| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 423249000 | RADIOACTIVE (AT. NO. 84+ OR RADIOACTIVE ISOTOPE OF ANOTHER ELEMENT) | 39 |
| 20080226528 | FUSION PROCESS USING AN ALKALI METAL METALATE - The product of a molten alkali metal metalate phase separation can be processed into a purified metal from a metal source. Metal sources include native ores, recycled metal, metal alloys, impure metal stock, recycle materials, etc. The method uses a molten alkali metal metalate as a process medium or solvent in purifying or extracting high value metal or metal oxides from metal sources. Vitrification methods using the silicate glass separation phase can be prepared as is or can be prepared with a particulate phase distributed throughout the silica glass phase and encapsulated and fixed within the continuous glass phase. Tungsten metal can be obtained from an alkali metal tungstate. A typically finely divided tungsten metal powder can be obtained from a variety of tungsten sources including recycled tungsten scrap, tungsten carbide scrap, low grade tungsten ore typically comprising tungsten oxide or other form of tungsten in a variety of oxidation states. | 09-18-2008 |
| 20090035201 | PREPARATION METHOD OF TC-99M-LABELED IRON OXIDE NANOPARTICLE AND DIAGNOSTIC IMAGING OR THERAPEUTIC AGENT FOR CANCER DISEASES COMPRISING THE SAME - Disclosed herein are a method of preparing a technetium-99m-labeled iron oxide (Fe | 02-05-2009 |
| 20090060812 | MEDICAL RADIOISOTOPES AND METHODS FOR PRODUCING THE SAME - This disclosure concerns a new method for preparing radioisotopes, such as molybdenum-99, by alpha particle irradiation, such as by alpha particle irradiation of zirconium-96. Molybdenum-99 is a precursor to the medically-significant radioisotope technetium-99m. Also disclosed are novel compositions containing one or more of technetium-99m, molybdenum-99 and zirconium species. Systems for producing molybdenum-99 and technetium-99m, including alpha particle generators and irradiation targets, also are described. | 03-05-2009 |
| 20090252666 | FLUORIDE DRYING METHOD - The invention relates to methods and apparatus for drying [ | 10-08-2009 |
| 20090274603 | NON-AQUEOUS EXTRACTION OF [18F] FLUORIDE FROM CYCLOTRON TARGETS - The present invention provides a method and an apparatus for extracting an isotope from a gas. More specifically, the present invention depicts a system that has been devised which provides [ | 11-05-2009 |
| 20090311157 | NUCLEOPHILIC RADIOFLUORINATION USING MICROFABRICATED DEVICES - A microscale solution for conducting [ | 12-17-2009 |
| 20100028234 | Methods for making and processing metal targets for producing Cu-67 radioisotope for medical applications - The present invention provides a method for producing Cu67 radioisotope suitable for use in medical applications. The method comprises irradiating a metallic zinc-68 (Zn68) target with a high energy gamma ray beam. After irradiation, the Cu67 is isolated from the Zn68 by any suitable method (e.g., chemical and/or physical separation). In a preferred embodiment, the Cu67 is isolated by sublimation of the zinc (e.g., at about 500-700° C. under reduced pressure) to afford a copper residue containing Cu67. The Cu67 can be further purified by chemical means (i.e., dissolution in acid, followed by ion exchange). | 02-04-2010 |
| 20100055016 | METHOD OF MANUFACTURING OXIDE-BASED NANO-STRUCTURED MATERIAL - Provided is a method of manufacturing oxide-based nano-structured materials using a chemical wet process, and thus, the method can be employed to manufacture oxide-based nano-structured materials having uniform composition and good electrical characteristics in large quantities, the method having a relatively simple process which does not use large growing equipment. The method includes preparing a first organic solution that comprises a metal, mixing the first organic solution with a second organic solution that contains hydroxyl radicals (—OH), filtering the mixed solution using a filter in order to extract oxide-based nano-structured materials formed in the mixed solution, drying the extracted oxide-based nano-structured materials to remove any remaining organic solution, and heat treating the dried oxide-based nano-structured materials. | 03-04-2010 |
| 20100239481 | PROCESS FOR TRITIUM REMOVAL FROM WATER BY TRANSFER OF TRITIUM FROM WATER TO AN ELEMENTAL HYDROGEN STREAM, FOLLOWED BY MEMBRANE DIFFUSION TRITIUM STRIPPING AND ENRICHMENT, AND FINAL TRITIUM ENRICHMENT BY THERMAL DIFFUSION - A diffusion based process for tritium removal from water by tritium transfer from water to an elemental hydrogen stream, followed by a membrane diffusion cascade for tritium stripping and enrichment, and final tritium enrichment by one or more thermal diffusion columns. The combination of process steps takes advantage of membrane diffusion's large throughput capability at low tritium concentration with the simplicity of thermal diffusion for small throughput final tritium enrichment. The membrane diffusion stages use supported or unsupported microporous or hydrogen permeable metal membranes (such as Pd/Ag alloy). The diffusion process is compatible with any front-end process to transfer tritium from tritiated water to elemental hydrogen. The process may be designed and operated at low pressure, with small gas inventory, and no inherent overpressure hazard. | 09-23-2010 |
| 20110020206 | ADSORBENT, PREPARATION METHOD THEREOF AND SR-90/Y-90 GENERATOR USING THE SAME - Disclosed herein is an radioisotope adsorbent including a bifunctional organosilane compound, including an organosiloxane functional group and a phosphate group, bonded on the surface of silica which is a bone structure of the adsorbent, and a method of preparing the radioisotope adsorbent, and a strontium/yttrium generator using the radioisotope adsorbent. Since the radioisotope adsorbent has a high adsorption capacity for | 01-27-2011 |
| 20110305618 | METHOD FOR SYNTHESIS OF A RADIONUCLIDE-LABELED COMPOUND USING AN EXCHANGE RESIN - The invention pertains to a method for eluting a radionuclide-label or a radionuclide-labeled compound using a solid phase extraction resin, to a device for performing such a method, and to a computer program for controlling such a device. | 12-15-2011 |
| 20120003135 | WATER TREATMENT - Methods of treating water, methods of removing radium from water, methods for controlling the amount of at least one target element removed from water and the amount of at least one target element in a pellet, a pellet and treated water. The method may generally include providing water including a principal ion and a target element, contacting the water with a fluidized bed, the fluidized bed including seed material, and controlling at least one of a type and a size of the seed material to remove principal ion and target element from the water. The target element may include radium. The principal ion may include calcium, magnesium, etc. A pellet may include a seed material, radium carbonate crystals, and calcium carbonate crystals | 01-05-2012 |
| 20120244055 | Adsorbents for Radioisotopes, Preparation Method Thereof, and Radioisotope Generators Using the Same - Disclosed is a novel adsorbent for use in a | 09-27-2012 |
| 20130022525 | METHODS AND COMPOSITIONS FOR DRYING IN THE PREPARATION OF RADIOPHARMACEUTICALS - A method of drying a radioisotope solution having radioisotopes includes passing the radioisotope solution through a solid phase extraction column containing an anion exchange group, thereby trapping the radioisotopes in the column. The method also includes passing an eluent through the column, thereby removing the radioisotopes from the column. The eluent includes a cation trapping agent/salt complex, less than 4% water, and the remainder is a solvent. A method of producing the eluent includes reacting a cation trapping agent with a salt in the presence of less than 4% water and a solvent to form solubilized cation trapping agent/salt complex, wherein one of the cation trapping agent and the salt is present in en excess of a stoichiometric amount and ending the reaction when a predetermined amount of solubilized cation trapping agent/salt complex has been formed. | 01-24-2013 |
| 20130045151 | C-11 Cyanide Production System - A method for providing | 02-21-2013 |
| 20130115156 | PROCESS FOR THE DETRITIATION OF SOFT HOUSEKEEPING WASTE AND PLANT THEREOF - A process for removal of tritium from materials that are contaminated thereby envisages the use of a detritiation reactor RT, in which the reaction for the removal of tritium from the waste takes place, the waste being recovered by a flow of moist inert gas in which an extremely low percentage of humidity is used. The heated waste releases a current of tritiated gases, the current of gases being removed from the reactor via the moist inert gas, which conveys it into a membrane reactor RM for decontamination. The membrane reactor, in fact, is able to remove selectively the tritium present in the mixture of gases: there is thus the dual advantage of purifying the mixture of gases and of recovering the tritium contained therein. | 05-09-2013 |
| 20130302236 | GAMMA RADIATION SOURCE - A gamma radiation source comprises | 11-14-2013 |
| 20130336870 | Advanced Tritium System for Separation of Tritium from Radioactive Wastes and Reactor Water in Light Water Systems - Systems, methods, and processes for a high throughput, low concentration processing of low activity tritiated light water include the electrolysis of at least some of the tritiated water to produce hydrogen and tritium gas. The hydrogen and tritium gas produced by electrolysis in some cases are combined with heated water vapor to increase throughput and passed through a liquid phase catalytic exchange column, which generally includes a catalyst that includes palladium coated with a hydrophobic polymer. As the hydrogen and tritium gas, along with heated water vapor, rise through the LPCE column, the tritium is retained on the catalyst. Deionized wash water passes down the column (i.e., in the opposite direction of the flow of the hydrogen gas and heated water vapor) and carries the retained tritium out of the LPCE column. Useful in separating tritium from radioactive waste materials and from the water from nuclear reactors. | 12-19-2013 |
| 20140065048 | CARBON NANOTUBE ARRAY - A carbon nanotube array suitable for use in labeling is provided. The carbon nanotube array includes at least two different isotope-doped carbon nanotube sub-arrays. Each isotope-doped carbon nanotube sub-array includes a plurality of carbon nanotubes. The carbon nanotubes in different isotope-doped carbon nanotube sub-arrays are composed of different kinds of carbon isotopes. | 03-06-2014 |
| 20140286846 | MESOPOROUS METAL OXIDES AND PROCESSES FOR PREPARATION THEREOF - A process for preparing a mesoporous metal oxide, i.e., transition metal oxide, Lanthanide metal oxide, a post-transition metal oxide and metalloid oxide. The process comprises providing a micellar solution comprising a metal precursor, an interface modifier, a hydrotropic ion precursor, and a surfactant; and heating the micellar solution at a temperature and for a period of time sufficient to form the mesoporous metal oxide. A mesoporous metal oxide prepared by the above process. A method of controlling nano-sized wall crystallinity and mesoporosity in mesoporous metal oxides. The method comprises providing a micellar solution comprising a metal precursor, an interface modifier, a hydrotropic ion precursor, and a surfactant; and heating the micellar solution at a temperature and for a period of time sufficient to control nano-sized wall crystallinity and mesoporosity in the mesoporous metal oxides. Mesoporous metal oxides and a method of tuning structural properties of mesoporous metal oxides. | 09-25-2014 |
| 20140356270 | BALANCED CLOSED LOOP CONTINUOUS EXTRACTION PROCESS FOR HYDROGEN ISOTOPES - A system and method for tritium separation systems using a mixed bed catalytic exchange process in a Liquid Phase Catalytic Exchange/Closed Loop Continuous Process (LPCE/CLCP) system, that operates as a low temperature and low pressure continuous balanced process, designed to rapidly, economically and safely extract and isolate isotope specific products without generating unwanted products in the form of new waste streams. | 12-04-2014 |
| 20150044117 | CAVITAND COMPOSITIONS AND METHODS OF USE THEREOF - Cavitand compositions that comprise void spaces are disclosed. The void spaces may be empty, which means that voids are free of guest molecules or atoms, or the void spaces may comprise guest molecules or atoms that are normally in their gas phase at standard temperature and pressure. These cavitands may be useful for industrial applications, such as the separation or storage of gasses. Novel cavitand compounds are also disclosed. | 02-12-2015 |
| 20150380119 | METHOD AND APPARATUS FOR SYNTHESIZING RADIOACTIVE TECHNETIUM-99M-CONTAINING SUBSTANCE - A method for synthesizing a radioactive technetium-99m-containing substance and a synthesizing device are provided. The method for synthesizing a radioactive technetium-99m-containing substance has a step for generating negative muons and a step for irradiating the negative muons onto a ruthenium sample. The ruthenium material preferably includes a metallic ruthenium and/or a ruthenium compound. Also, the ruthenium sample preferably has a plurality of superimposed ruthenium thin plates having a thickness of 4 mm or less. | 12-31-2015 |
| 20160053345 | PROCESS FOR ISOLATION AND PURIFICATION OF ASTATINE-211 - This disclosure relates to methods for purifying and isolating astatine-211 from bismuth metal. Also disclosed are automated methods for purifying and isolating astatine-211 from bismuth metal. | 02-25-2016 |
| 20160055928 | METHOD FOR PREPARATION OF ALPHA SOURCES OF POLONIUM USING SULFIDE MICRO-PRECIPITATION - A method for preparing alpha sources of polonium. A sample of polonium is provided in a solution. A controlled amount of sulfide and a controlled amount of a metal capable of forming an insoluble sulfide salt in the solution are introduced into the solution, in order to co-precipitate polonium from the solution. The precipitates are filtered out. | 02-25-2016 |
| 423250000 | Transuranium compound | 2 |
| 20150118139 | STRONTIUM PHOSPHATE MICROPARTICLE FOR RADIOLOGICAL IMAGING AND THERAPY - This invention relates to a method for making strontium-phosphate microparticles that incorporate radioisotopes for radiation therapy and imaging. | 04-30-2015 |
| 423251000 | Plutonium containing | 1 |
| 20140219900 | PROCESS FOR PREPARING AN OXYHALOGENIDE AND/OR OXIDE OF ACTINIDE(S) AND/OR OF LANTHANIDE(S) FROM A MEDIUM COMPRISING AT LEAST ONE MOLTEN SALT - The invention relates to a process for manufacturing an oxychloride or oxide of actinide(s) and/or of lanthanide(s) from a chloride of actinide(s) and/or of lanthanide(s) present in a medium comprising at least one molten salt of chloride type comprising a step of bringing said chloride of actinide(s) and/or lanthanide(s) present in said medium comprising at least one molten salt of chloride type into contact with a wet inert gas. | 08-07-2014 |
| 423252000 | Thorium compound | 3 |
| 20080233030 | Process for Manufacturing an Electrochemical Device - Process for manufacturing an electrochemical device including a cathode, an anode and at least one electrolyte membrane disposed between the anode and the cathode, wherein at least one of the cathode, the anode and the electrolyte membrane, contains at least a ceramic material. | 09-25-2008 |
| 20080260612 | Oxidation of metallic materials as part of an extraction, purification and/or refining process - Multi-step metal compound oxidation process to produce compounds and enhanced metal oxides from various source materials, e.g. metal sulfides, carbides, nitrides and other metal containing materials with metal oxides from secondary reaction steps being utilized as an oxidation agent in the first reactions. | 10-23-2008 |
| 20120177556 | COMBUSTION SYNTHESIS METHOD AND BORON-CONTAINING MATERIALS PRODUCED THEREFROM - One embodiment of the present disclosure provides a method of making a ceramic material that contains boron and a metal. A metal source, an oxidizer, a boron source, and a fuel source are combined. These reactants are then heated at, or to, a temperature sufficient to initiate a combustion reaction. The combustion reaction produces a ceramic material that includes boron and the metal. The present disclosure also provides materials formed by the disclosed method, as well as methods and systems using such materials. | 07-12-2012 |
| 423253000 | Uranium compound | 9 |
| 20110217222 | PROCESS FOR THE ACID DIGESTION OF METAL-CONTAINING COMPOUNDS - Aqueous leachant compositions and processes for using the same comprising: (a) providing a metal-containing compound; and (b) subjecting the metal-containing compound to an acid digestion comprising contacting the metal-containing compound with an aqueous leachant; wherein the aqueous leachant comprises a mixture selected from the group consisting of: (i) sulfuric acid and one or more alkanesulfonic acids having alkane moieties selected from the group consisting of propyl, ethyl and methyl groups, at a weight ratio of alkanesulfonic acid to sulfuric acid of 1:1000 to 1:1; (ii) sulfuric acid and one or more salts of alkanesulfonic acids having alkane moieties selected from the group consisting of propyl, ethyl and methyl groups, at a weight ratio of salt of alkanesulfonic acid to sulfuric acid of 1:9 to 1:99. | 09-08-2011 |
| 20140112858 | FUEL PREPARATION FOR USE IN THE PRODUCTION OF MEDICAL ISOTOPES - The present invention relates generally to the field of medical isotope production by fission of uranium-235 and the fuel utilized therein (e.g., the production of suitable Low Enriched Uranium (LEU is uranium having 20 weight percent or less uranium-235) fuel for medical isotope production) and, in particular to a method for producing LEU fuel and a LEU fuel product that is suitable for use in the production of medical isotopes. In one embodiment, the LEU fuel of the present invention is designed to be utilized in an Aqueous Homogeneous Reactor (AHR) for the production of various medical isotopes including, but not limited to, molybdenum-99, cesium-137, iodine-131, strontium-89, xenon-133 and yttrium-90. | 04-24-2014 |
| 423254000 | Binary compound | 7 |
| 423258000 | Fluorine containing | 3 |
| 20150064089 | FLUIDIZED BED REACTORS INCLUDING CONICAL GAS DISTRIBUTORS AND RELATED METHODS OF FLUORINATION - Embodiments of a fluidized bed fluorination reactor are provided, as are embodiments of a fluidized bed reactor and embodiments of a fluorination method carried-out utilizing a fluidized bed fluorination reactor. In one embodiment, the fluidized bed fluorination reactor includes a source of fluorine gas, a reaction vessel, a windbox fluidly coupled to the source of fluorine gas, and a conical gas distributor fluidly coupled between the reaction vessel and the windbox. The conical gas distributor has a plurality of gas flow openings directing fluorine gas flow from the windbox into the fluorination reaction vessel during the fluorination process. | 03-05-2015 |
| 423259000 | Tetrafluoride | 2 |
| 20140065049 | INTERNAL CYCLONE FOR FLUIDIZED BED REACTOR - A fluidized bed reactor comprising a reaction column having a fluid portion; a gas inflow means for flowing a gas upwardly from the fluid portion of the reaction column; a particle feed means for feeding particles to the fluid portion of the reaction column; a cyclone capable of separating particles from the gas flowing upwardly from the fluid portion of the reaction column, the cyclone being located within the reaction column and being in communication with the gas flowing upwardly, wherein the cyclone comprises a cyclone body having an inlet, a gas outlet, and a particle drop port; and a particle discharge pipe having an upper part connected to the particle drop port of the cyclone body, and a lower part, wherein the particle discharge pipe is located substantially outside of the reaction column. | 03-06-2014 |
| 20150064090 | SERIES-COUPLED FLUIDIZED BED REACTOR UNITS INCLUDING CYCLONIC PLENUM ASSEMBLIES AND RELATED METHODS OF HYDROFLUORINATION - Embodiments of a series-coupled fluidized bed reactor unit are provided. In one embodiment, the reactor unit includes primary and secondary reactors. The primary reactor includes a reaction vessel, a gas distributor fluidly coupled to the reaction vessel, and a cyclonic plenum assembly. The cyclonic plenum assembly includes a plenum assembly housing, which is fluidly coupled to the gas distributor and which has an annular sidewall; and a gas/solids inlet pipe, which fluidly couples a partially-reacted gas outlet of the secondary reactor to the plenum assembly housing. The gas/solids inlet pipe is tangentially positioned with respect to the annular sidewall of the plenum assembly housing to induce vortex flow within the plenum assembly housing of the partially-reacted gas received from the secondary fluidized bed reactor through the gas/solids inlet pipe to promote the cyclonic separation of entrained solids from the partially-reacted gas prior to entry into the gas distributor. | 03-05-2015 |
| 423260000 | Oxygen containing | 4 |
| 20110104032 | METHOD OF PRODUCING SULFUR TETRAFLUORIDE FROM URANIUM TETRAFLUORIDE - A method for converting depleted uranium tetrafluoride (UF | 05-05-2011 |
| 20130280157 | METHOD FOR CONVERTING UO3 OR U3O8 INTO HYDRATED UO4 - A method for converting UO | 10-24-2013 |
| 423261000 | Dioxide | 2 |
| 20100278704 | TWO STEP DRY UO2 PRODUCTION PROCESS UTILIZING A POSITIVE SEALING VALVE MEANS BETWEEN STEPS - The present invention provides a two-step process for producing nuclear grade, active uranium dioxide (UO | 11-04-2010 |
| 20110110837 | SEGMENTED REACTORS FOR CAPACITY AND ENRICHMENT CHANGES IN CONVERSION OF URANIUM HEXAFLUORIDE TO URANIUM DIOXIDE - A dry conversion reactor for converting uranium hexafluoride to uranium dioxide, the dry conversion reactor including a gas-phase reaction segment and a fluidized bed segment, wherein at least one of the gas-phase reaction segment and the fluidized bed segment is a replaceable segment. A method for operating a dry conversion reactor utilizing a uranium hexafluoride to uranium dioxide conversion process, the method including replacing at least one conversion reactor segment. | 05-12-2011 |
