Abstract: Described are methods for the recovery of uranium from uranium hexafluoride dissolved directly into ionic liquids.

Abstract: Described are methods for the recovery of uranium from uranium hexafluoride dissolved directly into ionic liquids.

Abstract: Described are methods for the recovery of uranium from uranium hexafluoride dissolved directly into ionic liquids.

Abstract: Described are methods for the recovery of uranium from uranium hexafluoride dissolved directly into ionic liquids.

Abstract: A process for recovering a rare earth element. The process includes adding water and a nonaqueous acid to an ionic liquid, and dissolving an oxide of a first rare earth element directly into the ionic liquid to form an ionic solution comprising at least about 0.1 weight percent water, the acid and an ion of the first rare earth element. The process further includes applying a potential to the ionic solution to deposit the first rare earth element onto an electrode as a metal.

Abstract: This document provides a dual flask for laboratory use, methods of using a dual flask, and systems including a dual flask. A dual flask can include a first flask structure and a second flask structure. Each flask structure can include a body and a neck. The first body and the second body in a dual flask provided herein can be connected together and have a filter there between such that fluids can be filtered between said first and second bodies.

Abstract: A process for recovering a rare earth element. The process includes adding water and a nonaqueous acid to an ionic liquid, and dissolving an oxide of a first rare earth element directly into the ionic liquid to form an ionic solution comprising at least about 0.1 weight percent water, the acid and an ion of the first rare earth element. The process further includes applying a potential to the ionic solution to deposit the first rare earth element onto an electrode as a metal.

Abstract: Uranic and transuranic metals and metal oxides are first dissolved in ozone compositions. The resulting solution in ozone can be further dissolved in ionic liquids to form a second solution. The metals in the second solution are then electrochemically deposited from the second solutions as room temperature ionic liquid (RTIL), tri-methyl-n-butyl ammonium n-bis(trifluoromethansulfonylimide) [Me3NnBu][TFSI] providing an alternative non-aqueous system for the extraction and reclamation of actinides from reprocessed fuel materials. Deposition of U metal is achieved using TFSI complexes of U(III) and U(IV) containing the anion common to the RTIL. TFSI complexes of uranium were produced to ensure solubility of the species in the ionic liquid. The methods provide a first measure of the thermodynamic properties of U metal deposition using Uranium complexes with different oxidation states from RTIL solution at room temperature.

Abstract: This document provides a dual flask for laboratory use, methods of using a dual flask, and systems including a dual flask. A dual flask can include a first flask structure and a second flask structure. Each flask structure can include a body and a neck. The first body and the second body in a dual flask provided herein can be connected together and have a filter there between such that fluids can be filtered between said first and second bodies.

Abstract: Uranium metal can be electrochemical deposited from room temperature ionic liquid (RTIL), tri-methyl-n-butyl ammonium n-bis(trifluoromethansulfonylimide) [Me3NnBu][TFSI] providing an alternative non-aqueous system for the extraction and reclamation of actinides from reprocessed fuel materials. Deposition of U metal is achieved using TFSI complexes of U(III) and U(IV) containing the anion common to the RTIL. TFSI complexes of uranium were produced to ensure solubility of the species in the ionic liquid. The methods provide a first measure of the thermodynamic properties of U metal deposition using Uranium complexes with different oxidation states from RTIL solution at room temperature.

Abstract: A spent fuel reprocessing method contacts an aqueous solution containing Technetium(V) and uranyl with an acidic solution comprising hydroxylamine hydrochloride or acetohydroxamic acid to reduce Tc(V) to Tc(II, and then extracts the uranyl with an organic phase, leaving technetium(II) in aqueous solution.

Abstract: A spent fuel reprocessing method contacts an aqueous solution containing Technetium(V) and uranyl with an acidic solution comprising hydroxylamine hydrochloride or acetohydroxamic acid to reduce Tc(V) to Tc(II, and then extracts the uranyl with an organic phase, leaving technetium(II) in aqueous solution.

Abstract: A method of preparing an actinide nitride fuel for nuclear reactors is provided. The method comprises the steps of a) providing at least one actinide oxide and optionally zirconium oxide; b) mixing the oxide with a source of hydrogen fluoride for a period of time and at a temperature sufficient to convert the oxide to a fluoride salt; c) heating the fluoride salt to remove water; d) heating the fluoride salt in a nitrogen atmosphere for a period of time and at a temperature sufficient to convert the fluorides to nitrides; and e) heating the nitrides under vacuum and/or inert atmosphere for a period of time sufficient to convert the nitrides to mononitrides.

Abstract: The present invention provides methods for separating isotopes of actinide elements such as uranium using microorganisms, e.g., metal or sulfate reducing bacteria. The microorganisms reduce the actinide element to form a precipitate, which contains a greater proportion of the lighter isotope relative to the heavier isotope than the starting material. The precipitate may be collected, re-oxidized, and subjected to multiple rounds of enrichment. Alternately, separation processes not requiring formation of a precipitate may be used. The invention also features cell-free systems for isotope separation. The invention further provides compositions produced according to the foregoing methods, including compositions comprising enriched uraninite.

Abstract: The present invention provides methods for separating isotopes of actinide elements such as uranium using microorganisms, e.g., metal or sulfate reducing bacteria. The microorganisms reduce the actinide element to form a precipitate, which contains a greater proportion of the lighter isotope relative to the heavier isotope than the starting material. The precipitate may be collected, re-oxidized, and subjected to multiple rounds of enrichment. Alternately, separation processes not requiring formation of a precipitate may be used. The invention also features cell-free systems for isotope separation.