Radioactive (at. No. 84+ Or Radioactive Isotope Of Another Element) Patents (Class 423/249)
  • Patent number: 10703771
    Abstract: The present invention provides a new chemical process, a new cassette configuration, and new software for the automated production of multiple batches of an [18F]labelled compound on a single cassette. The invention allows one synthesizer in one hot cell to produce sequentially a plurality of batches of [18F]-labelled PET tracer in the same day. In particular, the present invention provides a novel arrangement useful for the trapping of [18F]fluoride and recovery of [18O]water.
    Type: Grant
    Filed: November 12, 2015
    Date of Patent: July 7, 2020
    Assignee: GE HEALTHCARE LIMITED
    Inventors: Xavier Franci, Steve Lignon, Audrey Marie Lange, Nicolas Verbrugge
  • Patent number: 10662125
    Abstract: The present invention provides a new chemical process, a new cassette configuration, and new software for the automated production of multiple batches of an [18F]-labelled compound on a single cassette. The invention allows one synthesizer in one hot cell to produce sequentially a plurality of batches of [18F]-labelled PET tracer in the same day. In particular, the present invention provides a novel arrangement useful for purifying two consecutive batches of a reaction mixture comprising an 18F-labelled compound.
    Type: Grant
    Filed: November 12, 2015
    Date of Patent: May 26, 2020
    Assignee: GE HEATLHCARE LIMITED
    Inventors: Xavier Franci, Steve Lignon, Audrey Marie Lange, Nicolas Verbrugge
  • Patent number: 10167197
    Abstract: It is intended to provide an industrially advantageous method for obtaining zirconium tungsten phosphate that is useful as a negative thermal expansion material and exhibits a single phase in X-ray diffraction. The method for producing zirconium tungsten phosphate according to the present invention comprises using a mixture of a tungsten compound and an amorphous compound containing phosphorus and zirconium as a reaction precursor and calcining the reaction precursor. Preferably, the reaction precursor has an infrared absorption peak at least at 950 to 1150 cm?1, and the maximum value of the infrared absorption peak in this range appears at 1030 (±20) cm?1.
    Type: Grant
    Filed: October 4, 2016
    Date of Patent: January 1, 2019
    Assignee: NIPPON CHEMICAL INDUSTRIAL CO., LTD.
    Inventor: Junya Fukazawa
  • Patent number: 9962136
    Abstract: A method of reconstructing time-varying position of individual radioactive point sources directly from Positron Emission Tomography (PET) measurements is provided that includes using a PET scanner to acquire list-mode coincidence events of a moving radioactive point source, using an appropriately programmed computer to model a trajectory of the moving radioactive point source as a 3D function of a temporal variable, then apply an optimization procedure to find the trajectory that minimizes a distance between the trajectory and the recorded list-mode coincidence events, and using the PET scanner to output a real time position of the radioactive point source.
    Type: Grant
    Filed: May 13, 2015
    Date of Patent: May 8, 2018
    Assignee: The Board of Trustees of the Leland Stanford Junior University
    Inventor: Guillem Pratx
  • Patent number: 9865367
    Abstract: Systems and methods for separation or isolation of technetium radioisotopes from aqueous solutions of radioactive or non-radioactive molybdate salts using a polyalkyl glycol-based cross-linked polyether polymer. Some embodiments can be used for the effective purification of radioactive technetium-99m produced from low specific activity 99Mo.
    Type: Grant
    Filed: December 20, 2013
    Date of Patent: January 9, 2018
    Assignee: TRIUMF, A Joint Venture
    Inventors: Francois Benard, Kuo-Shyan Lin, Stefan Zeisler, Milan Vuckovic, Paul Schaffer
  • Patent number: 9827556
    Abstract: Disclosed is an exhaust gas purification catalyst carrier which includes a phosphate salt represented by formula: MPO4 (wherein M represents Y, La, or Al) or a zirconium phosphate represented by formula ZrP2O7; an exhaust gas purification catalyst containing a noble metal at least containing Rh and supported on the carrier; and an exhaust gas purification catalyst product having a catalyst support made of a ceramic or metallic material, and a layer of the exhaust gas purification catalyst, the layer being supported on the catalyst support.
    Type: Grant
    Filed: August 27, 2012
    Date of Patent: November 28, 2017
    Assignee: MITSUI MINING & SMELTING CO., LTD.
    Inventors: Yuki Nagao, Takahiro Sato, Yunosuke Nakahara, Masato Machida
  • Patent number: 9478409
    Abstract: In various embodiments, a method for coating a workpiece is provided. The method may include drying a workpiece, the workpiece being coated with at least one oxide layer as an uppermost layer; depositing a dielectric layer over the uppermost layer of the dried workpiece; wherein the workpiece is continuously subject to a pressure which is lower than atmospheric pressure during the drying process and during the depositing process.
    Type: Grant
    Filed: January 12, 2015
    Date of Patent: October 25, 2016
    Assignee: INFINEON TECHNOLOGIES AG
    Inventors: Juergen Steinbrenner, Markus Kahn, Helmut Schoenherr
  • Patent number: 9346049
    Abstract: A system for measuring asphaltene content of crude oil, includes a microfluidic chip, the microfluidic chip having a crude oil sample inlet port, a solvent port, a mixer and reactor section in fluid communication with the crude oil sample inlet port and the solvent port, and a filter in fluid communication with the mixer and reactor section, the filter having an inlet side and an outlet side, a waste port in fluid communication with the inlet side of the filter, and a product port in fluid communication with the outlet side of the filter. The system further includes an optical cell in fluid communication with the product port.
    Type: Grant
    Filed: April 6, 2015
    Date of Patent: May 24, 2016
    Assignee: Schlumberger Technology Corporation
    Inventors: Farshid Mostowfi, Abdel M. Kharrat, Philip James Homewood, Joseph Samuel Baddeley, Marc Schneider
  • Patent number: 9047998
    Abstract: The invention relates to a method of producing radionuclides. According to the method, a target medium comprising at least a target nuclide material is irradiated in an irradiation zone with neutron irradiation. Radionuclides form in the target nuclide material as a result of the irradiation, and at least some of the formed radionuclides are ejected from the target nuclide material. The ejected radionuclides are then captured and collected in a carbon-based recoil capture material which does not have an empty cage structure at crystallographic level.
    Type: Grant
    Filed: March 10, 2011
    Date of Patent: June 2, 2015
    Assignee: The South African Nuclear Energy Corporation Limited
    Inventors: David Randall Jansen, Geert Cornelis Krijger, Zvonimir Ivica Kolar, Jan Rijn Zeevaart
  • Patent number: 9028587
    Abstract: A method is described for obtaining purified 68Ga. The method comprises eluting 68Ga from a sorbent in and/or on which are sorbed 68Ga and 68Ge, so as to generate a crude 68Ga solution. The sorbent should have a higher affinity for 68Ge than for 68Ga. The crude 68Ga solution is then applied to a medium cation exchange resin, and the resin is eluted with an aqueous alcohol so as to retain the 68Ga on the resin and remove unwanted species from the resin. The resin is then eluted with an eluent, which may be an acidic solution, an alkaline solution or a solution of a species capable of complexing 68Ga ions, so as to obtain an eluate comprising purified 68Ga ions.
    Type: Grant
    Filed: March 3, 2011
    Date of Patent: May 12, 2015
    Assignee: Australian Nuclear Science and Technology Organisation
    Inventor: Van So Le
  • Patent number: 9023305
    Abstract: The invention relates to a strontium-82/rubidium-82 generator, comprising a column filled with a cationic exchanger loaded with strontium-82, and having an inlet and an outlet, and a liquid medium, wherein parts of the column, inlet and outlet coming into contact with the liquid medium are iron-free, preferably metal-free, to a method for producing rubidium-82, and to the obtained diagnostic agent.
    Type: Grant
    Filed: August 14, 2009
    Date of Patent: May 5, 2015
    Assignee: Stichting Jeroen Bosch Ziekenhuis
    Inventor: Roland Anthonius Maria Johannus Claessens
  • Publication number: 20150118495
    Abstract: This invention relates to strontium-phosphate microparticles that incorporate radioisotopes for radiation therapy and imaging.
    Type: Application
    Filed: October 21, 2014
    Publication date: April 30, 2015
    Applicant: MO-SCI CORPORATION
    Inventors: Delbert E. Day, Yiyong He
  • Publication number: 20150118139
    Abstract: This invention relates to a method for making strontium-phosphate microparticles that incorporate radioisotopes for radiation therapy and imaging.
    Type: Application
    Filed: October 21, 2014
    Publication date: April 30, 2015
    Applicant: MO-SCI CORPORATION
    Inventors: Delbert E. Day, Yiyong He
  • Publication number: 20150105262
    Abstract: The invention provides the Magnetoelectric Effect Material consisted of a single isotope, the alloy of isotopes, or the compound of isotopes. The invention applies enrichment and purification to increase the isotope abundance, to create the density of nuclear exciton by irradiation, and therefore increase the magnetoelectric effect of the crystal of single isotope, the alloy crystal of isotopes and the compound crystal of isotopes. The invention provides the manufacturing method including the selection rules of isotopes, the fabrication processes and the structure of composite materials. The invention belongs to the area of the nuclear science and the improvement of material character. The invention using the transition of entangled multiple photons to achieve the delocalized nuclear exciton. The mix of selected isotopes adjusts the decay lifetime of nuclear exciton and the irradiation efficiency to generate the nuclear exciton.
    Type: Application
    Filed: February 3, 2012
    Publication date: April 16, 2015
    Inventor: Yao Cheng
  • Publication number: 20150104386
    Abstract: The present invention provides a method for the generation of 223Ra of pharmaceutically tolerable purity comprising i) preparing a generator mixture comprising 227Ac, 227Th and 223Ra; ii) loading said generator mixture onto a strong base anion exchange resin; iii) eluting said 223Ra from said strong base anion exchange resin using a first mineral acid in an alcoholic aqueous solution to give a first eluted 223Ra solution; iv) loading the 223Ra of the first eluted 223Ra solution onto a strong acid cation exchange resin; and v) eluting the 223Ra from said strong acid cation exchange resin losing a second mineral acid in aqueous solution to provide a second eluted solution. The invention additionally provides products of corresponding purity and/or products obtained or obtainable by such a method.
    Type: Application
    Filed: November 20, 2014
    Publication date: April 16, 2015
    Inventors: Jan Roger KARLSON, Peer BØRRETZEN
  • Publication number: 20150044117
    Abstract: 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.
    Type: Application
    Filed: March 22, 2013
    Publication date: February 12, 2015
    Applicant: GEORGETOWN UNIVERSITY
    Inventors: Kevin Travis Holman, Christopher Kane
  • Publication number: 20140356270
    Abstract: 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.
    Type: Application
    Filed: June 2, 2014
    Publication date: December 4, 2014
    Applicants: Kurion, Inc., Nuclear Sources and Services, Inc.
    Inventors: Christopher Robert Shmayda, Robert D. Gallagher
  • Publication number: 20140356282
    Abstract: Methods of synthesizing 100Mo2C and 99mTcO4? are disclosed. Methods of 100Mo2C generation involve thermally carburizing 100MoO3. Methods of 99mTcO4 generation involve proton bombardment of 100Mo2C in a cyclotron. Yields of 99mTcO4 can be increased by sintering 100Mo2C prior to bombardment. The methods also include recycling of 100Mo2C to form 100MoO3. SPECT images obtained using 99mTcO4 generated by the disclosed methods are also presented.
    Type: Application
    Filed: June 2, 2014
    Publication date: December 4, 2014
    Applicant: Washington University
    Inventors: Vernal Richards, Suzanne Lapi
  • Publication number: 20140286846
    Abstract: 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.
    Type: Application
    Filed: September 25, 2013
    Publication date: September 25, 2014
    Applicant: UNIVERSITY OF CONNECTICUT
    Inventors: Steven L. Suib, Altug Suleyman Poyraz
  • Patent number: 8821824
    Abstract: 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.
    Type: Grant
    Filed: June 21, 2011
    Date of Patent: September 2, 2014
    Assignees: ENEA—Agenzia Nazionale per le Nuove Tecnologie, l'Energia e lo Sviluppo Economico Sostenibile, Commissariat a l'Energie Atomique et aux Energies
    Inventors: Nicolas Ghirelli, Silvano Tosti, Pierre Trabuc, Fabio Borgognoni, Karine Liger, Alessia Santucci, Xavier Lefebvre
  • Publication number: 20140227176
    Abstract: A process for manufacturing magnetic and/or radioactive metal nanoparticles, the process comprising: preparing an electrolyte solution including metal ions and a stabilizer; generating a plasma at an interface of the electrolyte solution at atmospheric pressure; and recovering magnetic and/or radioactive metal nanoparticles. The magnetic metal nanoparticles can comprise magnetoradioactive nanoparticles. The magnetic metal nanoparticles can be used as MRI contrast agents and the magnetoradioactive nanoparticles can also be used as contrast agents and for dual PET/MRI applications. It also relates to a multi-plasma apparatus for synthesizing nanoparticles.
    Type: Application
    Filed: December 20, 2011
    Publication date: August 14, 2014
    Inventors: Fortin Marc-Andre, Christian Sarra-Bournet, Mathieu Letourneau, Gaetan Laroche
  • Patent number: 8758714
    Abstract: Disclosed is a novel adsorbent for use in a 99Mo/99mTc generator, which is a medical diagnostic radioisotope generator, and in a 188W/188Re generator, which is a therapeutic radioisotope generator. The adsorbent composed of sulfated alumina or alumina-sulfated zirconia exhibits adsorption capacity superior to that of conventional adsorbents, and is stable and is thus loaded in a dry state in an adsorption column so that the radioisotope 99Mo or 188W can be adsorbed. Thus, it is possible to miniaturize the column, and such a miniaturized column is small, convenient to use, and highly efficient, and extracts a radioisotope satisfying the requirements for pharmaceuticals, and thus can be useful for radioisotope generators extracting 99mTc or 188Re.
    Type: Grant
    Filed: June 7, 2012
    Date of Patent: June 24, 2014
    Assignee: Korea Atomic Energy Research Institute
    Inventors: Jun Sig Lee, Hyon Soo Han, Ul Jae Park, Kwang Jae Son, Hyeon Young Shin, Soon Bog Hong, Kang Duk Jang, Jong Sub Lee
  • Patent number: 8747790
    Abstract: A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450° C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80° C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.
    Type: Grant
    Filed: August 16, 2013
    Date of Patent: June 10, 2014
    Assignee: UT-Battelle, LLC
    Inventors: Emory D. Collins, Guillermo D. Delcul, Rodney D. Hunt, Jared A. Johnson, Barry B. Spencer
  • Patent number: 8679377
    Abstract: A gamma radiation source comprises 75Selenium wherein the 75Selenium is provided in the form of compounds, alloys or mixtures with one or more nonmetals which upon irradiation do not produce products capable of sustained emission of radiation which would unacceptably interfere with the gamma radiation of 75Selenium. A further gamma radiation source comprises 75Selenium wherein the 75Selenium is provided in the form of compounds, alloys or mixtures with one or more metals or nonmetals, the neutron irradiation of which does produce products capable of sustained emission of radiation which would acceptably complement the gamma radiation of 75Selenium. Further, the gamma radiation source may have components that are separately irradiated before being combined and the components may be of natural isotopic composition or of isotopically modified composition so that the subsequent radiation peaks may also be adjusted in relative frequency.
    Type: Grant
    Filed: December 5, 2012
    Date of Patent: March 25, 2014
    Inventors: John J. Munro, III, Kevin J. Schehr
  • Publication number: 20140065048
    Abstract: 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.
    Type: Application
    Filed: November 12, 2013
    Publication date: March 6, 2014
    Applicants: HON HAI PRECISION INDUSTRY CO., LTD., TSINGHUA UNIVERSITY
    Inventors: LIANG LIU, KAI-LI JIANG, SHOU-SHAN FAN
  • Publication number: 20140044624
    Abstract: The invention relates to a detritiation device comprising i) a furnace (1) for melting tritiated waste, said furnace comprising a hearth for receiving tritiated waste and a bubbling device for introducing a hydrogenated bubbling gas into the hearth during the melting and treatment of the tritiated waste in the furnace (1), and ii) a catalytic reactor with a quadrupole membrane (2) for treating the gas resulting from the melting and treatment of the tritiated waste in the furnace (1), said reactor comprising a membrane (20) for separating two flows of gas, the membrane (20) being permeable to the hydrogen isotopes. The invention also relates to an associated detritiation method.
    Type: Application
    Filed: April 23, 2012
    Publication date: February 13, 2014
    Inventors: Nicolas Ghirelli, Pierre Trabuc, Olivier Gastaldi, Pascal Lejay, Joel Balay, Abdellali Hadj-Azzem
  • Publication number: 20140039074
    Abstract: The invention generally relates to the preparation of 18F-labeled radiopharmaceuticals. In particular, this invention relates to the advanced processes for an efficient eiution of [18F]fluoride trapped in a cartridge filled with quaternary ammonium polymer which comprises inert non-basic and non-nucleophilic counter anions. The said methods and polymer cartridges allow the rapid preparation of suitable [18F]fluoride solution, which is also less basic to reduce the formation of byproducts, finally to increase radiochemical yield and purity of 18F-radiopharmaceuticals.
    Type: Application
    Filed: September 6, 2011
    Publication date: February 6, 2014
    Applicant: PIRAMAL IMAGING SA
    Inventors: Dae Yoon Chi, Byoung Se Lee, Sang Ju Lee, Jin-Sook Ryu, Seung Ju Oh
  • Patent number: 8641903
    Abstract: The present invention is related to a method to obtain reactive [18F] fluorides in an organic medium suitable for radiolabelling without any azeotropic evaporation step, by the use of a solid phase extraction column containing a modified non-ionic solid support.
    Type: Grant
    Filed: April 22, 2008
    Date of Patent: February 4, 2014
    Assignees: Trasis S.A., Universite de Liège
    Inventors: Samuel Voccia, Joël Aerts, Christian Lemaire, André Luxen, Jean-Luc Morelle, Gauthier Philippart
  • Publication number: 20130336870
    Abstract: 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.
    Type: Application
    Filed: April 15, 2013
    Publication date: December 19, 2013
    Applicant: Kurion, Inc.
    Inventors: Mark S. Denton, Walter T. Shmayda
  • Publication number: 20130302236
    Abstract: A gamma radiation source comprises 75Selenium wherein the 75Selenium is provided in the form of compounds, alloys or mixtures with one or more nonmetals which upon irradiation do not produce products capable of sustained emission of radiation which would unacceptably interfere with the gamma radiation of 75Selenium. A further gamma radiation source comprises 75Selenium wherein the 75Selenium is provided in the form of compounds, alloys or mixtures with one or more metals or nonmetals, the neutron irradiation of which does produce products capable of sustained emission of radiation which would acceptably complement the gamma radiation of 75Selenium. Further, the gamma radiation source may have components that are separately irradiated before being combined and the components may be of natural isotopic composition or of isotopically modified composition so that the subsequent radiation peaks may also be adjusted in relative frequency.
    Type: Application
    Filed: December 5, 2012
    Publication date: November 14, 2013
    Inventors: John J. Munro, III, Kevin J. Schehr
  • Patent number: 8574523
    Abstract: A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450° C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80° C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.
    Type: Grant
    Filed: April 5, 2011
    Date of Patent: November 5, 2013
    Assignee: UT-Battelle, LLC
    Inventors: Emory D. Collins, Guillermo D. Delcul, Rodney D. Hunt, Jared A. Johnson, Barry B. Spencer
  • Publication number: 20130136690
    Abstract: The present invention provides a method for the generation of 223Ra of pharmaceutically tolerable purity comprising i) preparing a generator mixture comprising 227Ac, 227Th and 223Ra; ii) loading said generator mixture onto a strong base anion exchange resin; iii) eluting said 223Ra from said strong base anion exchange resin using a first mineral acid in an alcoholic aqueous solution to give a first eluted 223Ra solution; iv) loading the 223Ra of the first eluted 223Ra solution onto a strong acid cation exchange resin; and v) eluting the 223Ra from said strong acid cation exchange resin using a second mineral acid in aqueous solution to provide a second eluted solution. The invention additionally provides products of corresponding purity and/or products obtained or obtainable by such a method.
    Type: Application
    Filed: April 29, 2011
    Publication date: May 30, 2013
    Applicant: ALGETA ASA
    Inventors: Jan Roger Karlson, Peer Børretzen
  • Patent number: 8440058
    Abstract: Method for concentrating nitrogen isotope to obtain a final product nitrogen, in which the stable nitrogen isotope, 15N, is concentrated, by low-temperature distillation of raw material nitrogen containing trace amounts of oxygen and argon using a plurality of distillation columns in a cascade arrangement. An argon-oxygen mixture is discharged from the bottom of the final column and 15N-concentrated nitrogen is extracted from a lower intermediate point of the final column. The flow rate of the argon-oxygen mixture discharged from the bottom of the final column is controlled based on the reading of a thermometer installed below the point where the final product 15N-concentrated nitrogen is extracted, thereby providing a stable nitrogen product.
    Type: Grant
    Filed: September 12, 2008
    Date of Patent: May 14, 2013
    Assignee: Taiyo Nippon Sanso Corporation
    Inventor: Hitoshi Kihara
  • Publication number: 20130115156
    Abstract: 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.
    Type: Application
    Filed: June 21, 2011
    Publication date: May 9, 2013
    Applicant: ENEA - AGENZIA NAZIONALE PER LE NUOVE TECNOLOGIE, L'ENERGIA E LO SVILUPPO ECONOMIC
    Inventors: Nicolas Ghirelli, Silvano Tosti, Pierre Trabuc, Fabio Borgognoni, Karine Liger, Alessia Santucci, Xavier Lefebvre
  • Patent number: 8383021
    Abstract: Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.
    Type: Grant
    Filed: November 12, 2009
    Date of Patent: February 26, 2013
    Assignee: Sandia Corporation
    Inventors: James L. Krumhansl, Tina M. Nenoff
  • Publication number: 20130045151
    Abstract: A method for providing 11C-labeled cyanides from 11C labeled oxides in a target gas stream retrieved from an irradiated high pressure gaseous target containing O2, wherein 11C labeled oxides are reduced with H2 in the presence of a nickel catalyst under a pressure and a temperature sufficient to form a product stream comprising at least about 95% 11CH4, the 11CH4 is then combined with an excess of NH3 in a carrier/reaction stream flowing at an accelerated velocity and the combined 11CH4 carrier/reaction stream is then contacted with a platinum (Pt) catalyst particulate supported on a substantially-chemically-nonreactive heat-stable support at a temperature of at least about 900° C., whereby a product stream comprising at least about 60% H11CN is provided in less than 10 minutes from retrieval of the 11C labeled oxide.
    Type: Application
    Filed: August 13, 2012
    Publication date: February 21, 2013
    Applicant: Brookhaven Science Associates, LLC
    Inventors: Dohyun Kim, David Alexoff, Sung Won Kim, Jacob Hooker, Richard A. Ferrieri
  • Publication number: 20130022525
    Abstract: 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.
    Type: Application
    Filed: July 16, 2012
    Publication date: January 24, 2013
    Inventors: Dennis B. ESHIMA, Mehmet Husnu, Henry Padgett, Thomas A. Klausing, Chad E. Bouton, Herman Benecke, Daniel B. Garbark
  • Patent number: 8357316
    Abstract: One gamma radiation source comprises 75Selenium or a precursor thereof, wherein the 75Selenium is provided in the form of one or more thermally stable compounds, alloys or mixtures with one or more nonmetals which upon irradiation do not produce products capable of sustained emission of radiation which would unacceptably interfere with the gamma radiation of 75Selenium. A further gamma radiation source comprises 75Selenium or a precursor thereof, wherein the 75Selenium is provided in the form of one or more thermally stable compounds, alloys or mixtures with one or more metals or nonmetals, the neutron irradiation of which does produce products capable of sustained emission of radiation which would acceptably complement the gamma radiation of 75Selenium.
    Type: Grant
    Filed: September 28, 2009
    Date of Patent: January 22, 2013
    Inventors: John J. Munro, III, Kevin J. Schehr
  • Patent number: 8329122
    Abstract: A method is presented for producing and isolating an isotopically enriched compound of a desired isotope from a parent radionuclide. The method includes forming, or placing, a precipitate containing a parent radionuclide of the desired daughter isotope in a first reaction zone and allowing sufficient time for the parent to decay into the desired gaseous daughter radioisotope. The method further contemplates collecting the desired daughter isotope as a solid in a second reaction zone through the application of temperatures below the freezing point of the desired isotope to a second reaction zone that is connected to the first reaction zone. Specifically, a method is presented for producing isotopically enriched compounds of xenon, including the radioactive isotope Xe-131m and the stable isotope Xe-131.
    Type: Grant
    Filed: July 1, 2009
    Date of Patent: December 11, 2012
    Assignee: The United States of America, as represented by the Department of Energy
    Inventor: Matthew G. Watrous
  • Publication number: 20120276003
    Abstract: The present disclosure relates to a compound comprising an oxygen-15 and a process for preparation thereof. It also relates to the use of the compound in positron and/or other nuclide imaging and use of the compound in obtaining a perfusion and/or metabolic image in an animal and/or human body. A process for preparing the compound comprises irradiating a compound comprising oxygen via irradiation energy in the range of 10 MeV to 430 MeV. The oxygen atom in the compound may then be allowed to be converted to an oxygen-15 positron nuclide through a photonuclear reaction. Provided that the molecular structure of the irradiated compound is not disrupted, a compound comprising an oxygen-15 is prepared.
    Type: Application
    Filed: September 25, 2011
    Publication date: November 1, 2012
    Applicant: Beijing Top Grade Medical Equipment Co., Ltd.
    Inventors: Jun Zeng, Qiyin Sun
  • Publication number: 20120270296
    Abstract: An isotope-doped nano-structure is provided. The isotope-doped nano-structure includes at least one isotope-doped nano-structure segment having at least two isotopes of the element. The at least two isotopes of the element are mixed uniformly in a certain proportion. The isotope-doped nano-structure can be used for isotope labeling one type of the unlabeled structures such as DNAs, proteins, glucoses, gluconic acids, starches, biotin enzymes, sorbitols, or organic amines. An isotope labeled structure is also provided.
    Type: Application
    Filed: July 3, 2012
    Publication date: October 25, 2012
    Applicants: HON HAI PRECISION INDUSTRY CO., LTD., TSINGHUA UNIVERSITY
    Inventors: SHOU-SHAN FAN, LIANG LIU, KAI-LI JIANG
  • Publication number: 20120244055
    Abstract: Disclosed is a novel adsorbent for use in a 99Mo/99mTc generator, which is a medical diagnostic radioisotope generator, and in a 188W/188Re generator, which is a therapeutic radioisotope generator. The adsorbent composed of sulfated alumina or alumina-sulfated zirconia exhibits adsorption capacity superior to that of conventional adsorbents, and is stable and is thus loaded in a dry state in an adsorption column so that the radioisotope 99Mo or 188W can be adsorbed. Thus, it is possible to miniaturize the column, and such a miniaturized column is small, convenient to use, and highly efficient, and extracts a radioisotope satisfying the requirements for pharmaceuticals, and thus can be useful for radioisotope generators extracting 99mTc or 188Re.
    Type: Application
    Filed: June 7, 2012
    Publication date: September 27, 2012
    Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
    Inventors: Jun Sig LEE, Hyon Soo HAN, Ul Jae PARK, Kwang Jae SON, Hyeon Young SHIN, Soon Bog HONG, Kang Duk JANG, Jong Sub LEE
  • Patent number: 8262950
    Abstract: Materials and methods of making low-sintering-temperature glass waste forms that sequester radioactive iodine in a strong and durable structure. First, the iodine is captured by an adsorbant, which forms an iodine-loaded material, e.g., AgI, AgI-zeolite, AgI-mordenite, Ag-silica aerogel, ZnI2, CuI, or Bi5O7I. Next, particles of the iodine-loaded material are mixed with powdered frits of low-sintering-temperature glasses (comprising various oxides of Si, B, Bi, Pb, and Zn), and then sintered at a relatively low temperature, ranging from 425° C. to 550° C. The sintering converts the mixed powders into a solid block of a glassy waste form, having low iodine leaching rates. The vitrified glassy waste form can contain as much as 60 wt % AgI. A preferred glass, having a sintering temperature of 500° C. (below the silver iodide sublimation temperature of 500° C.) was identified that contains oxides of boron, bismuth, and zinc, while containing essentially no lead or silicon.
    Type: Grant
    Filed: March 19, 2010
    Date of Patent: September 11, 2012
    Assignee: Sandia Corporation
    Inventors: Tina M. Nenoff, James L. Krumhansl, Terry J. Garino, Nathan W. Ockwig
  • Patent number: 8236277
    Abstract: A process comprises (a) combining (1) at least one base and (2) at least one metal carboxylate salt comprising (i) a metal cation selected from metal cations that form amphoteric metal oxides or oxyhydroxides and (ii) a carboxylate anion comprising from one to four alkyleneoxy moieties, or metal carboxylate salt precursors comprising (i) at least one metal salt comprising the metal cation and a non-interfering anion and (ii) at least one carboxylic acid comprising from one to four alkyleneoxy moieties, at least one salt of the carboxylic acid and a non-interfering, non-metal cation, or a mixture thereof; and (b) allowing the base and the metal carboxylate salt or metal carboxylate salt precursors to react.
    Type: Grant
    Filed: December 18, 2007
    Date of Patent: August 7, 2012
    Assignee: 3M Innovative Properties Company
    Inventor: Timothy D. Dunbar
  • Patent number: 8126104
    Abstract: 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.
    Type: Grant
    Filed: August 2, 2005
    Date of Patent: February 28, 2012
    Assignee: Battelle Memorial Institute
    Inventors: Robert E. Schenter, Dennis W. Wester, Glenn W. Hollenberg, Brian M. Rapko, Gregg J. Lumetta
  • Patent number: 8093178
    Abstract: Disclosed in a catalyst which enables to reduce the carbon monoxide concentration in a product gas to 5 ppm by volume or less when carbon monoxide in a raw material gas containing hydrogen and carbon monoxide is selectively oxidized. The catalyst comprises a support of an inorganic oxide and ruthenium loaded thereon, and the relative loading depth X(Ru) of ruthenium in the radial direction in a redial cross-section of the catalyst satisfies the requirement defined by the following formula (1) X(Ru)?15??(1).
    Type: Grant
    Filed: December 17, 2007
    Date of Patent: January 10, 2012
    Assignee: Nippon Oil Corporation
    Inventors: Yasuyuki Iwasa, Takaya Matsumoto
  • Publication number: 20120003135
    Abstract: 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.
    Type: Application
    Filed: January 4, 2010
    Publication date: January 5, 2012
    Inventors: Nicholas Vollendorf, Eric Fessler, Mark Pronley, Erik L. Storvik
  • Patent number: RE45703
    Abstract: The present invention relates to SiC nanostructures, including SiC nanopowder, SiC nanowires, and composites of SiC nanopowder and nanowires, which can be used as catalyst supports in membrane electrode assemblies and in fuel cells. The present invention also relates to composite catalyst supports comprising nanopowder and one or more inorganic nanowires for a membrane electrode assembly.
    Type: Grant
    Filed: October 2, 2014
    Date of Patent: September 29, 2015
    Assignee: OneD Material LLC
    Inventors: Yimin Zhu, Jay L. Goldman, Baixin Qian, Ionel C. Stefan
  • Patent number: RE46921
    Abstract: The present invention relates to SiC nanostructures, including SiC nanopowder, SiC nanowires, and composites of SiC nanopowder and nanowires, which can be used as catalyst supports in membrane electrode assemblies and in fuel cells. The present invention also relates to composite catalyst supports comprising nanopowder and one or more inorganic nanowires for a membrane electrode assembly.
    Type: Grant
    Filed: September 28, 2015
    Date of Patent: June 26, 2018
    Assignee: OneD Material LLC
    Inventors: Yimin Zhu, Jay L. Goldman, Baixin Qian, Ionel C. Stefan
  • Patent number: RE48084
    Abstract: The present invention relates to SiC nanostructures, including SiC nanopowder, SiC nanowires, and composites of SiC nanopowder and nanowires, which can be used as catalyst supports in membrane electrode assemblies and in fuel cells. The present invention also relates to composite catalyst supports comprising nanopowder and one or more inorganic nanowires for a membrane electrode assembly.
    Type: Grant
    Filed: June 25, 2018
    Date of Patent: July 7, 2020
    Assignee: ONED MATERIAL LLC
    Inventors: Yimin Zhu, Jay L. Goldman, Baixin Qian, Ionel C. Stefan