10 results about "Radium" patented technology

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.

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 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.

Liquid is irradiated in irradiation device (2) by protons, deuterium nuclei or gamma rays. 226 The radium target, and the resulting product extracted from the irradiated liquid target solution in the first extraction device (6). 225 Origin of A 226 Radium production 225 Actinium. Then, after another irradiation, it was removed. 225 Actinium liquid target solution for further production 225 Actinium. The liquid target solution is preferably circulated through the irradiation device in a closed loop (4) and through the first extraction device (6) in another closed loop (7). The advantage of this method is that the irradiated target solution does not require drying and redissolving to separate radium from the produced actinium, and no further drying and redissolving steps are needed to regenerate the liquid target from the separated radium. Therefore, radium targets can be recovered more efficiently and safely, especially considering the effects of... 226 Radon gas is continuously produced by the decay of radium.

The invention relates to a process for producing medical-grade lead-212, comprising the steps of: a) production of lead-212 by radioactive decay of radium-224 in at least one first chromatography column containing a first stationary phase on which radium-224 is fixed; b) elution of the lead-212 thus produced from the first stationary phase; c) loading of the eluate thus obtained into a second chromatography column containing a second stationary phase to fix the lead-212 on the second stationary phase; d) washing of the second stationary phase; d) elution of the lead-212 from the second stationary phase; and characterized in that: - step b) comprises circulating in said at least one first chromatography column an ​​aqueous solution A1 comprising from 0.8 mol / L to 1.6 mol / L of a chloride, optionally with at most 200 mmol / L of HCl;and- step d) includes circulating an aqueous solution A2 comprising 0.01 mol / L to 1 mol / L of chloride through the second chromatography column. Applications: manufacture of lead-212 based radiopharmaceuticals, useful in nuclear medicine.

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.

METHOD FOR RECOVERING AN ARSENIC-ENRICHED CONCENTRATE FROM RADIOLOGICALLY CONTAMINATED ORE The present invention relates to a method for recovering a concentrate enriched in arsenic and other possible metals from a uranium-bearing ore containing radium and arsenic, by flotation. Figure for the abstract: None

The present invention provides a method for separating lead radioisotopes from a mixture comprising lead radioisotopes and radium or thorium radioisotopes, and a system comprising a plurality of chromatography columns. The system can comprise a first cartridge column having a lead complexing medium that preferentially binds lead radioisotopes over radium or thorium radioisotopes; and a second cartridge column having a weak cation exchange medium, wherein the pH of a loading solution used to load the second cartridge column is pH 2L , the pH of an eluent used to elute lead radioisotopes from the second cartridge column is pH 2E , and the pH 2L is greater than pH 2E . The system can further comprise a third cartridge column and a fourth cartridge column having chromatographic media to extract and purify 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.

This invention discloses a method for extracting radium from uranium ore leaching solution, comprising: obtaining a pre-adsorbent material and a main adsorbent material based on macroporous adsorption resin; filling the pre-adsorbent material into a pre-chromatographic column; filling the main adsorbent material into a main chromatographic column; connecting the pre-adsorbent column and the main chromatographic column in series; pumping the uranium ore leaching solution into the series-connected columns at a preset flow rate; adsorbing thorium, radium, and lead elements in the feed solution; eluting the main chromatographic column with nitric acid solution; eluting the main chromatographic column stepwise with hydrochloric acid solution; collecting the eluent to obtain a radium-enriched eluent; and leaving a lead-enriched resin phase on the main chromatographic column. This method utilizes the tandem connection of two columns, acid gradient elution, and the synergistic coordination effect of crown ether ionic liquids to enhance the specific recognition and coordination ability of lead ions in the hydrochloric acid system, improve the selective separation efficiency of radium and lead, reduce usage costs, increase the extraction purity and recovery rate of radium, and reduce the amount of radioactive waste generated.

The present invention relates to a method for recovering a concentrate enriched with arsenic and other optional metals from a uranium-bearing ore comprising radium and arsenic, by flotation.