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Matches 51 - 100 out of 1,204

Document Document Title
WO/2013/066957A1
In a preferred embodiment, a process for extracting uranium from wet-process phosphoric acid (WPA), comprises separating uranium from WPA to produce a loaded uranium solution stream and a uranium depleted WPA stream. The loaded uranium s...  
WO/2013/040694A1
A process for upgrading tantalum and niobium ores and concentrates is described herein. The process comprising: a) submitting the ore or concentrate to a caustic fusion or an alkali fusion using a melt comprising at least one salt of an ...  
WO/2013/011100A1
The invention relates to a process and a device for bringing two immiscible liquids into contact, without mixing and at high temperature, with heating and brazing by induction. In particular, the invention relates to a process and a devi...  
WO/2012/156894A3
The invention discloses a metal extraction process and arrangement therefore which includes a microfiltration plant for removing suspended solids from a pregnant leach solution including a metal to form a first retentate including the so...  
WO/2012/150984A2
Provided are methods using a ketoxime in metal extraction. One aspect of the invention relates to a method for the recovery of metal from a metal-containing aqueous solution at an elevated temperature using a ketoxime. Another aspect rel...  
WO/2012/150984A3
Provided are methods using a ketoxime in metal extraction. One aspect of the invention relates to a method for the recovery of metal from a metal-containing aqueous solution at an elevated temperature using a ketoxime. Another aspect rel...  
WO/2012/130902A1
The invention relates to novel compounds which are useful as actinide ligands and which have the following general formula (I). The invention further relates to a method for synthesizing said compounds as well as to the uses thereof.  
WO/2012/109705A1
The invention discloses a method for recovering uranium from an acidic leach solution or leach pulp in salt water using an amino-phosphorus resin, wherein the liquid phase of the leach solution or leach pulp contains greater than 3 g/L c...  
WO/2012/093170A1
The main subject-matter of the present invention is a process for the dissolution of at least one element chosen from niobium and tantalum and at least one other element chosen from uranium and the rare earth elements, advantageously for...  
WO/2012/089684A3
The invention relates to a powder of a metastable γ phase uranium- and molybdenum-based alloy, which is formed by particles having an elongation index at least equal to 1.1 and a non-zero closed porosity value and comprising grains havi...  
WO/2012/089684A2
The invention relates to a powder of a metastable γ phase uranium- and molybdenum-based alloy, which is formed by particles having an elongation index at least equal to 1.1 and a non-zero closed porosity value and comprising grains havi...  
WO/2012/084740A1
The invention relates to a method for converting UO3 and/or U3O8 into hydrated UO4 having the formula UO4, nH2O, where n is 2 or 4, including the following consecutive steps: a) preparing an aqueous suspension of a UO3 powder and/or a U3...  
WO/2012/087400A1
Modular cathode assemblies (300) are useable in electrolytic reduction systems and include a basket (310) through which fluid electrolyte may pass and exchange charge with a material to be reduced in the basket. The basket can be divided...  
WO/2012/069573A1
The present invention relates to a process that makes it possible to separate the americium present in an acidic aqueous phase or in an organic phase from other metallic elements that are also found in this phase, by complexing the ameri...  
WO/2011/161650A1
This invention relates to a froth flotation process to beneficiate uranium economically from both low grade tailings dump ores or high grade ores; by upgrading into a concentrate. The first stage is a sulphide flotation for pyrite recove...  
WO/2011/147871A1
The invention relates to a method for treating spent nuclear fuel which, among other advantages, does not require the operation of reductive back-extraction of plutonium. Said method can be used in particular in the treatment of uranium ...  
WO/2011/144937A1
The invention provides a process for the reprocessing of spent nuclear fuel, the process comprising the steps of: (a) electrorefining the metal to produce a liquid metal cathode comprising the liquid metal alloyed with actinide or fissio...  
WO/2011/132138A1
This invention relates to the integration of ammonium carbonate leach processes with established acid and alkaline uranium leach processes as multifunctional industrial processes for the extraction, high degree purification and conversio...  
WO/2011/116426A1
A process for leaching uranium from a refractory uraniferous mineral including the step of treating a slurry containing said uraniferous mineral and ferrous ions in a reactor with an acid and an oxidant to increase the ORP in the reactor...  
WO/2011/098979A3
The invention relates to novel algae of the Coccomyxa genus, in particular the algae of a novel species called Coccomyxa actinabiotis, and to the use thereof for metal uptake from aqueous media, and in particular from radioactive media.  
WO/2011/098979A2
The invention relates to novel algae of the Coccomyxa genus, in particular the algae of a novel species called Coccomyxa actinabiotis, and to the use thereof for metal uptake from aqueous media, and in particular from radioactive media.  
WO/2011/095679A1
The invention relates to a method for the selective recovery of uranium from a sulphate-based acidic aqueous solution of uranium containing iron and other metals by means of solvent extraction, in which the extractant used in the organic...  
WO/2011/082454A1
The present invention provides a process for the production of a uranium trioxide yellowcake from a uranium peroxide precipitate, the peroxide precipitate being in the form of a low solids content, uranium rich feed slurry, the process i...  
WO/2011/076739A1
The invention relates to a method making it possible to purify the uranium from a natural uranium concentrate. Said method includes: a) extracting the uranium, present in the form of uranyl nitrate, in an aqueous phase A1 resulting from ...  
WO/2011/067271A1
The invention relates to a method for chemically decontaminating the surface of a metal component of the primary circuit of a pressurized-water reactor, said surface comprising an oxide layer. The method is divided into two process stage...  
WO/2011/012579A1
The invention relates to the use of a diglycolamide to increase the separation factor between americium and curium and/or between lanthanides during an extraction operation including contacting an acidic aqueous phase, which contains ame...  
WO/2011/012563A1
The invention relates to a method for selectively recovering americium from an aqueous nitric phase containing americium, curium, and fission products including lanthanides and yttrium, but free of uranium, plutonium and neptunium, or wh...  
WO/2011/009814A1
The invention relates to novel compounds that can be used as actinide ligands, to the synthesis of said compounds and to the uses thereof. Said compounds have the following general formula (I): (formula I) in which R1 and R2, identical o...  
WO/2011/006974A1
The invention relates to a method for extracting at least one chemical element contained in a molten salt medium, comprising the following steps: a) a step consisting in bringing the molten salt medium containing the chemical element int...  
WO/2010/014562A2
A process for the extraction of uranium compounds from wet-process phosphoric acid includes lowering the iron concentration of the wet-process phosphoric acid and reducing the valency of any remaining ferric iron in the wet-process phosp...  
WO/2010/014745A2
Systems for treating material are provided that can include a vessel defining a volume, at least one conduit coupled to the vessel and in fluid communication with the vessel, material within the vessel, and N F3 material within the condu...  
WO/2010/014745A3
Systems for treating material are provided that can include a vessel defining a volume, at least one conduit coupled to the vessel and in fluid communication with the vessel, material within the vessel, and N F3 material within the condu...  
WO/2010/014562A3
A process for the extraction of uranium compounds from wet-process phosphoric acid includes lowering the iron concentration of the wet-process phosphoric acid and reducing the valency of any remaining ferric iron in the wet-process phosp...  
WO/2009/120373A2
A process and composition for extracting metal from a metal-laden ore, soil or rock is provided A liquid, three-component aqueous lixiviant comprises water, an alkali metal salt and a low pH acidic composition A four-component aqueous li...  
WO/2009/013759A1
A process for refining yellowcake to produce nuclear grade uranium using a single step precipitation route for the simultaneous removal of heavy metals, boron and other rare earth metals comprising dissolving the yellowcake in nitric aci...  
WO/2008/101296A1
A process for the drying of yellowcake, the yellowcake initially being in the form of a low solids content, uranium rich feed slurry, the process including the stages of : a. dewatering the feed slurry to produce a first dewatered solids...  
WO/2008/070195A2
A product includes actinium-225 (225Ac) and less than about 1 microgram (μg) of iron (Fe) per millicurie (mCi) of actinium-225. The product may have a radioisotopic purity of greater than about 99.99 atomic percent (at%) actinium-225 an...  
WO/2008/049807A1
The present invention relates to a method for separating together all the actinides (III), (IV), (V) and (VI) present in a highly acidic aqueous phase from the fission products, especially lanthanides, also present in said phase using a ...  
WO/2008/028664A1
The present application is directed to a method for the purification of Radium, in particular 226Ra1 for target preparation for an essentially pure 225Ac production from available radioactive sources, using an extraction chromatography i...  
WO/2008/003681A1
The invention relates to a method for very effectively separating a chemical element from uranium using an aqueous acid phase, in a uranium extraction cycle, when this chemical element is present in said phase with a concentration below ...  
WO/2007/123917A3
A system for combusting carbon-containing fuel includes a reactor 10 for simultaneously supporting oxidation of the fuel and conversion of CO2 within the reactor. A metal oxide or metal is input to the reactor to convert the CO2 to a min...  
WO/2007/096119A2
The present invention describes a method for purification of225Ac from irradiated 226Ra-targets provided on a support, comprising a leaching treatment of the 226Ra-targets for leaching essentially the entirety of 225Ac and 226Ra with nit...  
WO/2007/096119A3
The present invention describes a method for purification of225Ac from irradiated 226Ra-targets provided on a support, comprising a leaching treatment of the 226Ra-targets for leaching essentially the entirety of 225Ac and 226Ra with nit...  
WO/2007/085659A1
The invention relates to a method of separating, in an aqueous medium, at least one actinide element from one or more lanthanide elements, and employing at least one molecule which complexes the said actinide element to be separated, and...  
WO/2007/084116A3
Embodiments of a method and a system for recovering a metal, such as uranium, from a metal-containing material are disclosed. The metal-containing material is exposed to an extractant containing a liquid or supercritical-fluid solvent an...  
WO/2006/136948A2
The invention relates to a process for the chemical benef iciation of raw material containing tantalum-niobium such as wastes, scoria, concentrates and ores. The process comprises the step of decomposing the raw material with a carbonate...  
WO/2006/136948A3
The invention relates to a process for the chemical benef iciation of raw material containing tantalum-niobium such as wastes, scoria, concentrates and ores. The process comprises the step of decomposing the raw material with a carbonate...  
WO/2006/123051A3
The invention relates to novel p-tert-butylcalix[6]arenes of formulae (IA) and (IB) with carboxylic or hydroxyamino triacidic functions in positions 2,4 and 6, and other functions in positions 1, 3 and 5, supported liquid membranes and s...  
WO2006007265A3
An apparatus and method to remove uranium from a body of material wherein the method includes the steps of depositing the body of solid material in an ultrasonic extractor and depositing an amount of acid in the ultrasonic extractor. The...  
WO2006016892A3
A mixed extractant solvent including calix[4]arene-bis-(tert-octylbenzo)-crown-6 ("BOBCalixC6"), 4',4',(5')-di-(t-butyldicyclo-hexano)-18-crown-6 ("DtBul8C6"), and at least one modifier dissolved in a diluent. The mixed extractant solven...  

Matches 51 - 100 out of 1,204