74 results about "Radium" patented technology

The present invention relates to a device-produced medical isotope 225 Photonuclear reaction preparation in Ac production technology 225 Ac radium target design, specifically involving a method for producing 225 Ac's 226 Ra isotope target and its application. 226 The Ra isotope target comprises a nickel substrate, 226 Ra isotope sample, nickel electroplating layer and nickel protective shell; wherein, 226 The Ra isotope sample is evenly concentrated in the center of the nickel substrate, and the nickel electroplating layer covers 226 The outer surface of the Ra isotope sample, and the nickel substrate and nickel electroplating layer will 226 The Ra isotope sample is wrapped in the middle; the nickel protective shell wraps the nickel electroplating layer. 226 Ra isotope targets can be used in electron linear accelerators as a photonuclear reaction production 225 Ac raw material target, can improve 225 Production of Ac isotopes.

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.

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.

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.

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 uranium-radium balance correction method, device, medium and equipment, and relates to the field of sandstone type uranium mine uranium exploration, and the method comprises the steps: obtaining an industrial uranium mine hole, carrying out the geophysical logging of the industrial uranium mine hole, determining a mineralized section through quantitative gamma interpretation, and carrying out the geological logging and geophysical exploration logging of a rock core, uranium and radium samples are collected and analyzed in the mineralization section; uranium fission instant neutron logging is carried out on the mineralization section, and the uranium ore section depth range is determined according to the ratio of the epithermal neutron time spectrum to the thermal neutron time spectrum of uranium fission instant neutron logging; according to the uranium radium sample analysis result of the mineralization section, determining a single sample section uranium radium balance coefficient, and according to the single sample section uranium radium balance coefficient, determining a single engineering uranium radium balance coefficient; determining a uranium radium balance coefficient partition map according to the single-project uranium radium balance coefficient; and correcting the quantitative gamma logging curve in the uranium ore section depth range of uranium instantaneous neutron logging by utilizing the coefficients in different uranium-radium balance regions to obtain the actual depth range, thickness and grade of the uranium ore section.

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.

Systems and methods are provided for separation of gypsum and / or rare earth elements and yttrium from phosphogypsum. Gypsum can be extracted from the phosphogypsum by dissolution with a basic aqueous medium that can include salinity, followed by reprecipitation of the calcium sulfate dihydrate (gypsum) and optional recycling of the solvent. A further extraction, of rare earth elements and yttrium, can be performed on the intermediate residue from the gypsum extraction step. The further extraction can be done by using one or more acidic, aqueous media on the intermediate residue, leaving a final residue that contains most or all of the radium that was present in the initial phosphogypsum. Optionally, the radium can be extracted from the residue for medical isotopes.

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.

The invention discloses a plasma excitation and maintenance device based on alpha decay ray auxiliary ionization, and belongs to the technical field of plasmas, the plasma excitation and maintenance device comprises a plasma excitation tube, a plasma excitation coil and a plasma detection device, one end of the plasma excitation tube is connected with working gas, the other end of the plasma excitation tube is open, and the open end is a plasma energy injection end; a radioactive substance is embedded in the inner wall of the plasma excitation tube or the air inlet end of the plasma excitation tube, the radioactive substance is one or a combination of more of americium, plutonium and radium, the radiation intensity of the radioactive substance is 0.1-2000 / mu Ci, the open end of the plasma excitation tube is a gradually-shrunk nozzle, and the diameter of the gradually-shrunk nozzle is 10-20 micrometers. And gas in the plasma excitation tube is ionized by utilizing high-energy rays generated by decay, so that the functions of auxiliary excitation and plasma maintenance are achieved.

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.

The invention belongs to the technical field of sandstone-type uranium ore geological exploration, and particularly relates to a sandstone-type uranium ore interlayer oxidation zone front line detection method, which comprises the following steps of: firstly, preliminarily drawing an interlayer oxidation zone front line based on the oxide condition of rock, and then correcting the interlayer oxidation zone front line twice according to the radiation quantity analysis of a sample and a uranium radium balance coefficient, compared with an existing uranium mine interlayer oxidation zone front line detection method, the method has the advantages that the interlayer oxidation zone front line can be efficiently and rapidly detected, and the time cost and the capital cost are saved.

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.