57 results about "Radium" patented technology

Systems and methods for generating radionuclides, such as radium-224, are disclosed herein. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, and a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a fourth resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

A method of generating an emulsion for treating a patient. The method includes generating a water-based solution carrying an agent which turns into a hydrogel by addition of calcium ions. Radium radionuclides are added to the water-based solution in a concentration sufficient for radiotherapy. After adding the radium to the water-based solution, the water-based solution is mixed with an emulsifier and an oil.

Systems and methods for generating radionuclides, such as radium-224. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228 and bismuth-212, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a third resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

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 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.

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.

A radiation therapy source (20, 30, 40) for treating a tumor includes a flexible core (22) impermeable to radon and a polymeric coating (28, 48) on the flexible core. The polymer coating is impermeable to radium and allows radon to diffuse through the polymer coating. The radiation therapy source further includes an alpha-emitting radium radionuclide (26) in the polymer coating or between the flexible core and the polymer coating.

Methods of processing phosphogypsum (PG) to recover Radium (e.g., 226Ra), and / or other constituents from PG, are described. PG (stockpiled PG, fresh PG or a combination) is combined with a leach solution, allowed to react for 2-6 hours (e.g., a single leaching step), at a temperature in the range of about 40-70 °C to obtain leachate and leach residue. Further processing by subjecting the leachate and / or the leach residue to one or more separation techniques, such as ion exchange, enables the recovery of one or more constituents of interest. By separating 226Ra, rare earth elements (REE) and / or other constituents from this secondary resource (e.g., waste PG), gypsum can be purified for use in the construction industry, the recovery of 226Ra can be used to produce dedicated isotopes like 223Ra and / or 223 Ac for life-saving cancer medication, and raw materials can be provided for the high-tech industry, agriculture and the building industry.

The invention belongs to the technical field of sandstone-type uranium ore, and particularly relates to a method for improving the credibility of a sandstone-type uranium ore metallogenic age test result, and the method comprises the steps: 1, carrying out the sampling, drilling and screening of a working region; 2, selecting a rock core as a sample according to the mineralization thickness of the ore section; 3, dividing each sample into a plurality of lower samples, and respectively carrying out U and Pb isotope determination and radium content determination on the lower samples; and step 4, performing U-Pb isochrone age fitting according to U and Pb isotope determination and radium content determination results of the plurality of lower small samples in each sample to obtain the ore-forming age of the sandstone type uranium ore. According to the method, personal subjective factors in the sandstone type uranium ore metallogenic age test process can be effectively reduced, and the credibility of the sandstone type uranium ore metallogenic age test result is improved.

Techniques are described for producing radium-225 from a sample containing radium- 226, and milking the sample for actinium- 225, which results in a higher yield of actinium-225 for a given sample in a given period of time compared with conventional approaches. In particular, returning the sample to the reactor while there is still a significant amount of radium-225 in the sample can, over time, produce more actinium- 225 than the conventional approach of milking the sample until the vast majority of radium-225 has decayed into actinium-225.

This invention discloses a method for selectively separating uranium and radium, belonging to the field of solid waste treatment technology. The method utilizes modified rapeseed straw hydrothermal carbon (HTC-AA-Na). The hydrothermal carbon preparation method includes placing pretreated rapeseed straw in an aqueous acrylic acid solution for carbonization to obtain hydrothermal carbon HTC-AA rich in carboxyl functional groups; then, HTC-AA is placed in a NaOH solution and stirred, and the H groups in the carboxyl groups are removed through cation exchange. + Replaced with Na + HTC-AA-Na was obtained. When NaNO3 was added to a mixed solution containing uranium and radium, HTC-AA-Na selectively adsorbed uranium while hardly adsorbing radium; when EDTA-2Na was added to the same solution, HTC-AA-Na selectively adsorbed radium while hardly adsorbing uranium, thus achieving selective separation of uranium and radium. This invention provides a green and sustainable technical path for the harmless treatment of uranium tailings.

The invention discloses a rare earth radioactive slag reduction and barium sulfate slag recycling method based on transformation and decomposition of barium sulfate. The method comprises the following steps: drying, ball-milling and screening rare earth radioactive slag, adding water into sodium hydroxide, and mixing to obtain rare earth slag; roasting and transforming the rare earth slag under the condition of introducing carbon dioxide; washing the roasted and transformed rare earth slag with water; the washed rare earth slag is subjected to acid dissolution and solid-liquid separation, and high-silicon slag without radioactive elements and an acid solution with the radioactive elements are obtained; sulfuric acid is added into the acid solution step by step for fractional precipitation and radium removal, and barium and radium residues containing radioactive elements and barium sulfate residues without radioactivity are obtained through solid-liquid separation; adjusting the mass ratio of the barium sulfate slag and sodium hydroxide, then carrying out alkali conversion and acid dissolution to obtain a barium chloride solution, and recycling the barium chloride solution for removing sulfate radicals from the rare earth feed liquid. According to the method, barium sulfate in the rare earth radioactive slag can be transformed into more than 95% of soluble barium salt, the amount of the rare earth radioactive slag is reduced by more than 85%, and the barium circulation rate reaches more than 90%.

An embodiment of the present invention relates to a 226Ra recovery method, the 226Ra recovery method including a step (A1) in which a 226Ra-containing substance that is in a solid state and a carrier that has the function of adsorping 226Ra ions are immersed in a treatment solution, after which the treatment solution is irradiated with ultrasonic waves.

A method of generating an emulsion for treating a patient. The method includes generating a water-based solution carrying an agent which turns into a hydrogel by addition of calcium ions. Radium radionuclides are added to the water-based solution in a concentration sufficient for radiotherapy. After adding the radium to the water-based solution, the water-based solution is mixed with an emulsifier and an oil.

The invention relates to wet preparation of a radiation therapy source and a method for accumulating radium radionuclides. The method comprises providing a first solution comprising a thorium radionuclide and a thorium binding extractant, wherein the first solution does not bind to radium; allowing a portion of the thorium radionuclides in the first solution to decay to radium atoms; and collecting radium atoms resulting from the decay. The collected radium atoms may be contained in a solution into which a brachytherapy source is immersed in a manner that collects radium atoms onto the brachytherapy source.

Methods of processing phosphogypsum (PG) to recover Radium (e.g., 226Ra), and / or other constituents from PG, are described. PG (stockpiled PG, fresh PG or a combination) is combined with a leach solution, allowed to react for 2-6 hours (e.g., a single leaching step), at a temperature in the range of about 40-70° C. to obtain leachate and leach residue. Further processing by subjecting the leachate and / or the leach residue to one or more separation techniques, such as ion exchange, enables the recovery of one or more constituents of interest. By separating 226Ra, rare earth elements (REE) and / or other constituents from this secondary resource (e.g., waste PG), gypsum can be purified for use in the construction industry, the recovery of 226Ra can be used to produce dedicated isotopes like 223Ra and / or 225Ac for life-saving cancer medication, and raw materials can be provided for the high-tech industry, agriculture and the building industry.

Methods of processing phosphogypsum (PG) to recover Radium (e.g., 226Ra), and / or other constituents from PG, are described. PG (stockpiled PG, fresh PG or a combination) is combined with a leach solution, allowed to react for 2-6 hours (e.g., a single leaching step), at a temperature in the range of about 40-70° C. to obtain leachate and leach residue. Further processing by subjecting the leachate and / or the leach residue to one or more separation techniques, such as ion exchange, enables the recovery of one or more constituents of interest. By separating 226Ra, rare earth elements (REE) and / or other constituents from this secondary resource (e.g., waste PG), gypsum can be purified for use in the construction industry, the recovery of 226Ra can be used to produce dedicated isotopes like 223Ra and / or 225Ac for life-saving cancer medication, and raw materials can be provided for the high-tech industry, agriculture and the building industry.

Systems and methods for generating radionuclides, such as radium-224. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228 and bismuth-212, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a third resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

Methods of processing phosphogypsum (PG) to recover Radium (e.g., 226Ra), and / or other constituents from PG, are described. PG (stockpiled PG, fresh PG or a combination) is combined with a leach solution, allowed to react for about 2-6 hours (e.g., a single leaching step), at a temperature in the range of about 40-70° C. to obtain leachate and leach residue. Further processing by subjecting the leachate and / or the leach residue to one or more separation techniques, such as ion exchange, enables the recovery of one or more constituents of interest. By separating 226Ra, rare earth elements (REE) and / or other constituents from this secondary resource (e.g., waste PG), gypsum can be purified for use in the construction industry, the recovery of 226Ra can be used to produce dedicated isotopes like 223Ra and / or 225Ac for life-saving cancer medication, and raw materials can be provided for the high-tech industry, agriculture and the building industry.

A system and method are provided for obtaining radium radionuclides by separating radium from thorium and other nuclides. The system and method in one embodiment can comprise a multi-column configuration in which the first column is a strong cation exchange column onto which radium is adsorbed, the next columns comprise TEVA and TRU resins that adsorb and removes nuclides from radium, and subsequent columns can include Pb resin, mono- or di-phosphonic acid based resins, and / or prefilter resin, that further remove nuclides from radium.

The present application relates to an apparatus for manufacturing a material containing radium-225 from a material containing radium-226, by which apparatus a starting material containing radium-226 is subjected to neutron irradiation from a nuclear reactor to cause 226 Ra to be converted into radium-225, thereby providing a material containing radium-225, characterized in that the neutron irradiation of the starting material containing radium-226 is carried out in a moderated nuclear reactor; and the starting material containing radium-226 is shielded with a thermal neutron absorption shield.

The invention provides a laminated beta-gamma radiation sampling uranium measuring instrument and method.The measuring instrument comprises a laminated beta-gamma radiation sampling probe and a processing unit, and the laminated beta-gamma radiation sampling probe converts beta rays and gamma rays emitted by rock ore into nuclear pulse signals; the processing unit is specifically a computer with preset measurement software, and the computer is used for processing a beta channel instrument spectrum and a gamma channel instrument spectrum which are formed by modulating the nuclear pulse signals through the electronic circuit unit, so that measurement and calculation of the uranium grade are completed. The radiation sampling instrument can measure the intensity of beta rays emitted by uranium series and the intensity of gamma rays emitted by a radium group at the same time when uranium and radium in rock ore are in radioactive imbalance, the grade of uranium in the rock ore can be determined more accurately, one-time measurement is adopted, and the working efficiency is high; and the large-area GAGG + SiPM and large-volume scintillator + PTM laminated type combined beta-gamma probe is high in sensitivity, good in stability and convenient to popularize and use.

The present application relates to the technical field of medical isotopes, and particularly relates to a thorium phosphonate framework material, a preparation method thereof and application of the thorium phosphonate framework material in a thorium-radium generator. The thorium phosphonate framework material has a chemical formula of Th2(TppmH4)2(H2O)4·8H2O, a monoclinic crystal structure, a space group of P21 / c, a unit cell parameter of a=14.4222-14.4242 Å, b=22.5950-22.5982 Å, c=22.1265-22.1301 Å, β=108.993-108.997°, and a unit cell volume of 6819.239 ų. The thorium phosphonate framework material is a solid particle for imprisoning thorium ions in a framework material, and when applied in a thorium-radium generator, the volume of the generator can be reduced, and the specific activity of a radium product can be improved; when thorium is decayed into radium, the radium can be released from the restraint of the framework material, and the radium can be directly eluted out of the framework material.

Systems and methods for generating radionuclides, such as radium-224. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228 and bismuth-212, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a third resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

The invention discloses a method for extracting prenuclide and preparing medical alpha isotope on a large scale based on monazite discharged waste slag. According to the method, high-value conversion of radioactive waste is realized by comprehensively utilizing the monazite waste slag. The alpha isotope is used as a core raw material for extracting preposed nuclide, so that the environmental harm of radioactive waste residues is reduced, waste is turned into wealth, and a stable raw material source is provided for preparing the medical alpha isotope. A complete technical chain for extracting the medical alpha isotope 225Ac / 212Pb from the monazite waste slag containing 226Ra and 228Ra is constructed, and efficient output of high-value nuclides is achieved. 226Ra and 228Ra in the discharged waste slag are obtained through a step-by-step extraction process flow of a coarse radium product and a fine radium product, a radium target of an ECANS device is manufactured, and hot medical alpha isotopes such as 225Ac, 212Pb and the like can be prepared on a large scale by utilizing a photo-nuclear reaction. According to the preparation mode, the utilization rate of the discharged waste slag is increased, and the requirement of radioactive diagnosis and treatment on the medical alpha isotope can be met.

This invention provides a method for separating lead radioisotopes from a mixture comprising lead radioisotopes and radioisotopes of radium or thorium, and a system comprising multiple chromatographic columns. The system may include a first ferrule column having a lead complexing medium that preferentially binds lead radioisotopes compared to radium or thorium radioisotopes; and a second ferrule column having a weak cation exchange medium, wherein the pH of the loading solution for loading the second ferrule column is pH [pH value missing]. 2L The pH of the eluent used to elute lead radioisotopes from the second cassette column is pH. 2E And pH 2L greater than pH 2E The system may also include a third and a fourth cassette column with chromatographic media for the extraction and purification of lead radioisotopes, thereby providing a purified solution of lead radioisotopes that can be used for medical and other purposes, such as for labeling radiopharmaceutical compounds.

The invention provides a target design for preparing Ac-225 through irradiation of Ra-226 by an accelerator, and particularly provides an application of a metal niobium film in preparation of medical isotope actinide 225, the niobium metal film is selected as a covering material to cover radioactive radium deposited on a target, and therefore radioactive gas is prevented from polluting a target chamber and the environment. In addition, the annular groove is machined in the target piece base body, so that the upper surface of the target piece is kept flat after the niobium film is added, and installation of the target piece on an accelerator is facilitated.

METHOD FOR PURIFYING RADIUM FROM BARIUM AND IMPURITIES IN AQUEOUS SOLUTION. The present invention relates to a method for separating radium from barium by selective chromatographic separation. Figure for abstract: None

The invention discloses an ionic rare earth concentrate acid leaching optimization process. The process comprises the following steps: acid leaching, adding barium chloride to generate barium sulfate precipitate, adding solid sodium carbonate, filtering to obtain insoluble residues and barium chloride radium feed liquid, extracting leachate to recover thorium, and the like. The method has the advantages that main radioactive elements, namely thorium and radium, in the acid-soluble slag generated in the original process can be separated and enriched in the previous acid-soluble slag and the primary barium sulfate slag, the previous acid-soluble slag and the primary barium sulfate slag are subjected to specific treatment, and the total amount of radioactive solid waste is reduced.

A method for determination of Actinium-227 (Ac-227) via indirectly produced Ra-225 / Ac-225 parent / daughter. The determination of Ac-227 or its decay daughters can be used as a “pre-release” quality control test for total Ac-227 content.