion in nuclear reactor" patented technology

Main characteristic of the invention is the exploitation of the very large flux of high energy neutrons generated in a nuclear fusion tokamak with beam-driven plasma for the purpose of producing radioisotopes. It specifically relates to the deployment of precursor materials into the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of Deuterium (D) and Tritium (T) to generate radioactive isotopes, so-called radioisotopes. The precursor materials contained in metallic capsules are incorporated into the blankets that surround the plasma.

A radioisotope production capsule is described. Each capsule includes generally an inner container for housing one of a target material and a neutron moderator, an outer container surrounding the inner container for housing the one of the target material and the neutron moderator not housed by the inner container, and cladding for isolating the target material from the neutron moderator. One or more modular capsules are placed in each of a plurality of plug fingers. Each single plug finger loaded with one or more capsules is inserted into a guide thimble of an array of guide thimbles in a fuel assembly.

A containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

The invention provides an isotope production method based on irradiation of a side reflecting layer of a pebble-bed high-temperature gas cooled reactor. The method comprises the following steps: transforming a neutron source duct and a physical starting device duct in the side reflecting layer of the pebble-bed high-temperature gas cooled reactor; designing an isotope target on the basis of the production requirement of the isotope to be produced and the reconstructed pore parameters, and adjusting the isotope target according to the safety analysis result of the isotope produced by online irradiation of the side reflecting layer; designing an isotope irradiation device for carrying out in-pile and out-pile operation on the isotope target, and calculating isotope irradiation theoretical parameters; and loading an isotope target into the modified pore channel through an isotope irradiation device, performing online irradiation according to isotope irradiation theoretical parameters, and discharging the isotope target after irradiation is completed. According to the method, the radioactive isotope is generated through online irradiation of the side reflecting layer of the pebble-bed high-temperature gas cooled reactor, so that the application scene of the reactor is enriched, and the utilization efficiency of the reactor is improved.

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 containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

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 provides a single / double-module energy-adjustable superconducting electron accelerator device, a medical isotope production system and a medical isotope production method, and the device comprises an injection system which is used for generating an electron beam current with certain energy and current intensity; the acceleration module system comprises single or double parallel acceleration modules, and each acceleration module comprises a superconducting cavity and a low-temperature unit; the low-temperature unit comprises a refrigerator, a high-thermal-conductivity cold chain, and a cold shield and a vacuum shell which sequentially cover the periphery; the radio frequency system is used for feeding microwave power into the superconducting cavity, maintaining the amplitude and phase stability of an electromagnetic field and accurately compensating the frequency deviation of the superconducting cavity; and the electron motion trail control system is used for guiding the electron beam to pass through the acceleration module and the plurality of circulating transmission pipelines with the corner radiuses sequentially enlarged for multiple times. The technical problems that an existing accelerator is limited by serious heating and cannot achieve high-flow-intensity and high-energy operation, a low-temperature cooling system is complex, so that the operation and maintenance cost is high, high energy and high flow intensity cannot be considered at the same time, and medical isotope production is difficult to meet are solved.

The invention relates to the technical field of isotope irradiation production, in particular to a target material arrangement device suitable for researching reactor irradiation production of iride-192. The target material arrangement device mainly comprises a cladding, a plurality of clamping blocks and iridium sheets, the clamping blocks are arranged on the inner side of the cladding and arranged around the circumference of the central axis of the cladding, and the iridium sheets are arranged on the clamping blocks; and the iridium sheet is arranged on one side, in contact with the cladding, of the clamping block. Through the structure, the target material in the target material arrangement mode of the iride-192 is designed into a pure I < r > circular sheet. The small-size target material can improve the irradiation uniformity of a single target material and can be used for manufacturing a small-size flaw detection source device, and the application range of a product is widened. The target material is defined as a natural target material and a high-enrichment-degree target material according to the difference of the content of the iridium 191 in the target material, the target material arrangement can be automatically adjusted according to the actual production requirement, and the production flexibility of the iridium 192 can be 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 provides a single-module double-cavity parallel superconducting electron accelerator device, a medical isotope production system and a medical isotope production method, and the device comprises an injection system which is used for generating an electron beam current with certain energy and current intensity; the acceleration module system comprises a low-temperature unit and a superconducting cavity; the low-temperature unit comprises a refrigerator, a high-thermal-conductivity cold chain, and a cold shield and a vacuum shell which sequentially cover the periphery; the refrigerating machine is connected with the superconducting cavity through a high-thermal-conductivity cold chain; the radio frequency system is used for feeding microwave power into each superconducting cavity, maintaining the amplitude and phase stability of an electromagnetic field and accurately compensating the frequency deviation of the superconducting cavity; and the electronic motion trail control system is used for guiding the electronic beam current to pass through the double parallel superconducting cavities and a plurality of circulating transmission pipelines of which the corner radiuses are sequentially enlarged for multiple times. The technical problems that an existing accelerator is limited by serious heating and cannot achieve high-flow-intensity and high-energy operation, a low-temperature cooling system is complex, so that the operation and maintenance cost is high, high energy and high flow intensity cannot be considered at the same time, and medical isotope production is difficult to meet are solved.

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 design, configuration and operation concept of a system, herein called radioisotope recovery system, to deploy and recover different precursor materials into and from the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of D and T ions, which will cause the generation of radioactive isotopes (also called radioisotopes). Main characteristics of the invention are (i) a closed loop that circulates precursor materials into and out of a nuclear fusion tokamak with beam-driven plasma, (ii) the compliance of the system with the design and maintenance of a nuclear fusion tokamak with beam-driven plasma.

The embodiment of the invention discloses a method and a device for preparing 212Pb based on 226Ra, and the method comprises the following steps: carrying out reactor irradiation treatment on a target material containing 226Ra to obtain an irradiated target material; and dissolving the irradiation target material to obtain a target material dissolving solution. The target material dissolving solution is placed in a first separation column to be subjected to first acid leaching treatment, a Th-containing adsorption column is obtained, and the first separation column is used for adsorbing Th. And carrying out second acid leaching treatment on the Th-containing adsorption column to obtain a Th-containing eluent. And carrying out standing treatment on the Th-containing eluent to obtain a standing solution containing 228Th. And the standing liquid containing 228Th is placed in a second separation column to be subjected to third acid leaching treatment, eluant containing 212Pb is obtained, and the second separation column is used for separating lead.

This invention provides a target loading device for producing short-half-life isotopes in a heavy water reactor, comprising a channel, an electric cylinder, and a target drum assembly. One end of the channel leads to the reactor core. The target drum assembly sequentially pushes the loaded targets to the target outlet. The main shaft of the electric cylinder is coaxially arranged with the target outlet, driving the main shaft to move towards the target outlet to push the target at the outlet into the channel. The target enters the reactor core through the channel. This invention enables the loading of short-half-life radioactive isotope targets for several days or tens of days during heavy water reactor power operation, facilitating installation and maintenance. Different types and quantities of isotope targets can be loaded into the core production channel during heavy water reactor power operation.

A radioisotope production capsule is described. Each capsule includes generally an inner container for housing one of a target material and a neutron moderator, an outer container surrounding the inner container for housing the one of the target material and the neutron moderator not housed by the inner container, and cladding for isolating the target material from the neutron moderator. One or more modular capsules are placed in each of a plurality of plug fingers. Each single plug finger loaded with one or more capsules is inserted into a guide thimble of an array of guide thimbles in a fuel assembly.

This invention discloses a method for producing radioactive isotopes in the core of an advanced high-temperature reactor using a spherical target. This invention overcomes the limitations of using neutron irradiation channels or fuel-related components of nuclear reactors, such as conditioning rods in heavy water reactors and combustible poison rods in pressurized water reactors, to produce radioactive isotopes. It sets a precedent for the mass production of radioactive isotopes using the core of a nuclear reactor, and has significant strategic implications for exploring high-value applications of commercial advanced high-temperature reactors to reduce operating costs and mass-produce radioactive isotopes, including the strategic isotope tritium.

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.

A coupler is provided for connecting the illumination target assembly to the motion system. [Solution] The coupler includes a housing and an inner assembly. The housing includes a distal end, a proximal end, and a side portion defining a cavity therein. The side portion includes a plurality of side holes extending into the cavity. The inner assembly includes an actuator body, a return member for applying an axial default force to the actuator body, and a plurality of friction members configured to be driven laterally by the actuator body through the plurality of side holes. The actuator body is disposed within the cavity and includes a first section, a second section, and an intermediate section. Also provided is a coupling system including a coupling insert for a movement system and a coupler for an irradiation target assembly.

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 invention discloses a method for producing radioactive isotopes in a reactor core of an advanced high-temperature reactor by adopting a spherical target piece. According to the invention, the limitation that the radioactive isotope can only be produced by using a neutron irradiation channel of a nuclear reactor or fuel-related components such as an adjusting rod of a heavy water reactor and a burnable poison rod of a pressurized water reactor is broken through, and a precedent of mass production of the radioactive isotope by using the reactor core of the nuclear reactor is created; the method has important strategic significance for exploring high-value application scenes of commercial advanced high-temperature reactors to reduce operation cost and producing radioactive isotopes including strategic isotope tritium in batches.

An irradiation target is formed into a sphere. The spherical irradiation target can be iridium metal (10) containing natural or enriched iridium 191. The radiation source of the present invention can be manufactured by manufacturing a spherical irradiation target, accommodating the spherical irradiation target in a rotating capsule (20), and rotating an axial flow impeller (32) by a downward flow of a reactor primary coolant, whereby the rotating capsule (20) is rotated. This radiation source provides an improved nondestructive inspection image having a high geometric resolution, and has no radiation source anisotropy and also has high target recyclability.

The present invention discloses a target component, belonging to the technical field of the core of a nuclear reactor, which includes a first end plug, a clamping tube, a second end plug, a connecting tube, a third end plug and a target rod. The first end plug is used to be connected with a pressing system, and the connection between the first end plug and the clamping tube is a movable connection. A limiting member is provided inside the connecting tube. The limiting member can move axially to be connected with the first end plug so that the first end plug is connected to the clamping tube in position, and the limiting member can move axially away from the first end plug so that the first end plug and the clamping tube are detachably connected. In the present invention, the connection between the first end plug and the clamping tube is a detachable connection, and locking and unlocking are achieved through a mechanical clamping structure, which is convenient for installation and disassembly, enables structural components such as the pressing system to be reused, reduces the cost of the radiation target, reduces the generation of radioactive waste, and at the same time, no debris or falling parts will be generated during the underwater disassembly process of the target component, and it will not affect the water in the spent fuel pool.

Reactor target assemblies are provided that can include a housing defining a perimeter of at least one volume and Np or Am spheres within the one volume. Reactor assemblies are provided that can include a reactor vessel and a bundle of target assemblies within the reactor vessel, at least one of the target assemblies comprising a housing defining a volume with Np or Am spheres being within the volume. Irradiation methods are also provided that can include irradiating Np or Am spheres within a nuclear reactor, then removing the irradiated spheres from the reactor and treating the irradiated spheres.

Various embodiments include a method of producing purified lutetium-177. The method may include irradiating a target material containing lutetium-176 in a nuclear reactor, separating lutetium-177 from the irradiated target material using electromagnetic isotope separation, dissolving the separated lutetium-177 in an acidic solution, purifying the dissolved lutetium-177 using a series of chromatographic columns and ion resins, and eluting the purified lutetium-177 in a final chemical form suitable for medical use. The chromatographic columns may include a first column containing a lanthanide resin and a second column containing a diglycolamide resin. The final chemical form may be lutetium-177 chloride.

The invention discloses an isotope production method of a pneumatic conveying type coating target material ball. The method comprises the following steps: putting a coating target ball into an absorption ball pore channel of a reflecting layer of a pebble-bed high-temperature gas cooled reactor for irradiation; after irradiation is completed, the coating target balls are conveyed back to the ball storage tank through a pneumatic conveying system; transferring the coated target balls after irradiation in the ball storage tank to a post-treatment hot chamber; and in a post-treatment hot chamber, dissolving and separating the coating of the coating target ball containing the target isotope to obtain a dissolving solution, and purifying the dissolving solution to obtain an isotope solution. Based on an existing secondary shut-down system engineering design scheme and a remote control technology, full-sealing and remote automatic operation of a target ball are achieved for isotope production, the risk that personnel make contact with radioactivity is reduced to the maximum extent, and normal power generation operation of the pebble-bed high-temperature gas cooled reactor is not affected.

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 application provides a design method of a medical isotope reactor fuel solution, which comprises: the fuel solution comprises uranyl nitrate and nitric acid; the concentration of F ‑ ≤1mg / L, Cl ‑ ≤1mg / L, total boron equivalent ≤4.0μg / gU, Ru ion ≤0.02g / L, Cr ion ≤0.05g / L, Al ion ≤11.12g / L, and other impurities meet the requirements of GB / T 10266 standard; the concentration of acid, the concentration of uranium and the temperature of the fuel solution are controlled to control the pH value of the fuel solution; the operation power density of the fuel solution is not greater than 2.0kW / L, and a catalyst is used to prevent the fuel solution from generating precipitates during operation. The design method of the medical isotope reactor fuel solution provided by the application can realize long-term stable operation of the fuel solution, and is safe and economical.