12results about "Radium compounds" patented technology

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).

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 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).