Organic Synthetic Resin Patents (Class 423/7)
  • Patent number: 10730752
    Abstract: Methods for a facile, template free and one-step synthesis of nanoporous carbons by using a heterocyclic aromatic organic compound as a single source precursor of both carbon and nitrogen are described. The heterocyclic aromatic organic compound contains nitrogen in pyrrolic and/or pyridinic positions and is chemically activated with NaOH, KOH or ZnCl2 at high temperatures in a solid state mixture as a synthesis protocol to promote fine micropores during carbonization. Nanoporous carbons synthesized by these methods that have superior gas sorption/storage and energy storage properties are also described. The nanoporous carbons are useful as carbon sequestration agents and supercapacitors.
    Type: Grant
    Filed: May 3, 2017
    Date of Patent: August 4, 2020
    Assignee: Virginia Commonwealth University
    Inventors: Hani M. El-Kaderi, Babak Ashourirad
  • Patent number: 10704120
    Abstract: The present invention provides a method for easy and efficient recovery of high purity scandium from nickel oxide ore, the method comprising: an adsorption step for passing a scandium-containing solution through an ion exchange resin to adsorb scandium on the ion exchange resin; an elution step for eluting scandium from the ion exchange resin to obtain a post-elution solution; an impurity extraction step in which after the elution step, the scandium-containing solution is subjected to a first solvent extraction using an amine-based impurity extractant and is separated into a first aqueous phase containing scandium and into a first organic phase containing impurities; and a scandium extraction step in which the first aqueous phase is subjected to a second solvent extraction using an amide derivative-containing scandium extractant to obtain a second organic phase containing scandium.
    Type: Grant
    Filed: January 31, 2017
    Date of Patent: July 7, 2020
    Assignee: SUMITOMO METAL MINING CO., LTD.
    Inventors: Itsumi Matsuoka, Hiroshi Kobayashi, Yusuke Senba
  • Patent number: 10696562
    Abstract: Disclosed herein are methods, techniques, and processes for enhancing the purity of a mixed rare earth solution. In one embodiment the rare earth mixture may include Lanthanum, Cerium, Praseodymium, Neodymium, Promethium, Samarium, Europium, Gadolinium, Terbium, Dysprosium, Holmium, Erbium, Thulium, Ytterbium, Lutetium, Scandium, and/or Yttrium. In one embodiment, the resin is a chelating resin that interacts poorly with one or more rare earth elements. In one embodiment a rare earth is selectively excluded for example, Lanthanum (sometimes considered a transition metal), Cerium, Praseodymium, Neodymium, Promethium, Samarium, Europium, Gadolinium, Terbium, Dysprosium, Holmium, Erbium, Thulium, Ytterbium, Lutetium, Scandium, and/or Yttrium. In one embodiment, yttrium is selectively excluded from the column.
    Type: Grant
    Filed: December 5, 2014
    Date of Patent: June 30, 2020
    Inventors: Benjamin V. Kronholm, Corby G. Anderson
  • Patent number: 9878320
    Abstract: Hybrid media formed by combining a metal precursor solution with particulate media to yield a mixture, decanting the mixture to yield a decanted mixture, heating the decanted mixture in via microwave radiation to yield hybrid media, rinsing the hybrid media with water, soaking the rinsed hybrid media in a salt solution, and rinsing the soaked hybrid media with water. The hybrid media includes a metal dioxide derived from the metal precursor, such as TiO2 derived from TiOSO4.
    Type: Grant
    Filed: July 10, 2015
    Date of Patent: January 30, 2018
    Assignee: Arizona Board of Regents on behalf of Arizona State University
    Inventors: Kiril D. Hristovski, Paul K. Westerhoff
  • Patent number: 9330795
    Abstract: The invention relates to a method for preparing a fuel based on oxide, carbide, and/or oxycarbide comprising uranium and at least one actinide and/or lanthanide component, comprising the following steps: a step for preparing a load solution consisting in a nitric solution comprising said actinide and/or lanthanide in the form of actinide and/or lanthanide nitrates and uranium as a hydroxylated uranyl nitrate complex; a step for passing said solution over a cation exchange resin comprising carboxylic groups, with which the actinide and/or the lanthanide in cationic form and the uranium as uranyl remain bound to the resin; a heat treatment step of said resin so as to obtain said fuel.
    Type: Grant
    Filed: September 22, 2009
    Date of Patent: May 3, 2016
    Assignee: COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES
    Inventors: Sebastien Picart, Hamid Mokhtari, Isabelle Jobelin
  • Patent number: 9315766
    Abstract: A solid particle for washing and the washing method using the same are provided. The solid particle is a polymer solid particle, wherein open pores are distributed on the solid particle surface. The washing method using the solid particle comprises steps of separating the articles to be washed with the solid particles, rinsing the articles to be washed and drying the articles to be washed.
    Type: Grant
    Filed: November 11, 2011
    Date of Patent: April 19, 2016
    Assignees: HAIER GROUP CORPORATION, HAIER GROUP TECHNIQUE R&D CENTER
    Inventors: Zhengbao He, Chunfeng Lao
  • Patent number: 9309116
    Abstract: Disclosed are methods used to remove HF from a fluorocarbon containing stream, thereby forming a final aqueous HF solution having both a high HF concentration and low dissolved organic content.
    Type: Grant
    Filed: September 26, 2011
    Date of Patent: April 12, 2016
    Assignee: Honeywell International Inc.
    Inventors: Yuon Chiu, Richard Durick Horwath, Stephen A. Cottrell
  • Patent number: 9267896
    Abstract: According to the present invention, there is provided a method of determining a concentration of uranium including: a) a primary measuring step of measuring luminescence intensity or luminescence attenuation of uranium (VI) of an oxidant added sample obtained by adding an oxidant composition to a detection target sample; b) a secondary measuring step of adding different volumes of standard solution containing uranium (VI) having a predetermined concentration to a plurality of oxidant added samples, respectively, and then measuring luminescence intensity or luminescence attenuation of uranium (VI) contained in each standard solution added sample; and c) a calculating step of calculating a concentration of uranium (VI) contained in the detection target sample by a standard addition method based on the primary and secondary measurements. With the method for determining a concentration of uranium according to the present invention, the concentration of uranium may be further rapidly and accurately analyzed.
    Type: Grant
    Filed: December 28, 2012
    Date of Patent: February 23, 2016
    Assignee: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
    Inventors: Wan-Sik Cha, Euo-Chang Jung, Hye-Ryun Cho
  • Patent number: 9099208
    Abstract: Methods of purifying acidic metal solutions by removing at least a portion of alpha-particle emitting materials are provided. The purified metal solutions are useful in a variety of applications requiring low levels of alpha-particle emission.
    Type: Grant
    Filed: May 24, 2012
    Date of Patent: August 4, 2015
    Inventors: Matthew L. Grandbois, Harlan Robert Goltz, Jeffrey M. Calvert, Matthew Lawrence Rodgers, Charles R. Marston
  • Patent number: 8883096
    Abstract: 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 solution stream is then contacted by with an ion exchange resin. Uranium species bound to the ion exchange resin are eluted by contacting the resin with a solution comprising anions to produce a loaded uranium eluant stream. The loaded uranium eluant stream is treated to provide a uranium containing product.
    Type: Grant
    Filed: October 31, 2012
    Date of Patent: November 11, 2014
    Assignee: Urtek, LLC
    Inventors: Marcus Worsley Richardson, James Andrew Davidson, Bryn Llywelyn Jones, Jessica Mary Page, Karin Helene Soldenhoff, Tomasz Artur Safinski, Manh Toan Tran
  • Publication number: 20140294701
    Abstract: A functionalized mesoporous carbon composition comprising a mesoporous carbon scaffold having mesopores in which polyvinyl polymer grafts are covalently attached, wherein said mesopores have a size of at least 2 nm and up to 50 nm. Also described is a method for producing the functionalized mesoporous composition, wherein a reaction medium comprising a precursor mesoporous carbon, vinyl monomer, initiator, and solvent is subjected to sonication of sufficient power to result in grafting and polymerization of the vinyl monomer into mesopores of the precursor mesoporous carbon. Also described are methods for using the functionalized mesoporous carbon, particularly in extracting metal ions from metal-containing solutions.
    Type: Application
    Filed: March 27, 2013
    Publication date: October 2, 2014
    Inventors: Sheng Dai, Joanna Gorka, Richard T. Mayes
  • Patent number: 8703077
    Abstract: 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 phosphoric acid to ferrous iron, and then extracting uranium compounds from the wet-process phosphoric acid. The process can include separating a side stream from a feed stream of wet-process phosphoric acid, wherein the side stream has a greater concentration of the uranium compounds than the feed stream by filtration. Extracting uranium compounds from the wet-process phosphoric acid can be by ion exchange process or by solvent extraction.
    Type: Grant
    Filed: July 23, 2012
    Date of Patent: April 22, 2014
    Assignee: Urtek, LLC.
    Inventors: Mark S. Chalmers, James Andrew Davidson, Bryn Llywelyn Jones, Paul Robert Kucera, Peter Douglas Macintosh, Jessica Mary Page, Marcus Worsley Richardson, Karin Helene Soldenhoff, Colin Wayrauch
  • Patent number: 8652425
    Abstract: 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 conversion of processed or semi-processed uranium as U3O8, UO2, or most tetra or hexa-valent forms of uranium, and where applicable, for the recovery of uranium from uranium ores, using advanced multiple stage membrane based technologies for the separation and concentration of uranium in solution from heavy metals and lighter elements that may be present in the solution, and the selective leach and precipitation properties of an ammonium carbonate leach.
    Type: Grant
    Filed: April 19, 2011
    Date of Patent: February 18, 2014
    Inventor: Andrew Bassil
  • Publication number: 20140044615
    Abstract: 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 chloride ion in solution. The resin may comprise a functional group comprising an amino phosphonic group, an amino-phosphinic group, an amino phosphoric functional group and/or a combination thereof. According to the invention the leach solution or leach pulp may be generated by in-situ leaching, vat leaching, heap leaching and/or agitated leaching at ambient, elevated temperature and/or elevated pressure conditions in saline or hyper-saline water.
    Type: Application
    Filed: February 15, 2012
    Publication date: February 13, 2014
    Applicant: Clean Teq Holding Limited
    Inventors: John Carr, Nikolai Zontov, Tony Chamberlain
  • Publication number: 20130343969
    Abstract: Extraction method for recovering metals. Phosphoric acid is contacted with an extractant suspension of solid particulate material comprising a para- or ferromagnetic material core surrounded by an outer shell of a chelating polymer whereby a metal is the solution is adsorbed on the chelating polymer, thereby removing it from the phosphoric acid solution. The metal-containing solid particulate material is magnetically separated from the solution and the metal is stripped from the solid particulate material for reuse.
    Type: Application
    Filed: June 20, 2013
    Publication date: December 26, 2013
    Inventors: Lev E. Bromberg, Yaroslav Klichko, T. Alan Hatton
  • Patent number: 8562922
    Abstract: The present application relates to novel gel-type or macroporous picolylamine resins which are based on at least one monovinylaromatic compound and at least one polyvinylaromatic compound and/or a (meth)acrylic compound and contain tertiary nitrogen atoms in structures of the general formula (I) as functional group, where R1 is an optionally substituted radical from the group consisting of picolyl, methylquinoline and methylpiperidine, R2 is —CH2—S—CH2COOR3 or —CH2—S—C1-C4-alkyl or —CH2—S—CH2CH(NH2)COOR3 or —CH2—S—CH2—CH(OH)—CH2(OH) or or derivatives thereof or —C?S(NH2), R3 is a radical from the group consisting of H, Na and K, m is an integer from 1 to 4, n and p are each, independently of one another, a number in the range from 0.1 to 1.9 and the sum of n and p is 2 and M is the polymer matrix, a process for preparing them and their uses, in particular the use in hydrometallurgy and electroplating.
    Type: Grant
    Filed: February 27, 2009
    Date of Patent: October 22, 2013
    Assignee: LANXESS Deutschland GmbH
    Inventors: Reinhold Klipper, Michael Schelhaas, Duilio Rossoni
  • Patent number: 8563622
    Abstract: The present application relates to novel monodisperse, gel-type or macroporous picolylamine resins which are based on at least one monovinylaromatic compound and at least one polyvinylaromatic compound and/or a (meth)acrylic compound and contain tertiary nitrogen atoms in structures of the general formula (I) as functional group, where R1 is an optionally substituted radical from the group consisting of picolyl, methylquinoline and methylpiperidine, R2 is a radical —(CH2)q—COOR3, R3 is a radical from the group consisting of H, Na and K, m is an integer from 1 to 4, n and p are each, independently of one another, a number in the range from 0.1 to 1.9 and the sum of n and p is 2, q is an integer from 1 to 5 and M is the polymer matrix, a process for preparing them and their uses, in particular the use in hydrometallurgy and electroplating.
    Type: Grant
    Filed: February 27, 2009
    Date of Patent: October 22, 2013
    Assignee: LANXESS Deutschland GmbH
    Inventors: Michael Schelhaas, Reinhold Klipper, Duilio Rossoni
  • Patent number: 8557201
    Abstract: The present invention is directed to a new more environmentally friendly method for the recovery of uranium from pregnant liquor solutions that comprise high concentration of sulfate by using an amino phosphonic functionalized resin.
    Type: Grant
    Filed: August 8, 2012
    Date of Patent: October 15, 2013
    Assignee: Rohm and Haas Company
    Inventor: Areski Rezkallah
  • Patent number: 8475747
    Abstract: A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.
    Type: Grant
    Filed: June 15, 2009
    Date of Patent: July 2, 2013
    Assignee: U.S. Department of Energy
    Inventors: Michael Ernest Johnson, Martin David Maloney
  • Patent number: 8475746
    Abstract: Disclosed herein is a uranium ion exchange adsorption method using ultrasound. The method includes placing a slurry obtained by mixing uranium ions, sulfuric acid and an ion exchange resin into a reaction bath, and stirring the slurry in the reaction bath while simultaneously applying ultrasound to the reaction bath to allow the uranium ions to be adsorbed to the ion exchange resin through ion exchange adsorption. The method has an improved ion exchange adsorption rate of the uranium ions.
    Type: Grant
    Filed: May 2, 2011
    Date of Patent: July 2, 2013
    Assignee: Korea Institute of Geoscience and Mineral Resources
    Inventors: Kyeong-Woo Chung, Chul-Joo Kim, Ho-Sung Yoon
  • Publication number: 20130164197
    Abstract: 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 solution stream is then contacted by with an ion exchange resin. Uranium species bound to the ion exchange resin are eluted by contacting the resin with a solution comprising anions to produce a loaded uranium eluant stream. The loaded uranium eluant stream is treated to provide a uranium containing product.
    Type: Application
    Filed: October 31, 2012
    Publication date: June 27, 2013
    Applicant: URTEK, LLC
    Inventor: URTEK, LLC
  • Publication number: 20130039823
    Abstract: 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 conversion of processed or semi-processed uranium as U3O8, UO2, or most tetra or hexa-valent forms of uranium, and where applicable, for the recovery of uranium from uranium ores, using advanced multiple stage membrane based technologies for the separation and concentration of uranium in solution from heavy metals and lighter elements that may be present in the solution, and the selective leach and precipitation properties of an ammonium carbonate leach.
    Type: Application
    Filed: April 19, 2011
    Publication date: February 14, 2013
    Inventor: Andrew Bassil
  • Patent number: 8362199
    Abstract: Interlayer insulating films 5,7 (insulating films) provided in a memory capacitor cell 8 are formed between a gate electrode 3 and a counter electrode 8C formed on a silicon wafer 1. The interlayer insulating films 5,7 comprise a borazine-based resin, having a specific dielectric constant of no greater than 2.6, a Young's modulus of 5 GPa or greater and a leak current of no greater than 1×10?8 A/cm2.
    Type: Grant
    Filed: June 1, 2009
    Date of Patent: January 29, 2013
    Assignee: Hitachi Chemical Co., Ltd.
    Inventors: Hiroshi Matsutani, Makoto Kaji, Koichi Abe, Yuko Uchimaru
  • Publication number: 20130022520
    Abstract: 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 phosphoric acid to ferrous iron, and then extracting uranium compounds from the wet-process phosphoric acid. The process can include separating a side stream from a feed stream of wet-process phosphoric acid, wherein the side stream has a greater concentration of the uranium compounds than the feed stream by filtration. Extracting uranium compounds from the wet-process phosphoric acid can be by ion exchange process or by solvent extraction.
    Type: Application
    Filed: July 23, 2012
    Publication date: January 24, 2013
    Inventors: Nicholas Warwick Bristow, Mark S. Chalmers, James Andrew Davidson, Bryn Llywelyn Jones, Paul Robert Kucera, Nick Lynn, Peter Douglas Macintosh, Jessica Mary Page, Thomas Charles Pool, Marcus Worsley Richardson, Karin Helene Soldenhoff, Kelvin John Taylor, Colin Wayrauch
  • Patent number: 8343446
    Abstract: The oxine ligands 5-chloro-8-hydroxyquiniline and 5-sulfoxyl-8-hydroxyquinoline are covalently bound, using, for example, the Mannich reaction, to a silica gel polyamine composite made from a silanized amorphous silica xerogel and polyallylamine. The resulting modified composites, termed CB-1 (X?Cl) and SB-1 (X?SO3H), respectively, show a clear selectivity for trivalent over divalent ions and selectivity for gallium over aluminum. The compounds of the invention can be applied for the sequestration of metals, such as heavy metals, from contaminated mine tailing leachates.
    Type: Grant
    Filed: October 13, 2011
    Date of Patent: January 1, 2013
    Assignee: The University of Montana
    Inventors: Edward Rosenberg, Paul Miranda, Yuen Onn Wong
  • Publication number: 20120189514
    Abstract: The invention covers the combination of utilizing the selectivity of an adsorbent to remove species from a liquid containing mixtures of ions and then subjecting the loaded resin to a chromatographic displacement utilizing the most selectively adsorbed species to displace the undesired co-adsorbing impurities. The technique can be used even when the most selectively adsorbed species is present as a minor constituent in the feed solution.
    Type: Application
    Filed: December 23, 2011
    Publication date: July 26, 2012
    Inventor: Gordon Rossiter
  • Patent number: 8153087
    Abstract: The present application is directed to a method for the purification of Radium, in particular 226Ra, for target preparation for an essentially pure 225Ac production from available radioactive sources, using an extraction chromatography in order to separate chemically similar elements such as Ba, Sr, and Pb from the desired Ra; wherein said extraction chromatography has an extractant system on the basis of a crown ether. The invention is further related to a method for recycling of 226Ra, for target preparation for 225Ac production from radium sources irradiated with accelerated protons (p,2n), after separation of the produced 225AC. In this method a combination of the above extraction chromatography and a cation exchange chromatography is used. The obtained 226Ra is essentially free of the following chemical contaminants consisting of Ag, Al, As, Be, Bi, Ca, Cd, Co, Cr, Cu, Fe, Ga, K, Li, Mg, Mn, Na, Ni, Pb, Sr, V, Zn, and Ba.
    Type: Grant
    Filed: March 5, 2009
    Date of Patent: April 10, 2012
    Assignee: Actinium Pharmaceuticals Inc.
    Inventors: Eva Kabai, Josue Manuel Moreno Bermudez, Richard Henkelmann, Andreas Turler
  • Patent number: 8137644
    Abstract: The invention relates to a method for the removal of uranium(VI) species from waters by means of weakly basic, polyacrylic-based anion exchangers, said uranium(VI) species being present in the form of uranyl complexes as dissolved uranyl.
    Type: Grant
    Filed: May 4, 2005
    Date of Patent: March 20, 2012
    Assignees: ATC, Rohm and Haas Company
    Inventors: Wolfgang Hoell, Gunther Mann
  • Patent number: 7988937
    Abstract: The present invention relates to a method for the volumetric decontamination of radioactive metals. The method includes the step of precipitating out radioactive gamma and beta emitting nucleotides and then recovering non-radioactive metal compounds.
    Type: Grant
    Filed: September 1, 2010
    Date of Patent: August 2, 2011
    Inventors: W. Novis Smith, David S. Eaker, Rick Low
  • Publication number: 20110091365
    Abstract: The present application relates to novel gel-type or macroporous picolylamine resins which are based on at least one monovinylaromatic compound and at least one polyvinylaromatic compound and/or a (meth)acrylic compound and contain tertiary nitrogen atoms in structures of the general formula (I) as functional group, where R1 is an optionally substituted radical from the group consisting of picolyl, methylquinoline and methylpiperidine, R2 is —CH2—S—CH2COOR3 or —CH2—S—C1-C4-alkyl or —CH2—S—CH2CH(NH2)COOR3 or —CH2—S—CH2—CH(OH)—CH2(OH) or or derivatives thereof or —C?S(NH2), R3 is a radical from the group consisting of H, Na and K, m is an integer from 1 to 4, n and p are each, independently of one another, a number in the range from 0.1 to 1.9 and the sum of n and p is 2 and M is the polymer matrix, a process for preparing them and their uses, in particular the use in hydrometallurgy and electroplating.
    Type: Application
    Filed: February 27, 2009
    Publication date: April 21, 2011
    Applicant: LANXESS DEUTSCHLAND GMBH
    Inventors: Reinhold Klipper, Michael Schelhaas, Duilio Rossoni
  • Patent number: 7704468
    Abstract: An extraction agent for the separation of trivalent actinides from lanthanides in an acidic media and a method for forming same are described, and wherein the methodology produces a stable regiospecific and/or stereospecific dithiophosphinic acid that can operate in an acidic media having a pH of less than about 7.
    Type: Grant
    Filed: September 21, 2005
    Date of Patent: April 27, 2010
    Assignee: Battelle Energy Alliance, LLC
    Inventors: John R. Klaehn, Mason K. Harrup, Jack D. Law, Dean R. Peterman
  • Publication number: 20100034713
    Abstract: A chemical element to be very efficiently separated from uranium starting from an acid aqueous phase, in an extraction cycle for the uranium, when this chemical element is present in said phase at a concentration less than that of the uranium, or even as a trace element, and when it is moreover less extractable by the extractant used in this extraction cycle than is the uranium. The chemical element can notably be neptunium(IV) or thorium 228.
    Type: Application
    Filed: July 2, 2007
    Publication date: February 11, 2010
    Applicant: COMPAGNIE GENERALE DES MATIERES NUCLEAIRES
    Inventors: Jean-Paul Moulin, Gilbert Andreoletti, Patrick Bourdet
  • Patent number: 7655199
    Abstract: The present invention relates to a process for the recovery of uranium in high silica environments comprising the use of a strong base macroreticular ion exchange resin.
    Type: Grant
    Filed: November 28, 2006
    Date of Patent: February 2, 2010
    Assignee: Rohm and Haas Company
    Inventors: Peter Ian Cable, Emmanuel Zaganiaris
  • Patent number: 7597862
    Abstract: A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.
    Type: Grant
    Filed: September 20, 2006
    Date of Patent: October 6, 2009
    Assignee: Battelle Energy Alliance, LLC
    Inventors: David H. Meikrantz, Terry A. Todd, Troy J. Tranter, E. Philip Horwitz
  • Patent number: 7553461
    Abstract: A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or actinide cations from an aqueous acidic sample solution is described. The separation medium is preferably free-flowing and comprises particles having a diglycolamide (DGA) extractant dispersed onto an inert, porous support.
    Type: Grant
    Filed: January 2, 2007
    Date of Patent: June 30, 2009
    Assignee: PG Research Foundation, Inc.
    Inventors: E. Philip Horwitz, Richard E. Barrans, Jr., Andrew H. Bond
  • Publication number: 20090022638
    Abstract: The present invention relates to the use of monodisperse, macroporous anion exchangers of type I or type II in hydrometallurgical processes for winning metals of value.
    Type: Application
    Filed: July 19, 2007
    Publication date: January 22, 2009
    Inventors: Duilio Rossoni, Reinhold Klippper, Rudolf Wagner, Wolfgang Wambach, Michael Schelhaas
  • Publication number: 20090001802
    Abstract: A novel class of dendritic macromolecules is provided having a core, a hyperbranched structure, and a plurality of units satisfying the formula —NR2(C?O)R1, in which R1 is not a continuation of the hyperbranched structure. Methods of preparing these dendritic macromolecules are also provided, as well as methods of using dendritic macromolecules, including those described above, in separation processes or as part of in situ leach mining processes. A class of facilities for in situ leach mining is also provided.
    Type: Application
    Filed: May 21, 2008
    Publication date: January 1, 2009
    Inventors: Mamadou S. Diallo, Jean Frechet, Emine Boz
  • Patent number: 7214318
    Abstract: A method for separation of actinide elements comprising feeding a solution containing actinide elements such as americium, curium, californium and the like, into a resin column in which a weakly basic primary, secondary or tertiary anion exchange resin obtained by resinifying pyridine, imidazole or alkylamine has been packed, and then feeding an eluent of a mixed solution of nitric acid and alkyl alcohol such as methanol, ethanol, propanol and the like into the resin column to chromatographically separate the actinide elements from each other. This method makes it possible to efficiently separate the actinide elements from each other by a unit operation at ordinary temperature and ordinary pressure while avoiding oxidation operation, and hence makes it possible to avoid generation of secondary wastes and operations difficult in terms of engineering, such as precipitation.
    Type: Grant
    Filed: February 4, 2005
    Date of Patent: May 8, 2007
    Assignee: Japan Nuclear Cycle Development Institute
    Inventors: Tatsuya Suzuki, Yasuhiko Fujii, Masaki Ozawa
  • Patent number: 7157061
    Abstract: A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.
    Type: Grant
    Filed: September 24, 2004
    Date of Patent: January 2, 2007
    Assignee: Battelle Energy Alliance, LLC
    Inventors: David H. Meikrantz, Terry A. Todd, Troy J. Tranter, E. Philip Horwitz
  • Patent number: 7157022
    Abstract: A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or actinide cations from an aqueous acidic sample solution is described. The separation medium is preferably free-flowing and comprises particles having a diglycolamide (DGA) extractant dispersed onto an inert, porous support.
    Type: Grant
    Filed: January 27, 2003
    Date of Patent: January 2, 2007
    Assignee: .PG Research Foundation, Inc.
    Inventors: E. Philip Horwitz, Richard E. Barrans, Jr., Andrew H. Bond
  • Patent number: 7148393
    Abstract: A surface contaminated by a radioactive isotope is cleaned by applying to it a solution that contains an ion-specific resin that is weakly bonded to an ion and a weak anion solution including a carrier, water, and an ion that frees the radioactive isotope from the contaminated surface. The radioactive isotope bonds with the ion-specific resin, replacing the ion weakly bonded to said ion-specific resin. In a preferred embodiment, the ion-specific resin is made in the counterion form of citrate, the ion that is weakly bonded to the ion-specific resin is citrate, the carrier is glycerin, the water is de-ionized or distilled, and the ion that frees the radioactive isotope from the contaminated surface is salicylate.
    Type: Grant
    Filed: April 22, 2003
    Date of Patent: December 12, 2006
    Assignee: Radiation Decontamination Solutions, LLC
    Inventor: John Kuperus
  • Patent number: 7087206
    Abstract: A multicolumn selectivity inversion generator separation method has been developed in which actinium ions, a desired daughter radionuclide, are selectively extracted from a solution of the thorium parent and daughter radionuclides by a primary separation column, stripped, and passed through a second guard column that retains any parent or other daughter interferents, while the desired daughter actinium ions and radium ions elute. This separation method minimizes the effects of radiation damage to the separation material and permits the reliable production of radionuclides of high chemical and radionuclidic purity for use in diagnostic or therapeutic nuclear medicine.
    Type: Grant
    Filed: September 30, 2002
    Date of Patent: August 8, 2006
    Assignee: PG Research Foundation
    Inventors: Andrew H. Bond, E. Philip Horwitz, Daniel R. McAlister
  • Patent number: 6485695
    Abstract: This invention relates to a method and an apparatus for preparing Bi-213 to be integrated in a radioimmunocojugate for human therapeutic use. According to the invention the method comprises the sequence of steps as follows: a) an ampoule 5 containing colloid-free actinium-225, obtained from drying an actinium nitrate solution, is loaded into a container 20 provided with radiation panels 21; b) a dissolving medium is poured into the ampoule 5; c) the solution obtained in the ampoule is transferred into an ion exchange column 6; d) an elution medium is circulated through the column 6; e) the eluate containing eluted Bi-213 is pumped towards a vial 10 for quantification and quality control.
    Type: Grant
    Filed: May 4, 2000
    Date of Patent: November 26, 2002
    Assignee: European Community (EC)
    Inventors: Lothar Koch, Christos Apostolidis, Roger Molinet, Bruno Brandalise, Willem Janssens, Jacques Van Geel
  • Patent number: 6153154
    Abstract: The present invention is a method of separating a short-lived daughter isotope from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a bi-directional pump and one or more valves, a solution of the parent isotope is processed to generate two separate solutions, one of which contains the daughter isotope, from which the parent has been removed with a high decontamination factor, and the other solution contains the recovered parent isotope. The process can be repeated on this solution of the parent isotope. The system with the fluid drive and one or more valves is controlled by a program on a microprocessor executing a series of steps to accomplish the operation. In one approach, the cow solution is passed through a separation medium that selectively retains the desired daughter isotope, while the parent isotope and the matrix pass through the medium. After washing this medium, the daughter is released from the separation medium using another solution.
    Type: Grant
    Filed: May 27, 1998
    Date of Patent: November 28, 2000
    Assignee: Battelle Memorial Institute
    Inventors: Oleg B. Egorov, Jay W. Grate, Lane A. Bray
  • Patent number: 5966584
    Abstract: Trivalent actinides can be separated from trivalent lanthanides in aqueous solutions at H.sup.+ concentrations of 2 mol/l to 0.001 mol/liter by extraction with bis(aryl)dithiophosphinic acid and a synergist such as TBP, TOPO and TBPO in an organic solvent. A high separation efficiency results. The method is applicable to high-level liquid waste from reactors and nuclear-material processing plants.
    Type: Grant
    Filed: September 17, 1997
    Date of Patent: October 12, 1999
    Assignee: Forschungszentrum Julich GmbH
    Inventors: Giuseppe Modolo, Reinhard Odoj
  • Patent number: 5945342
    Abstract: The present invention relates to methods for digesting diphosphonic acid substituted cation exchange resins that have become loaded with actinides, rare earth metals, or heavy metals, in a way that allows for downstream chromatographic analysis of the adsorbed species without damage to or inadequate elution from the downstream chromatographic resins. The methods of the present invention involve contacting the loaded diphosphonic acid resin with concentrated oxidizing acid in a closed vessel, and irradiating this mixture with microwave radiation. This efficiently increases the temperature of the mixture to a level suitable for digestion of the resin without the use of dehydrating acids that can damage downstream analytical resins. In order to ensure more complete digestion, the irradiated mixture can be mixed with hydrogen peroxide or other oxidant, and reirradiated with microwave radiation.
    Type: Grant
    Filed: May 18, 1998
    Date of Patent: August 31, 1999
    Assignee: Westinghouse Savannah River Company
    Inventors: Sherrod L. Maxwell, III, Sheldon T. Nichols
  • Patent number: 5476641
    Abstract: A method of separating and recovering Pu and Np from a Pu- and Np-containing nitric acid solution. The method comprises the steps of subjecting a nitric acid solution containing Pu and Np to valence adjustment by adding a reducing agent consisting of hydroxylamine nitrate and hydrazlne to said nitric acid solution so as to reduce Pu and Np in said nitric acid solution to Pu (III) and Np (IV), respectively; adjusting a nitric acid concentration of said nitric acid solution after said valence adjustment to 6 to 8 M; bringing said nitric acid solution after said nitric acid concentration adjustment into contact with a strong basic anion exchange resin so as to cause Np to be selectively adsorbed by said resin and to separate and recover Pu as a plutonium nitrate solution; and eluting said adsorbed Np (IV) by using diluted nitric acid of 1 M or below so as to recover Np as a neptunium nitrate solution.
    Type: Grant
    Filed: August 4, 1994
    Date of Patent: December 19, 1995
    Assignee: Doryokuro Kakunenryo Kaihatsu Jigyodan
    Inventors: Akio Todokoro, Yoshiyuki Kihara, Takashi Okada
  • Patent number: 5460791
    Abstract: A method of adsorbing and separating a heavy metal element by using a tannin adsorbent comprising:(a) adjusting the pH of a solution containing a plurality of heavy metal elements to a predetermined pH;(b) contacting the adsorbent with the solution in which the pH thereof is adjusted;(c) adjusting the pH of the solution contacted with the adsorbent to a pH different from the predetermined pH; and(d) contacting the solution in which the pH thereof is adjusted at the step (d) with the adsorbent prepared at the step (a).According to the inventive method, all of the heavy metal elements can be efficiently separated and adsorbed by using a tannin adsorbent from a solution containing a number of heavy metal elements. A method of regenerating a tannin adsorbent are also disclosed.
    Type: Grant
    Filed: August 10, 1992
    Date of Patent: October 24, 1995
    Assignee: Mitsubishi Nuclear Fuel Company, Ltd.
    Inventors: Wataru Shirato, Yoshinobu Kamei
  • Patent number: 5437848
    Abstract: A process for recovering metal and acid values from a source material containing metallic fluorides comprises digesting the source material in sulfuric acid to form a slurry, separating a fluoride containing solid phase and a metal containing first liquid phase. The solid phase is subjected to pyrohydrolysis, sulfuric and hydrofluoric acids are recovered, and the first liquid phase is processed to recover the metal values by solvent extraction or ion exchanges. The tantalum values are extracted from the first liquid aqueous phase by a water immiscible organic extractant such as methylisobutyl ketone to form a first liquid organic phase containing tantalum and a second liquid aqueous phase. The tantalum is stripped from the first organic phase using water. The process includes the additional steps of heating the separated solid phase from about ambient temperature to an elevated temperature in the presence of water vapor to evolve sulfuric acid and render the gangue chemically inert.
    Type: Grant
    Filed: July 10, 1992
    Date of Patent: August 1, 1995
    Assignee: Cabot Corporation
    Inventor: Robert A. Hard
  • Patent number: 5419880
    Abstract: A controlled multi-stage process for the stripping of uranium includes the introduction at one end of a solvent extraction device a uranium loaded organic solution. A concentrated stripping acidic aqueous solution is introduced at the other end of the solvent extraction device so that the aqueous solution and the organic solution are contacted counter-currently in the solvent extraction device at a temperature not substantially exceeding 35.degree. C.
    Type: Grant
    Filed: October 8, 1993
    Date of Patent: May 30, 1995
    Assignee: Falconbridge, Ltd.
    Inventors: Richard C. Swider, Steven A. Webster