16results about "Radium compounds" patented technology

The invention provides an ultra-pure thorium fluoride production process which comprises the following steps: preparing a nanoscale ThF4.xNH4F precursor through a gas-liquid-solid three-phase reaction, atomizing an ammonium fluoride solution into microdroplets by adopting ultrasonic atomization, and carrying out synergistic reaction with gaseous ammonium fluoride and a liquid-phase thorium nitrate solution; a microwave-plasma synergistic fluorination reaction is adopted, and the precursor is heated in a high-purity inert atmosphere to generate crude thorium fluoride; according to the ultra-pure thorium fluoride production process provided by the invention, the purity of thorium fluoride is remarkably improved through the technical means of preparation of a nanoscale precursor through a gas-liquid-solid three-phase reaction, microwave-plasma synergistic fluorination, multi-stage sublimation combined with graphene-based nano trapping membrane purification, intelligent process control, by-product closed-loop recovery and the like; the impurity content is low, and the requirements of nuclear reactor fuel substrates and high-end optical coatings on ultra-high purity are met. The method has the advantages of high yield, high process stability and small purity fluctuation among batches, and the production efficiency and the product consistency are obviously improved.

A method and system (300) for separating thorium from uranium and its decay products is provided. The method includes combining a nuclear fuel feedstock (102) containing thorium and uranium with a first acid (104, 204) to form a first solution. The first solution is contacted with an ion exchange resin (308) that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin (308), thereby forming a second solution (106, 206). The second solution (106, 206) is combined with oxalic acid to precipitate the uranium or thorium from the second solution, forming a precipitate (110, 210). The precipitate (110, 210) is separated from the second solution (106, 206).

The present disclosure provides a simple and versatile process suitable for large-scale production of alpha emitters. It does not require irradiation of the source material and it is based on aqueous solutions and a strong cation exchange resin.

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 present invention relates to a process for synthesizing actinide chloride(s) from actinide oxide(s) present in a molten salt, said process employing an aluminum (I) salt, a silicon (II) salt, and / or a beryllium (III) salt, and at least one chloride salt of an alkali and / or alkaline earth metal. The present invention also relates to the use of an aluminum (I) salt, a silicon (II) salt, and / or a beryllium (III) salt, for example, aluminum chloride AlCl3, for the synthesis of actinide chloride(s) from actinide oxide(s) in a molten salt fuel for molten salt nuclear fission reactors (MSFs).

A small-scale portable and transportable thorium LFTR (Liquid Fluoride Thorium Reactor) in the form of a molten salt reactor for use in clean power generation. The LFTR will serve as a modular design for stand alone, potential off-grid, or in addition to supporting power baseload as a primary, auxiliary and / or alternative energy power source.

The invention provides a method for separating and recovering useful components in rare earth production radioactive wastewater, and relates to the technical field of chemical separation. The method comprises the following steps: adding oxalic acid, controlling the pH value, filtering, dropwise adding sulfuric acid into the filtrate, stirring and precipitating at the set pH value, filtering to obtain filtrate I and calcium sulfate dihydrate whiskers, and heating and dehydrating to obtain anhydrous calcium sulfate whiskers; adding a NaOH solution into the filtrate I, controlling the pH value, and filtering to obtain thorium hydroxide and filtrate II; and adding sulfuric acid into the filtrate II to form acidified waste liquid, and adding resin or aerogel to adsorb and separate uranium. Through the procedures of fractional precipitation, hydrolysis, roasting, acidification, adsorption, elution, denitration reduction and the like, useful components Ca < 2 + >, U6 < + > and Th < 4 + > in the wastewater are effectively separated, and high-value products of calcium sulfate whiskers, thorium oxide and uranium oxide are obtained.

The invitation pertains to a process for the manufacturing of anhydrous thorium(IV) chloride comprising the steps of providing a thorium compound comprising a thorium (IV) cation, contacting the compound of (a) with an organic chlorinating agent; and isolating the anhydrous thorium(IV) chloride. The thorium compound may be a thorium oxalate prepared from a soluble thorium salt.

The invention discloses a preparation method of a high-purity metal thorium target material, and belongs to the technical field of purification and preparation of metal thorium. The crude metal thorium is placed in an iodination furnace, the iodination furnace is vacuumized, a low-temperature area and a high-temperature area are adjusted to the set temperature, iodine vapor is input for iodination, thorium is crystallized on a flat belt mother wire, the K value of the flat belt mother wire is adjusted along with the iodination reaction, the crystallized thorium is taken out after the reaction is finished, and the high-purity metal thorium is obtained; and the high-purity metal thorium is rolled and machined to obtain the metal thorium target material. According to the method, the crude metal thorium raw material is purified by adopting an iodination method and cooperating with the flat belt mother wire and corresponding temperature control, so that the content of non-metal impurities and oxide impurities in the metal thorium is effectively reduced, the metal thorium target material which is relatively low in hardness, good in forgeability and moderate in size is obtained, and subsequent preparation of a metal thorium sheet is facilitated; and meanwhile, thorium scraps and other materials in the manufacturing and machining process of the metal target sheet are recycled, the process is simple, and economic benefits are achieved.

The invention relates to a method for solidifying an aqueous solution of thorium nitrate Th(NO3)4, which method comprises the steps of: a) concentrating the aqueous solution by circulating the aqueous solution in an evaporator comprising an inlet for feeding the aqueous solution into the evaporator and an outlet for discharging the aqueous solution from the evaporator, wherein a temperature gradient prevails from a temperature θ1 of between 50°C and 70°C at the inlet of the evaporator to a temperature θ2 of between 130°C and 160°C at the outlet of the evaporator, whereby a concentration gradient of the aqueous solution is established between the inlet and the outlet of the evaporator, the establishment of the concentration gradient leading to a concentrated aqueous solution of thorium nitrate pentahydrate of formula Th(NO3)4.5H2O at the outlet of the evaporator; then b) transferring the thus-concentrated aqueous solution from the outlet of the evaporator to a container in which the aqueous solution is left to cool, whereby the aqueous solution solidifies in the container by crystallization of thorium nitrate pentahydrate. The invention can be used for the storage of aqueous solutions of thorium nitrate in solid form pending subsequent recovery of these solutions.

The present invention relates to a method for the preparation of mixed rare earth metal carbonates from monazite, this method comprising a first leaching with an alkaline hydroxide and a two-step second leaching in the presence of hydrochloric acid.

The present invention relates to a method for the synthesis of actinide chloride(s) from actinide oxide(s) present in a molten salt, the method using an aluminium(I) salt, a silicon(II) salt and / or a beryllium(III) salt, and optionally at least one chloride salt of an alkali and / or alkaline-earth metal. The present invention also relates to the use of an aluminium(I) salt, a silicon(II) salt and / or a beryllium(III) salt, for example aluminium chloride AlCl3, for the synthesis of actinide chloride(s) from actinide oxide(s) in a molten fuel salt for molten salt nuclear fission reactors (MSR).

The present invention relates to a process for the production of a metal or an alloy comprising the metal from a metal precursor. The process comprises reacting the metal precursor with a reducing agent in a self-sustaining exothermic reaction and separating the metal or the alloy comprising the metal from a slag produced during the reaction. The invention also relates to the use of an intermetallic compound defined by the chemical formula Ca8(Al 3‑x M x ) as a reducing agent in the reduction of a metal precursor to produce a metal or a metal alloy.

The invention relates to a process for solidifying an aqueous solution of thorium nitrate Th(NO3)4, which comprises the steps of: a) concentrating the aqueous solution by circulation in an evaporator comprising an inlet for supplying it with aqueous solution, an outlet for removing the aqueous solution from the evaporator, and in which there exists a temperature gradient from a temperature θ1 between 50 °C and 70 °C at the inlet of the evaporator to a temperature θ2 between 130 °C and 160 °C at the outlet of the evaporator, thereby establishing a concentration gradient of the aqueous solution between the inlet and outlet of the evaporator, leading to a concentrated aqueous solution of thorium nitrate pentahydrate of formula Th(NO3)4.5H2O at the evaporator outlet; then b) transfer of the concentrated aqueous solution from the evaporator outlet to a container where the aqueous solution is allowed to cool, whereby the aqueous solution solidifies in the container through crystallization of thorium nitrate pentahydrate. Applications: storage of aqueous thorium nitrate solutions in solid form pending further use of these solutions.

Methods and systems (300) for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock (102) comprising thorium and uranium with a first acid (104, 204) to form a first solution. The first solution is contacted an ion exchange resin (308) that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin (308) thereby forming a second solution (106 206). The second solution (106, 206) is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate (110, 210). The precipitate (110, 210) is separated from the second solution (106, 206).