United States Patent Office

Total Page:16

File Type:pdf, Size:1020Kb

United States Patent Office Patented Jan. 2, 1951 2,536,347 UNITED STATES PATENT OFFICE . 2,536,34 PRODUCTION OF BASEC AMEMONUM URANY SULFATE AND URANUM OXDE Eugene O. Brimm, Kenmore, and Carleton N. Smith, Snyder, N. Y., assignors, by mesne as signments, to Union Carbide and Carbon Cor poration, a corporation of New York NoDrawing. Application October 14, 1944, Serial No. 558,726 4. Claims. (C. 23-145) 2. This invention relates to the manufacture of an alkali-containing uranium compound with oxides of uranium, and pertains more partic acid and an ammonium salt of such acid, while ularly to a method for making uranosic oxide maintaining the pH of such suspension or solu (U3O8) of a high degree of purity. tion within the range of 4 and 6, preferably Uranosic oxide may be produced by calcining 45 to 5. (heating in the air) tranium compounds which The proportion of annonium salt is not ordi contain no nonvolatile impurities, e. g. ammo narily Critical, except as explained hereinafter. nium diuranate, annonium uranyl carbonate, Good results are obtainable at annonium salt uranyl nitrate, uranyl sulfate, uranic acid, or concentrations corresponding to about 10% by uranium peroxide. 10 Weight of the water present; but this concern The usual processes for recovering uranium tration may be varied within wide limits, for from its ores yield a produce containing from example 5% to 15%. 32% to 10% sodium combined with the uranium The foregoing treatment may be conducted at as sodium uranate. As this sodium can not be room temperature, in which case it should Or. driven off by heat, its removal is a necessary 5 dinarily be continued for several hours, or at elie preliminary to the preparation of IranOsic oxide wated temperatures, e. g. 90° to 95 C., which by calcination. hasten the reactions. One method which has been proposed consists Upon completion of the reactions, the reac in digesting sodium uranate with a concentrated tion mixttire is filtered, ieaving a residue of solution of ammonium chloride, thereby replac 20 alkali-free uranium compounds. The residue ing the Sodium with an ammonium radical and may be Washed with hot water, preferably con producing sodium chloride which may be re taining ammonium Salt, for instance a 1% solu moved by filtration and washing. By repeating tion of the ammonium salt of the acid used in the digestion step several times, using fresh por the first, digesting, step. After washing, the tions of ammonium chloride Solution, nearly all 25 residue is dried and then calcined to produce of the sodium may be extracted and the result pure uranosic oxide, U3O8. Suitable calcining ing ammonium uranate may then be calcined to temperatures are those within the range 750° to obtain uranosic oxide, The principal short 9000 C. coming of this method for large scale use is that While Satisfactory results may be obtained it is slow and expensive. 30 With various acids, such as hydrochloric, nitric, Another method consists in dissolving the or acetic, superior results are obtainable by the Sodium uranate in acid and then adding annonia, use of Sulfuric acid and ammonium sulfate. to precipitate ammonium uranate. This method One reason for the particularly favorable re must likewise be repeated if a pure product is Sults of the use of sulfuric acid and ammonium desired. Sulfate is that, under the conditions just men A third method, described in Patent 120.714, 35 tioned, an insoluble basic ammonium uranyl Harvey A. Seil, comprises moistening sodium Sulfate is formed. This novel compound, the uranate with enough Sulfuric acid to combine existence of which we have verified by X-ray with the Sodium to form sodium sulfate or bi diffraction methods, has a formula, by analysis, sulfate, heating the resulting mixture, and ex 40 Corresponding approximately to tracting the sodium sulfate with water. This method may be used to remove most of the sodium, but it has a serious disadvantage in It is an Orange-yellow crystalline solid, insoluble that critical control of the time and temperature in Water but Soluble in dilute mineral acids. At of heating are necessary. Low temperatures or 45 temperatures above 100° C., the Water is re short times lead to incomplete removal of sodium moved to an extent dependent upon the temper and loss of uranium. On extraction. Too Ong a ature. The compound has no melting point, but time and too high a temperature result in in at high temperatures decomposes with loss of complete removal of sodium because of the re ammonia, and, at still higher temperatures loses action of sodium sulfate with uranosic oxide to 50 SO3, yielding uranosic oxide, U3O8. Decomposi form Sodiurn uranate. tion is rapid at 800° C. Or above, slower at According to this invention, the removal of 600-7000 C. Substantially all alkali metal is accomplished Other acids, such as nitric, hydrochloric, and without dissolving any great amount of uranium, acetic, do not form insoluble basic ammonium by treating (digesting) an aqueous Suspension of 55 uranyl compounds, but, rather, mixtures of 2,536,847 3 4. urany salts with hydrated uranic oxide and other sulfate which comprises mixing an acid soluble known compounds. oxidic uranium compound with sulfuric acid and Thus, in another aspect, this invention includes, ammonium sulfate, and maintaining the pH of as a new and useful composition of matter, basic the mixture between 4 and 6. ammonium uranyl sulfate, and a novel method 2. A method of making basic annonium uranyl of making such compound by reacting upon an sulfate which comprises mixing a hot aqueous acid-soluble oxidic uranic compound, such as So suspension of Sodium uranate with Sulfuric acid dium uranate, with sulfuric acid and ammonium. and ammonium sulfate, and maintaining the pH sulfate. of mixture between 4.5 and 5. To form the desired basic ammonium uranyl O sulfate, it is of course necessary that enough 3. A method of making uranosic oxide which ammonium sulfate be present in the reaction comprises treating a hot aqueous suspension of mixture to satisfy the formula, given above of such Sodium uranate with Sulfuric acid and am basic ammonium uranyl sulfate. An excess of monium sulfate at a pH between 4.5 and 5 to ammonium salt is preferred. form a water-insoluble basic ammonium uranyl In a typical specific application of this invene 5 Sulfate, filtering off the liquid, and calcining the tion, a quantity of powdered Sodium uranate basic ammonium uranylsulfate. (6.8% Na2O) corresponding to 2649 pounds of 4. A method of making uranosic oxide which U3O8 was added to a 10% solution of ammonium comprises treating in aqueous medium a uranate sulfate containing 1686 pounds of ammonium Sul 20 with an acid and an ammonium salt of Such acid, fate. The resulting aqueous Suspension was while maintaining the pH of said medium be heated to about 90° to 95° C. and sulfuric acid tween 4 and 6, filtering the liquid from the re was added slowly, as the suspension was stirred, sulting solid, and calcining said solid. until the pH remained constant at 4.4. The EUGENE O. BRIMM. product was filtered and the filter cake washed 25 CARLETON N. SMITH, With hot 1% ammonium sulfate Solution. The washed cake was dried, then calcined for about REFERENCES CTED an hour at 1000° C. The calcined product con The following references are of record in the tained 99.24% U3O8. and 0.03% Na2O. file of this patent: The loss of uranium by solution in the acid and 30 Salt solution is very slight, under least favorable Mellor, “Inorganic and Theoretical Chemistry,' conditions being under 1.5% and under best con vol. 12, page 108, Longmans, Green and Co., LOn ditions being 0.5% or less. Calcination readily don (1932). (Copy in Div. 59.) eliminates all of the ammonia and substantially Lowry, “Inorganic Chemistry,' page 174, Sec all of the Sulfur. Sulfur contents are Ordinarily 35 Ond edition (1931). MacMillan and Co., London. well under 0.1%. (Copy in Div. 59.) . We claim: 1. A method of making basic ammonium uranyl .
Recommended publications
  • Used As a Reference in Ou 1 Ri)
    6307 U-003-307 .8 SUMMARY TECHNICAL REPORT FOR THE PERIOD APRIL 1, 1959 TO JUNE 30, 1959 - (USED AS A REFERENCE IN OU 1 RI) 07/20/59 NLCO-790 NLO 75 REPORT SUMMARY TECHNICAL REPORT I. For t le Period April 1, 1959 to June 30, 1959 I I AEC RESEARCH AND DEVELOPMENT REPORT NLCO- 790 -w6307 Technology -Feed Materials ..:i (M- 3679, 22nd Ed.) 8 - SUMMARY TECHNICAL REPORT FOR THE PERIOD - APRIL 1, 1959 TO JUNE 30, 1959 F. L. CUTHBERT, DIRECTOR c. E. CROMPTON, ASSOCIATE DIRECTOR TECHNICAL DIVISION ._. EDITED BY JOHN W. SIMMONS Date of Issuance: July 20, 1959 NATIONAL LEAD COMPANY OF OHIO p ' I Box 158, Cincinnati 39, Ohio *I Contract No. AT(30 -1) -1156 "630'7 -3- Page No. .' - .. SUMMARY. .. '. 7 - Feed Materials Evaluation :...I '. 11 I. .- . .. 2. Selective Digestion . :-;. 17 ,>+ 3. Bondingin theTri-n-butylPhosphate-H20-U-AcidSy$tem . 27 4. Extraction Column Control . ..: . 37 5. Activation of Pot-Produced Orange Oxide . .' . 41 . Hydrofluorination of Sodium-ContamGated Uranium Oxides. 41 Thermal Decomposition of AnhydibusUranylSulfate . 44 i .. 6. ADU ("Ammonium Diuranate") Process Development . 49 . Laboratory Determination of Impurity Decontamination by an ADU Process . 49 '- Thermobalance Hydrofluorination Investigation of Pilot Plant ADU . 52 7. Analyses of Variations in Visually Determined Derby Grades . 57 8. Recovery of Uranium from a Mixture of Uranium, Magnesium, and Magnesium Fluoride . 61 9. Scrap Processing by an Aqueous UF4 Process . 67 Labomtory Preparation of Green Salt from Plant-Produced UAP and Black Oxide . 67 Green Salt Preparation from Pickle Liquor, Black Oxide, and Reduction Pot Residues . 71 io.
    [Show full text]
  • Spectroscopic Signatures of Uranium Speciation for Forensics
    UNLV Theses, Dissertations, Professional Papers, and Capstones May 2017 Spectroscopic Signatures of Uranium Speciation for Forensics Nicholas Wozniak University of Nevada, Las Vegas Follow this and additional works at: https://digitalscholarship.unlv.edu/thesesdissertations Part of the Chemistry Commons Repository Citation Wozniak, Nicholas, "Spectroscopic Signatures of Uranium Speciation for Forensics" (2017). UNLV Theses, Dissertations, Professional Papers, and Capstones. 3063. http://dx.doi.org/10.34917/10986257 This Dissertation is protected by copyright and/or related rights. It has been brought to you by Digital Scholarship@UNLV with permission from the rights-holder(s). You are free to use this Dissertation in any way that is permitted by the copyright and related rights legislation that applies to your use. For other uses you need to obtain permission from the rights-holder(s) directly, unless additional rights are indicated by a Creative Commons license in the record and/or on the work itself. This Dissertation has been accepted for inclusion in UNLV Theses, Dissertations, Professional Papers, and Capstones by an authorized administrator of Digital Scholarship@UNLV. For more information, please contact [email protected]. SPECTROSCOPIC SIGNATURES OF URANIUM SPECIATION FOR FORENSICS By Nicholas Robert Wozniak Bachelors of Science – Chemistry Bachelors of Science – Physics Hope College 2012 A dissertation submitted in partial fulfillment of the requirements for the Doctor of Philosophy – Radiochemistry Department of Chemistry College of Sciences The Graduate College University of Nevada, Las Vegas May 2017 Dissertation Approval The Graduate College The University of Nevada, Las Vegas April 14, 2017 This dissertation prepared by Nicholas Robert Wozniak entitled Spectroscopic Signatures of Uranium Speciation for Forensics is approved in partial fulfillment of the requirements for the degree of Doctor of Philosophy – Radiochemistry Department of Chemistry Ken Czerwinski, Ph.D.
    [Show full text]
  • Technology of Uranium Purification. Impurities Decontamination
    TECHNOLOGY OF URANIUM PURIFICATION. IMPURITIES DECONTAMINATION FROM URANYL CHLORIDE BY EXTRACTION WITH TRI-n-OCTYLAMINE IN THE PRESENCE OF THIOUREA AS COMPLEXING LIGAND. AIcídio Abrão PUBLICAÇÃO IEA 458 DEZEMBRO/1976 CEQ 69 PUBL. I EA 45B OEZEMBRO/1976 CEQ 68 TECHNOLOGY OF URANIUM PURIFICATION. IMPURITIES DECONTAMINATION FROM URANYL CHLORIDE BY EXTRACTION WITH TRI-n-OCTYLAMINE IN THE PRESENCE OF THIOUREA AS COMPLEXING LIGAND. Alcidio Abrio CENTRO DE ENGENHARIA QUÍMICA (CEQ) INSTITUTO DE ENERGIA ATÔMICA SAO PAULO - BRASIL APHOVAOO PARA PUBLICAÇÃO EM NOVEMBRO/1976 CONSELHO DELIBERATIVO Eng? HMcio Modnto da Costa Eng? Ivano Humbert Marchesi Prof. Admar Cervellim Prof. Sérgio Matcarenhai de Oliveira Dr. Klaus Reinach Or. Roberto D'Utra Vai SUPERINTENDENTE Prof. Dr, Ròmulo Ribe/r.» Pierori INSTITUTO DE ENERGIA ATÔMICA Caixa Postal 11.049 (Pinheiros) Cidade Universitária "Armando de Sallei Oliveira" SAO PAULO - BRASIL NOTA Este trabalho foi confe-ido p«lo autor depois de composto e sua redação tt'i conforme o original, sem qualquer correçáo ou mudança. TECHNOLOGY OF URANIUM PURIFICATION. IMPURITIES DECONTAMINATION FROM URANYL CHLORIDE BY EXTRACTION WITH TRI-n-OCTYLAMINE IN THE PRESENCE OF THIOUREA AS COMPLEXING LIGAND- Alcidio Abrão ABSTRACT The extraction of jranyl chloride by trinoctyiamme ITOAI and in decontamination from several impurities v»,th the aid of thiourea is investigated The effect of thiourea as a complexing agsnt, giving rise to unextracted canonic species of several metallic ion and its consequence in the extraction of uranyl chlonde from hydrochloric acid with TOA benzene!x'lenel is described Also, the effect of an acidified thiourea solution for scrubbing the organic phase loaded with uranyl chloride is studied INTRODUCTION The long chain amines had shown to be excellent extractants for various inorganic rid organic acds, and for a great number of anionic metallic complexes Smith and Page'441 had indicated the association properties of high weight amines w.th acids.
    [Show full text]
  • Design of a Small Aqueous Homogeneous Reactor for Production of 99Mo Improving the Reliability of the Supply Chain
    Design of a small Aqueous Homogeneous Reactor for production of 99Mo Improving the reliability of the supply chain S. Rijnsdorp Master Thesis DESIGNOFASMALL AQUEOUS HOMOGENEOUS REACTOR FOR PRODUCTION OF 99MO IMPROVING THE RELIABILITY OF THE SUPPLY CHAIN by S. Rijnsdorp BSc in partial fulfillment of the requirements for the degree of Master of Science in Applied Physics at Delft University of Technology, to be defended on Tuesday September 2, 2014 at 09:30. faculty Applied Sciences department Radiation Science and Technology section Nuclear Energy and Radiation Applications supervisors Dr.ir. J.L. Kloosterman Dr.ir. M. Rohde thesis committee Dr.ir. J.L. Kloosterman TU Delft, Applied Sciences, RST, NERA Dr.ir. M. Rohde TU Delft, Applied Sciences, RST, NERA Dr. Eng. L.M. Portela TU Delft, Applied Sciences, ChemE, TP ABSTRACT Medical isotopes are used worldwide for medical imaging and treatment of patients with different kinds of diseases, for example thyroid diseases and blood disorders. The most widely used radio- isotope for medical imaging is 99mTc, a daughter nuclide of 99Mo. Annually, around 400,000 diag- nostical treatments using 99mTc are carried out in the Netherlands. The characteristic aspect that makes 99mTc so useful for medical imaging is also the challenge: 99mTc has a half-life of approximately 6 hours. Because also the parent nuclide 99Mo has a relatively short half-life (66 hours), a continuous production and supply is needed. Recently, a number of events occurred, disrupting the supply, which led to the wish for a more reliable production method of radioisotopes. Currently, the entire world demand is produced in 5 reactors, meaning that an unplanned outage of one or more reactors will immediately decrease the supply of 99Mo.
    [Show full text]
  • Present Status of the Use of Leu in Aqueous Reactors to Produce Mo-99
    PRESENT STATUS OF THE USE OF LEU IN AQUEOUS REACTORS TO PRODUCE MO-99 Russell M. Ball Technology Commercialization International, 1620 Belfield Place, Lynchburg, VA 24503, FAX: 804/384-1572 V.A. Pavshook and V.Ye.Khvostionov Russian Research Center - Kurchatov Institute, Moscow, 123182, Russia Presented at the 1998 International Meeting on Reduced Enrichment for Research and Test Reactors October 18 - 23, 1998 Sao Paulo, Brazil PRESENT STATUS OF THE USE OF LEU IN AQUEOUS REACTORS TO PRODUCE MO-99 Russell M. Ball, Technology Commercialization International, 1620 Belfield Place, Lynchburg, VA 24503, FAX: 804/384-1572 and V.A. Pavshook and V.Ye.Khvostionov, Russian Research Center - Kurchatov Institute, Moscow, 123182, Russia Abstract: An operating aqueous homogeneous reactor, the ARGUS at Kurchatov Institute, has been used to produce fission product molybdenum-99 (Mo-99), widely used in nuclear medicine to produce technetium-99m (Tc-99m). The Mo99 has been extracted from the sulfate solution using an organic sorbent after operation at 1 kW/liter. After purification, the material has been assayed and the result is well within required specification of the US Pharmacopaeia. Operation with LEU is planned to determine if any additional purification steps are required. Calculations are presented to show the sources and quantity of alpha activity when LEU is used. 1.0 BACKGROUND Nuclear medicine has relied on Tc-99m and its parent Mo-99 for diagnostics since its development at Brookhaven National Laboratory (USA) in 19641. Over 35,000 procedures per day using Tc-99ni created by Mo-99 are performed throughout the world. The major source of the Mo-99 is from fission of U-235.
    [Show full text]
  • Health Hazard Evaluation Report 81-055-954
    t H J l: ia .1 i~ ~l 1­~i ~J ( Health Hazard HETA 21-055-954 Evaluation COTTER CORPORATION CA~ON CITY, COLORADO Report PREFACE The Hazard Evaluations and Technical Assistance Branch of NIOSH conducts field investigations of possible health hazards 1n the workplace. These investigations are conducted under the authority of Section 20{a){6) of the Occupational Safety and Health Act of 1970, 29 U.S.C. 669(a){6) which authorizes the Secretary of Health and Human Services, following a written re<Juest from any employer or authorized representative of employees, to determine whether any substance normally found in the place of employment has potentially toxic effects in such concentrations as used or found. The Hazard Evaluations and Technical Assistance Branch also provides, upon re<Juest, medical, nursing, and industrial hygiene technical and consultative assistance (TA) to Federal, state, and local agencies; labor: industry and other groups or individuals to control occupational health hazards and to prevent related trauma and disease. Mention of company names or products does not constitute endorsement by the National Institute for Occupational Safety and Health. ) HETA 81-055-954 NIOSH INVESTIGATORS: MTA 80-107 Michael J. Thun MD September 1981 Dean B. Baker MD, MPH Cotter Corporation Alexander B. Smith MO, MS l Canon City, Colorado William Halperin, MD, MPH S~ARY In October, 1980, the National Institute for Occupational Safety and Health (NIOSH) was asked by the Oil, Chemical and Atomic Workers International Union and its Local 2-844 to evaluate the health effects of exposure to uranium ore dust and to yellowcake at The Cotter Uranium Mill, Canon City, Colorado.
    [Show full text]
  • Advances in Uranium Refining and Conversion Iaea, Vienna, 1987 Iaea-Tecdoc-420
    IAEA-TECDOC-420 PROCEEDINGS OF A TECHNICAL COMMITTEE MEETING ON ADVANCE URANIUSN I M REFININ CONVERSIOD GAN N ORGANIZEE TH Y DB INTERNATIONAL ATOMIC ENERGY AGENCY AND HEL VIENNAN D» , 7-10 APRIL 1986 A TECHNICAL DOCUMENT ISSUEE TH Y DB INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 198? The IAEA doe t normallsno y maintain stock f reportso thisn i s series. However, microfiche copies of these reports can be obtained from ClearinghousS I N I e Internationa! Atomic Energy Agency Wagramerstrasse5 P.O. Box 100 A-1400 Vienna, Austria Orders shoul accompaniee db prepaymeny db Austriaf to n Schillings 100,- in the form of a cheque or in the form of IAEA microfiche service coupons which may be ordered separately from the I MIS Clearinghouse. ADVANCES IN URANIUM REFINING AND CONVERSION IAEA, VIENNA, 1987 IAEA-TECDOC-420 Printe IAEe th AustriAn i y d b a May 1987 FOREWORD One of the most important steps in the Nuclear Fuel Cycle is the Uranium Refining and conversion which goes from the yellow-cake to three different products: uranium dioxid, natura) O (U el metallic uraniu) (U m and uranium hexafluoride (UF ) . Although its added value is small, may 6 be 2-4% of the total cost of front-end, it is decisive for producing fuel r botfo h type f reactorso s : natural uranium (Magno d Canduan x d )an enriched uranium (LWR) n thiI . e cycls e uraniuth ste th ef o p m hexafluoride is produced which is very important for the enrichment of uranium. e totaTh l volum f thio e s industry e presenth t a , t time nearls i , f o y 40,000t U per year and at the end of the present century it would have reached the 60.000t U/a level.
    [Show full text]
  • A Quantitative Raman and Density Functional Theory Investigation of Uranyl Sulfate Complexation and Liquid-Liquid Phase Separation Under Hydrothermal Conditions
    A Quantitative Raman and Density Functional Theory Investigation of Uranyl Sulfate Complexation and Liquid-Liquid Phase Separation under Hydrothermal Conditions by Christopher D. Alcorn A Thesis presented to The University of Guelph In partial fulfillment of the requirements for the degree of Doctor of Philosophy In Chemistry Guelph, Ontario, Canada © Christopher D. Alcorn, May 2018 ABSTRACT A Quantitative Raman and Density Functional Theory Investigation of Uranyl Sulfate Complexation and Liquid-Liquid Phase Separation under Hydrothermal Conditions Christopher D. Alcorn Advisor: University of Guelph, 2017 Professor P. R. Tremaine State-of-the-art Raman spectroscopic techniques have been employed to quantitatively measure (i) the temperature-dependent Raman properties and thermal decomposition of several non-complexing anions in acidic and neutral solutions at temperatures up to 400 oC, (ii) the first and second formation constants of the uranyl sulfate system from 25 – 375 °C, and (iii) the speciation and concentrations of liquid-liquid phase separated mixtures of uranyl sulfate and sulfuric acid up to 425 °C. - The results of the first study show the stability followed the order HSO4 (stable) > - - - o ReO4 > ClO4 > CF3SO3 in acidic solution, with half-lives over 7 h at 300 C. In neutral - - - - solutions, the order was HSO4 (stable) > CF3SO3 > ReO4 > ClO4 , with half-lives over 8 h at 350 oC. Raman vibrational frequencies and relative Raman scattering coefficients of these anions were determined, providing temperature-dependent data for frequency calibration and for determining the efficiency of these anions to scatter Raman light. To our knowledge, this manuscript is the first of its kind to report quantitative values using this methodology.
    [Show full text]
  • 1200-09-02 Rev. 0, SHINE Target Solution Qualification Program
    ENCLOSURE 2 ATTACHMENT 7 SHINE MEDICAL TECHNOLOGIES, INC. SHINE MEDICAL TECHNOLOGIES, INC. APPLICATION FOR CONSTRUCTION PERMIT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 1200-09-02, REVISION 0 SHINE TARGET SOLUTION QUALIFICATION PROGRAM 21 pages follow 1200-09-02 Rev. 0 SHINE Target Solution Qualification Program Document Owner: Engineering Document Contact: Catherine Kolb RM Approval: Bill Hennessy on 10/26/2014 via SharePoint Effective Date: 10/31/2014 Periodic Review Date: 10/30/2017 Training Required: None Program Page 1 of 21 1200-09-02 Rev. 0 SHINE Target Solution Qualification Program REVISION LOG Revision # Description of Changes 0 Original Issue Program Page 2 of 21 1200-09-02 Rev. 0 SHINE Target Solution Qualification Program TABLE OF CONTENTS 1 Introduction ............................................................................................................................ 4 2 Target Solution History .......................................................................................................... 5 3 Target Solution Physical Parameters .................................................................................... 6 4 SHINE Facility Process Overview .......................................................................................... 7 5 Lab-scale Testing of Target Solution ................................................................................... 13 6 Specifications ......................................................................................................................
    [Show full text]
  • Mo-99 2014 TOPICAL MEETING on Conversion of Uranyl Sulfate
    Mo-99 2014 TOPICAL MEETING ON MOLYBDENUM-99 TECHNOLOGICAL DEVELOPMENT June 24-27, 2014 Hamilton Crowne Plaza Washington D. C. Conversion of Uranyl Sulfate Solution to Uranyl Nitrate Solution for Processing in UREX Megan E. Bennett, Delbert L. Bowers, Candido Pereira, George F. Vandegrift Chemical Sciences and Engineering Division Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 ABSTRACT In 2016, the Canadian research reactor at Chalk River will no long irradiate targets for 99Mo production, causing a worldwide shortage of 99mTc, unless reliable, alternative production methods are developed. SHINE Medical Technologies is developing a production method using a deuterium-tritium (DT) neutron generator and a non-critical aqueous solution of low enriched uranium (LEU) in the form of uranyl sulfate solution. In this process, the recycling of uranium solution is necessary for the next irradiation. It has been proposed that the UREX purification process be used to recycle the uranyl sulfate solution; however, UREX requires a uranyl nitrate solution. Uranyl sulfate solutions do not perform well in UREX, because sulfate forms a strong complex with the uranyl ion and uranyl cannot be preferentially extracted; therefore, the uranyl sulfate solution must be converted to nitrate. A precipitation procedure for the conversion of uranyl sulfate solution to uranyl nitrate solution is discussed. 1. Introduction The availability of metastable technetium-99 (99mTc) is critical to the medical community; it is used in more than 80% of nuclear medicine diagnostic tests, or approximately 70,000 medical imaging procedures throughout the world daily [1]. In 2009, It was reported that Canada’s Chalk River nuclear reactor and the Netherlands’ High Flux reactor produce approximately 85% of Europe’s and North America’s 99mTc supply [2].
    [Show full text]
  • United States Patent (19) 11 Patent Number: 5,910,971 Ponomarev-Stepnoy Et Al
    USOO5910971A United States Patent (19) 11 Patent Number: 5,910,971 Ponomarev-Stepnoy et al. (45) Date of Patent: Jun. 8, 1999 54 METHOD AND APPARATUS FOR THE 56) References Cited PRODUCTION AND EXTRACTION OF MOLYBDENUM-99 U.S. PATENT DOCUMENTS 4,284,472 8/1981 Pomares et al. ........................ 376/186 75 Inventors: Nikolai N. Ponomarev-Stepnoy; 5,596,611 1/1997 Ball ......................................... 376/189 Vladimir A. Pavshook; Grigoriy F. Bebikh; Vladimir Ye. Khvostionov; Primary Examiner Daniel D. Wasil Peter S. Trukhlyaev; Ivan K. Attorney, Agent, or Firm-Robert W. Becker & Associates Shvetsov, all of Moscow, Russian Federation 57 ABSTRACT The current invention involves a means for the production 73 Assignee: TCI Incorporated, Albuquerque, N.M. and extraction of the isotope molybdenum-99 for medical purposes in a waste free, Simple, and economical process. 21 Appl. No.: 09/028,183 Mo-99 is generated in the uranyl sulphate nuclear fuel of a homogeneous Solution nuclear reactor and extracted from 22 Filed: Feb. 23, 1998 the fuel by a solid polymer Sorbent with a greater than 90% (51) Int. Cl." ....................................................... G21G 1/02 purity. The Sorbent is composed of a composite ether of a 52 U.S. Cl. ............................................. 376/189; 376/186 maleic anhydride copolymer and O-benzoin-Oxime. 58 Field of Search ..................................... 376/186, 189, 376/.311, 354-358 13 Claims, 3 Drawing Sheets Solution Mo-99 Accumulation Reactor in Absorber Radioactive Byproducts Uranyl Sulfate U.S. Patent Jun. 8, 1999 Sheet 1 of 3 5,910,971 Fxtracted Tradiation Target Reactor 7 U235 or MO98 Radioactive Byproducts F.G.
    [Show full text]
  • Aqueous Homogeneous Reactors
    Part I AQUEOUS HOMOGENEOUS REACTORS JAMES A . LANE, Editor Oak Ridge National Laboratory 1. Homogeneous Reactors and Their Development 2. Nuclear Characteristics of One- and Two-Region Homogeneous Reactors 3. Properties of Aqueous Fuel Solutions 4. Technology of Aqueous Suspensions 5. Integrity of Metals in Homogeneous Reactor Media 6. Chemical Processing 7. Design and Construction of Experimental Homogeneous Reactors 8. Component Development 9. Large-Scale Homogeneous Reactor Studies 10. Homogeneous Reactor Cost Studies AUTHORS E. G . BOHLMANN H . F. MCDUFFII: P . R. KASTEN R. A. McNEES J. A. LANE C . L. SEGASER J. P. McBRIDE I . SPIEWAK D. G. THOMAS CONTRIBUTORS B. M . ADAMSON S . I . KAPLAN S. E. BEALL N. A. KROHN W. E . BROWNING C. G. LAWSON W . D . BURCH R. E. LEUZE R. D . CHEVERTON R. N. LYON E . L . COMPERE W. T. MCDUFFEE C . H. GABBARD L. E . MORSE J. C . GRIESS S. PETERSON D . B . HALL R. C. ROBERTSON E. C . RISE H. C. SAVAGE G. H. JENKS D. S. TOOMB J. C . WILSON PREFACE This compilation of information related to aqueous homogeneous reactors summarizes the results of more than ten years of research and development by Oak Ridge National Laboratory and other organizations . Some 1500 technical man-years of effort have been devoted to this work, the cost of which totals more than $50 million . A summary of a program of this magnitude must necessarily be devoted primarily to the main technical approaches pursued, with less attention to alternate approaches . For more complete coverage, the reader is directed to the selected bib- liography at the end of Part I .
    [Show full text]