Preparation of Anhydrous Uranium Tetrachloride and Measurements on Its Magnetic Susceptibility

Total Page:16

File Type:pdf, Size:1020Kb

Preparation of Anhydrous Uranium Tetrachloride and Measurements on Its Magnetic Susceptibility Journal of NUCLEAR SCIENCE and TECHNOLOGY, 8 〔9〕, p. 498~502 (September 1971). Preparation of Anhydrous Uranium Tetrachloride and Measurements on Its Magnetic Susceptibility Tetsuhiko YOSHIMURA*, Chie MIYAKE* and Shosuke IMOTO* Received May 24, 1971 The reaction of UO2 with CCl4 vapor was carried out in a vacuum of 10-5 mmHg at 500℃ in order to prepare UCl4 of high purity. The lattice parameters were calculated from X-ray analysis to be a0=8.278±0.002, c0=7.460±0.009. The product thus ohtained was verified by chemical and X-ray analyses to be of anhydride form. The magnetic susceptibility was measured over the temperature range from liquid N2 to liquid He temperature, which revealed a deviation from the straight 1/X-T relation toward lower temperature. and that the anhydrous compound had ortho- I. INTRODUCTION rhombic symmetry. Since the same morpho- In the U-Cl system, there are known to logy may also exist for the chloride also, the exist four compounds, UCl3, UCl4, UCl5 and UCl4 is required to be of high purity. UCl6. Their chemical, physical and thermo- Table 1 Physical properties of UCl4 dynamic properties have been extensively investigated(1)(2) as well as those of the fluo- rides. Among these compounds UCl4 is used as the starting material for the synthesis of various uranous complexes, for its high solubility in many organic polar solvents such as methanol, ethanol, acetone, as reported by Selbin et al. (3)~(5) and Bagnall et al. (6) This com- pound is also used as the starting material for the preparation of UC(7), UN, US2(1)(8),USe2(1) etc. for its high reactivity. It is subjected to sol- gel treatment in the form of hydrochloric acid solution, from which UO2 crystal with high purity can be prepared. The high vapor pressure of UCl4 at relatively low temperature suggests that it should be useful for non- aqueous reprocessing of spent fuel. The physical properties of UCl4 are shown in Two distinct methods are available for Table 1, together with the results of X-ray preparing UCl4: analysis measured by Staritzky(9). (1) Gas phase reaction in which the vapor However, UCl4 is so hygroscopic as to be of a chlorinating reagent such as HCl, deliquescent with a partial pressure of any- Cl2, CCl4, SOCl2 is made to react with thing more than 2 mmHg of water vapor in uranium oxide at elevated temperature; the atmosphere, and thus a dry box is always (2) Liquid phase reaction in which uranium needed for its handling. Concerning ThCl4, oxide at lower temperature is refluxed which is also very hygroscopic, it has been with a halogenating reagent such as reported that its tetragonal symmetric crystal, CCl4, CCl2=CClCCl3 (hexachloropropene) which is the form most commonly encounter- or CCl3CCl3 (hexachloroethane). In labo- ed and which is isomorphous with UCl4 has * Department of Nuclear Engineering, Faculty of been found to be really a hydrated compound, Engineering, Osaka University, Suita-shi, Osaka. -22- Vol. 8, No. 9 (Sep. 1971) 499 ratory scale, the most common method purities to be: C<15, N<30, F<10, Mg 4, Al utilizes the reaction between UO3 and 40, Si<50, Cl<10, Ca<10, Cr 10, Fe 10, Ni 10, hexachloropropene. Cu 4, Mo<3, Ca 0.3, Sn 3, Pb 3, in ppm. In this study, in order to obtain UCl4, with Spectrograde CCl4, by E. Merck was used. high purity, the former principle was adopted: 2. Preparation i. e., the reaction between UO2 and UCl4, at The apparatus for the reaction is shown high temperature. The principal reaction is in Fig. 1. In the quartz reaction tube in- UO2+CCl4→UCl4+CO2. serted in the furnace are arranged end to This method has the advantage that impurities end four sections of quartz tube each about are not introduced from the outside of system, 10cm long, which serve to collect individual and also that control of the amount of the fractions of the deposited products. The end higher chlorides is possible by applying suit- section is closed at its extremity and it carries able conditions. The purity of the product a quartz boat containing about 2g of UO2 can be raised by repeated sublimation and sample. During the reaction the temperature precipitation. is usually kept higher in the furnace A(500℃) As a representative property of UCl4, thus than in B(200℃). The glass ampoule in the prepared, we measured the magnetic suscep- bulge E of the reaction tube contains liquid tibility down to liquid He temperature to CCl4, previously distilled and trapped at solid extend the data obtained by Bommer(12), CO2 temperature, and packed in 10-3 mmHg Dawson(13) and Stoenner et al. (14), who only of vacuum. The magnetic hammer is padded measured down to liquid N2 temperature. with teflon sheet. When the vacuum reached about 10-5 mmHg and the temperature of the II. EXPERIMENTAL sample attained 500℃, the cock F was closed, The mechanism of the reaction of UO2 and the reaction between UO2 and CCl4 was with CCl4, vapor is described elsewhere(1) in initiated by breaking the glass ampoule with detail. the magnetic hammer, and gently heating The principal reaction is the bulge in order to promote the vaporiza- UO2+CCl4→UCl4+CO2. tion of CCl4. As soon as UCl4 was formed The competitive reactions are: by reaction, it immediately sublimed on account of its high vapor pressure of 0.64 UO2+CCl4一>UOCl2+COCl2 mmHg at 500℃, and deposited on the wall of UOCl2+CCl4→UCl4+COCl2 the section of tube next to that carrying the UO2+2COCl2→UCl4+2CO2 boat. It took about 4hr to complete the COCl2→CO+Cl2 reaction, i. e. to entirely consume the UO2 in UCl4+1/2Cl2→UCl5. the boat. While the reaction was incomplete, Besides, at 100゜~175℃ in high vacuum, UCl5 an intermediate product UOCl2 remained in undergoes a disproportionation reaction: 2UCl5→UCl4+UCl6 And at about 170℃, UCl6 decomposes into UCl4 and Cl2: UCl6→UCl4+Cl2 Taking these circumstances into account, the preparation of UCl4 was carried out as described below. 1. Materials The UO2 was supplied by Sumitomo Metal Mining Co. Ltd. The O/U ratio was 2.02, Fig. 1 Apparatus for reaction and and spectrometric analysis revealed the im- vacuum sublimation -23- 500 J. Nucl. Sci. Technol., the boat, which was confirmed by X-ray analysis is as follows: analysis. The UCl4, crystals thus obtained Found U:61.6±0.2, Cl:38.1±0.1, Total:99.7% had a blackish-violet color at high temper- Calculated U: 62.66, Cl:37.34% ature, but which turned dark green at room This data reveales that the UCl4 obtained temperature. When the furnace B was kept was anhydrous, which agrees with the result somewhat cooler, i.e. 100゜~150℃, a reddish- of X-ray analysis. Contamination by higher brown colored UCl5 crystallized on the lower chlorides was also exceedingly low. No temperature sections, as well as the UCl6, of marked difference in analytical data were blackish green color. The UCI6 was analyzed seen between the recycled and non-recycled by thermogravimetry, which revealed that products. The X-ray analyses were carried Cl2 was released by decomposition at about out by powder camera on samples enclosed 170°C. After the reaction tube was cooled, in a glass capillary in a dry box, and by it was evacuated to remove reaction gases diffractometry on samples covered with poly- such as COCl2 and residue CCl4, then it was vinyl chloride sheet. filled with Ar gas. The cock F was again closed and the reaction tube was separated 4. Susceptibility Measurement and brought into a dry box which was pre- Measurements of susceptibility on the UCl4, viously filled with Ar gas and dried with were made by the Faraday method over the P2O5 powder. The dry box was constantly temperature range of 4.2~80K in a field of swept with Ar gas during the handling of about 10 koe. The temperature was measur- the product. In certain runs the process was ed with both a Au-Co/Cu thermocouple and recycled, the UCl4 thus obtained being again carbon resistance. A recycled sample was sublimed in the same apparatus for recrystal- chosen. It was sealed in a glass tube filled lization on the wall in vacuum. with He gas. After the measurement on 3. Analysis the sample, the glass tube without the samples was blank tested down to 4.2K in order to The uranium content of the UCl4, was determined by the gravimetric analysis, using correct the result of measurement. The sus- what is known as the ammonia method (15). ceptibility did not vary over a range of magnetic field between 2 and 11.6 koe, which After all the uranous ion was oxidized to uranyl ion by the addition of dilute nitric indicated that no ferromagnetic impurities acid, ammonia was added to the solution, were present in the sample. The values of then the precipitate of ammonium diuranate magnetic susceptibility thus obtained were was filtered, dried and ignited. The ash, also corrected for the diamagnetism(13) caused U3O8, was weighed, and its content confirmed by the completely filled cores, adopting values by X-ray anlysis. of 22.9×10-6 for Cl- and 31.5×10-6 for U(IV). The chlorine content of UCl4 was deter- III. RESULTS AND DISCUSSION mined by potentiometric titration, using a AgNO3 standard solution. This reaction is 1. X-ray Analysis U4++4Cl-+4Ag++4NO-a→AgCl+U4++4NO-a. Powder diffraction data for UCl4,are shown The silverelectrode potential in Table 2, along with those of Staritzky(3).
Recommended publications
  • ORGANOMETAT,T,TC CHEMISTRY of URANIUM a Thesis Submitted By
    ORGANOMETAT,T,TC CHEMISTRY OF URANIUM A thesis submitted by R1TN R. SIGURDSON, B.Sc. for the DEGREE of DOCTOR of PHILOSOPHY of the UNIVERSITY of LONDON Royal College of Science Imperial College of Science and Technology London, SW7 ?AY August 1976 TO MY PARENTS 3 ACKNOWLEDGEMENTS I would like to express my gratitude to Professor Geoffrey Wilkinson, F.R.S. for his guidance and enthusiastic support throughout the course of this work. Many thanks are also extended to Drs. Dick Andersen, Ernesto Carmona-Guzman and David Cole-Hamilton for their suggestionS, encouragement and advice, and to Dr. Kostas Mertis for his patient help during the first months. I am indebted to the Canadian Research Council of Canada for financial support during the past three years. 4 CONTENTS ABSTRACT 6 INTRODUCTION I. The Chemistry of Uranium(IV) 8 .II. The Chemistry of Uranium(V) 15 III. The Chemistry of Uranium(VI) 16 CHAPTER I. DILITHIUMHEXAALKYLURANATE(IV) COMPLEXES I. Introduction 19 II. Results and Discussion 27 III. Experimental 35 CHAPTER II. TRILITHIUMOCTAALKYLURANATE(V) COMPLEXES I. Introduction 54 II. Results and Discussion 55 III. Experimental 60 CHAPTER III. ADDITION COMPOUNDS OF URANIUM(VI) HEXAISO-PROPDXIDE WITH LITHIUM, MAGNESIUM AND ALUMINIUM ALKYLS I. Introduction 70 II. Results and Discussion 71 III. Experimental 77 CHAPTER IV. ORGANOMETALLIC CHEMISTRY OF ADAMANTANE I. Introduction 84 II. Results and Discussion 85 III. Experimental 87 REFERENCES 92 5 ABBREVIATIONS Me - methyl Et - ethyl Prn- normal-propyl Pri- iso-propyl Bun- normal-butyl But- iso-butyl But- tertiary-butyl Ph - phenyl CP cyclopentadienyl DME - dimethoxyethane tmed - N,N,NI,N'-tetramethylethylenediamine pmdt - N,N,Nt,N",N"-pentamethyldiethylenetriamine g.l.c.
    [Show full text]
  • Sources, Effects and Risks of Ionizing Radiation
    SOURCES, EFFECTS AND RISKS OF IONIZING RADIATION United Nations Scientific Committee on the Effects of Atomic Radiation UNSCEAR 2016 Report to the General Assembly, with Scientific Annexes UNITED NATIONS New York, 2017 NOTE The report of the Committee without its annexes appears as Official Records of the General Assembly, Seventy-first Session, Supplement No. 46 and corrigendum (A/71/46 and Corr.1). The report reproduced here includes the corrections of the corrigendum. The designations employed and the presentation of material in this publication do not imply the expression of any opinion whatsoever on the part of the Secretariat of the United Nations concerning the legal status of any country, territory, city or area, or of its authorities, or concerning the delimitation of its frontiers or boundaries. The country names used in this document are, in most cases, those that were in use at the time the data were collected or the text prepared. In other cases, however, the names have been updated, where this was possible and appropriate, to reflect political changes. UNITED NATIONS PUBLICATION Sales No. E.17.IX.1 ISBN: 978-92-1-142316-7 eISBN: 978-92-1-060002-6 © United Nations, January 2017. All rights reserved, worldwide. This publication has not been formally edited. Information on uniform resource locators and links to Internet sites contained in the present publication are provided for the convenience of the reader and are correct at the time of issue. The United Nations takes no responsibility for the continued accuracy of that information or for the content of any external website.
    [Show full text]
  • System Studies of Fission-Fusion Hybrid Molten Salt Reactors
    University of Tennessee, Knoxville TRACE: Tennessee Research and Creative Exchange Doctoral Dissertations Graduate School 12-2013 SYSTEM STUDIES OF FISSION-FUSION HYBRID MOLTEN SALT REACTORS Robert D. Woolley University of Tennessee - Knoxville, [email protected] Follow this and additional works at: https://trace.tennessee.edu/utk_graddiss Part of the Nuclear Engineering Commons Recommended Citation Woolley, Robert D., "SYSTEM STUDIES OF FISSION-FUSION HYBRID MOLTEN SALT REACTORS. " PhD diss., University of Tennessee, 2013. https://trace.tennessee.edu/utk_graddiss/2628 This Dissertation is brought to you for free and open access by the Graduate School at TRACE: Tennessee Research and Creative Exchange. It has been accepted for inclusion in Doctoral Dissertations by an authorized administrator of TRACE: Tennessee Research and Creative Exchange. For more information, please contact [email protected]. To the Graduate Council: I am submitting herewith a dissertation written by Robert D. Woolley entitled "SYSTEM STUDIES OF FISSION-FUSION HYBRID MOLTEN SALT REACTORS." I have examined the final electronic copy of this dissertation for form and content and recommend that it be accepted in partial fulfillment of the equirr ements for the degree of Doctor of Philosophy, with a major in Nuclear Engineering. Laurence F. Miller, Major Professor We have read this dissertation and recommend its acceptance: Ronald E. Pevey, Arthur E. Ruggles, Robert M. Counce Accepted for the Council: Carolyn R. Hodges Vice Provost and Dean of the Graduate School (Original signatures are on file with official studentecor r ds.) SYSTEM STUDIES OF FISSION-FUSION HYBRID MOLTEN SALT REACTORS A Dissertation Presented for the Doctor of Philosophy Degree The University of Tennessee, Knoxville Robert D.
    [Show full text]
  • Export Control Handbook for Chemicals
    Export Control Handbook for Chemicals -Dual-use control list -Common Military List -Explosives precursors -Syria restrictive list -Psychotropics and narcotics precursors ARNES-NOVAU, X 2019 EUR 29879 This publication is a Technical report by the Joint Research Centre (JRC), the European Commission’s science and knowledge service. It aims to provide evidence-based scientific support to the European policymaking process. The scientific output expressed does not imply a policy position of the European Commission. Neither the European Commission nor any person acting on behalf of the Commission is responsible for the use that might be made of this publication. Contact information Xavier Arnés-Novau Joint Research Centre, Via Enrico Fermi 2749, 21027 Ispra (VA), Italy [email protected] Tel.: +39 0332-785421 Filippo Sevini Joint Research Centre, Via Enrico Fermi 2749, 21027 Ispra (VA), Italy [email protected] Tel.: +39 0332-786793 EU Science Hub https://ec.europa.eu/jrc JRC 117839 EUR 29879 Print ISBN 978-92-76-11971-5 ISSN 1018-5593 doi:10.2760/844026 PDF ISBN 978-92-76-11970-8 ISSN 1831-9424 doi:10.2760/339232 Luxembourg: Publications Office of the European Union, 2019 © European Atomic Energy Community, 2019 The reuse policy of the European Commission is implemented by Commission Decision 2011/833/EU of 12 December 2011 on the reuse of Commission documents (OJ L 330, 14.12.2011, p. 39). Reuse is authorised, provided the source of the document is acknowledged and its original meaning or message is not distorted. The European Commission shall not be liable for any consequence stemming from the reuse.
    [Show full text]
  • Jan. 15, 1952 C. D., WLDER 2,582,941 PROCESSES of PRODUCING URANIUM CHLORIDES Filed Oct
    Jan. 15, 1952 C. D., WLDER 2,582,941 PROCESSES OF PRODUCING URANIUM CHLORIDES Filed Oct. 2, 1944 d S Q Q Q t 2. INVENTOR. 6ozEMAW Z. WZZZOER ATTORNEY . Patented Jan. 15, 1952 2,582,941 UNITED STATES PATENT OFFICE 2,582,941 PROCESSES OF PRODUCING URANUM CHELORDES - Coleman D. Wilder, Oak Ridge, Tenn., assignor to the United States. of America, as represented bysion the United States Atomic Energy Commis Application October 12, 1944, Serial No. 558,452 8 Claims. (C1. 23-145) 2. - This invention relates to the manufacture of a pating carbon tetrachloride vapor in a speedy uranium chloride product, and more particularly stream of dry air, passing the resultant mixture re of uranium pentachloride over an uranium compound heated to the neigh - - - - - a . g a substantial proportion of borhood of 550° C. whereby uranium pentachlo uranium hexachloride, by a process for chlorinat: ride is formed and vaporized into the current, ing various, compositions comprising uranium moving the resulting vaporous mixture into a compounds, with carbon tetrachloride vapor car collecting receptacle so that most of the uranium ried by a Swift current of air. chloride will condense and settle out, and send This invention has for an object the rapid pro ing the gas stream through a dust separator to duction of a uranium chloride product compris strip it of the residual uranium-containing par ing a large proportion of uranium pentachloride ticles. and various proportions of uranium hexachlo The apparatus employed comprises a device ride. for supplying carbon tetrachloride, a device for A further object of the invention is to provide supplying dry air, a flash boiler in which the a high-yield, low-loss process for the production 5 carbon tetrachloride is vaporized and mixed with of uranium pentachloride which is economical the air, a reaction chamber in which the ai and suitable for large scale production of said carbon tetrachloride admixture is reacted with chloride.
    [Show full text]
  • CATALOG of NUCLEAR REACTOR CONCEPTS [Disc 1]
    ANL-7092 Reactor T e lcbnology (TID-4500, 46th Ed.) 1 AEC Research and D eve lopmerit Report ARGONNENATIONAL LABORATORY 9700 South Cass Avenue Argonne, Illinois 60440 CATALOG OF NUCLEAR REACTOR CONCEPTS Part I. Homogeneous and Quasi-homogeneous Reactors Section 111. Reactors Fueled withMolten- salt Solutions . Charles E. Teeter, James A. Lecky, and John H.Martens Technical Pu'blications Department September 1965 Operated by The University of Chicago da under i Contract W - 3 1 - 109-eng -38 with the U. S. Atomic Energy Commission 445b 0311q50 ' i21 a ! i 1 4 ? i 3 TABLE OF CONTENTS --Page Preface ........................................ 5 Plan of Catalog of Nuclear Reactor Concepts. ............... 6 SECTION 111. REACTORS FUELED WITH MOLTEN-SALT SOLUTIONS. ........................... 7 Chapter 1. Introduction. .......................... 7 Chapter 2. One-region Reactors .................... 11 Chapter 3. Two-region Reactors .................... !33 c 5 . - PREFACE This report is an additional section in the Catalog of Nuclear Reactor Concepts that was begun with ANL-6892 and continued in ANL-6909. As in the previous reports, the material is divided into chapters, each with text and references, plus data sheets that cover the individual concepts. The planof the catalog, with the report numbers for the sections already issued, is given on the following page. Dr. Charles E. Teeter, formerly employed by the Chicago Oper- . ations Office at Argonne, Illinois, is now affiliated with the Southeastern Massachusetts Technological Institute, New Bedford, Mass. Through. a consultantship arrangement with Argonne National Laboratory, he is con- c tinuing to help guide the organization and cofnpilation of this catalog. J.H.M. September, 1965 , PLANOFCATALOGOFREACTORCONCEPTS Gene r a1 Introduction ANL - 6 89 2 Part I.
    [Show full text]
  • SYNTHESIS and CHARACTERIZATION of a SERIES of URANIUM(IV) SPECIES: Investigating Coordination with a Redox Innocent Triamine Ligand
    SYNTHESIS AND CHARACTERIZATION OF A SERIES OF URANIUM(IV) SPECIES: Investigating Coordination With a Redox Innocent Triamine Ligand Student Author Selena L. Staun earned a BS complexes containing redox-active ligands, and studies 2+ degree in chemistry with a minor in the reductive silylation of the UO2 cation. in sociology in May 2016; she graduated with department honors. She will start graduate school Suzanne Bart graduated from the to pursue a PhD in chemistry University of Delaware with a BS beginning September 2016 at the in chemistry (2001) and earned her University of California, Santa PhD from Cornell University with Barbara. While at Purdue, Staun was an undergraduate Professor Paul J. Chirik (2006). researcher in the Bart Laboratory for over 2 years and Subsequently, she was an Alexander received Purdue’s Department of Chemistry 2015 von Humboldt Postdoctoral Summer Research Award. She also found time to Fellow at the Friedrich-Alexander facilitate student learning as a Supplemental Instruction University Erlangen-Nuremberg under the direction Leader for a math course and as a teaching assistant for a of Professor Karsten Meyer. In 2008 she became an biology lab. assistant professor at Purdue University, then in 2014 she was promoted to associate professor. Her research Mentors interests include organometallic transformations mediated by organoactinide species. Bart recently won John J. Kiernicki earned AB an NSF CAREER award, and has been named a 2012 degrees in chemistry and history Cottrell Scholar and 2014 Organometallics Young from Ripon College in 2011 and Investigator Fellow. is currently working on his PhD in inorganic chemistry at Purdue University.
    [Show full text]
  • Nuclear Fuel Cycle, with a Liquid Ore and Fuel: Toward Renewable Energy Cite This: Sustainable Energy Fuels, 2019, 3, 1693 Claude A
    Sustainable Energy & Fuels View Article Online PAPER View Journal | View Issue Nuclear fuel cycle, with a liquid ore and fuel: toward renewable energy Cite this: Sustainable Energy Fuels, 2019, 3, 1693 Claude A. Degueldre, * Richard J. Dawson and Vesna Najdanovic-Visak To fulfill the conditions required for a nuclear renewable energy concept, one has to explore a combination of processes going from the front end of the nuclear fuel cycle to the fuel production and the energy conversion using specific fluid fuels and reactors. Extraction of uranium from a diluted fluid ore such as seawater has been studied in various countries worldwide. This extraction should be carried out parsimoniously. An extraction rate of 103 tons of U per year over centuries would not modify significantly the equilibrium concentration of uranium in the oceans (3.3 ppb). This equilibrium results from the input of 104 tons of U per year by river waters and its scavenging on the sea floor from the 1.37 Â 1018 tons of water in the oceans. For a renewable uranium extraction, the use of a specific biomass material is suggested to adsorb uranium and subsequently other transition metals. The uranium loading on the biomass would be around 100 mg per kg. After contact time, the loaded material would be dried and Creative Commons Attribution-NonCommercial 3.0 Unported Licence. burned (CO2 neutral) with heat conversion into electricity. The uranium ‘burning’ in a molten salt fast reactor helps to optimize the energy conversion by burning all actinide isotopes with an excellent yield for producing a maximum amount of thermal energy from fission and converting it into electricity.
    [Show full text]
  • Depleted Uranium
    WHO/SDE/PHE/01.1 English only Limited Depleted uranium Sources, Exposure and Health Effects Department of Protection of the Human Environment World Health Organization Geneva April 2001 The illustration of the cover page is extracted from Rescue Mission: Planet Earth, ã Peace Child International 1994; used by permission. ã World Health Organization 2001 This document is not issued to the general public and all rights are reserved by the World Health Organization. The document may not be reviewed, abstracted, quoted, reproduced or translated, in part or in whole, without the prior written permission of WHO. No part of this document may be stored in a retrieval system or transmitted in any form or by any means – electronic, mechanical or other without the prior written permission of WHO. The views expressed in documents by named authors are solely the responsibility of those authors. Preface Depleted uranium (DU) has been used in medical and industrial applications for decades but only since its use in military conflicts in the Gulf and the Balkans has public concern been raised about potential health consequences from exposure to it. Concerns have been particularly for peacekeeping forces, humanitarian workers and local populations living and working in areas contaminated by DU following conflict. There has been a large amount of research on the health consequences to workers in the mining and milling of uranium, and on its use in nuclear power, that enables a reasonable assessment of its impact on human health1. Since DU acts chemically in the same way as uranium, and the radiological toxicity is somewhat less than uranium, this research can be used to evaluate health risks from ingestion, inhalation and contact with DU.
    [Show full text]
  • Uranium (III) Precipitation in Molten Chloride by Wet Argon Sparging Jean-François Vigier, Annabelle Laplace, Catherine Renard, Manuel Miguirditchian, Francis Abraham
    Uranium (III) precipitation in molten chloride by wet argon sparging Jean-François Vigier, Annabelle Laplace, Catherine Renard, Manuel Miguirditchian, Francis Abraham To cite this version: Jean-François Vigier, Annabelle Laplace, Catherine Renard, Manuel Miguirditchian, Francis Abra- ham. Uranium (III) precipitation in molten chloride by wet argon sparging. Journal of Nuclear Materials, Elsevier, 2016, 474, pp.19-27. 10.1016/j.jnucmat.2016.03.005. cea-02386899 HAL Id: cea-02386899 https://hal-cea.archives-ouvertes.fr/cea-02386899 Submitted on 6 Jan 2020 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. Journal of Nuclear Materials 474 (2016) 19e27 Contents lists available at ScienceDirect Journal of Nuclear Materials journal homepage: www.elsevier.com/locate/jnucmat Uranium (III) precipitation in molten chloride by wet argon sparging * Jean-François Vigier a, b, , Annabelle Laplace a, Catherine Renard b, Manuel Miguirditchian a, Francis Abraham b a CEA, Nuclear Energy Division, Radiochemistry & Processes Department, F-30207 Bagnols sur Ceze, France b Unite de Catalyse et de Chimie du Solide, UCCS UMR CNRS 8181, Univ. Lille Nord de France, ENSCL-USTL, B.P. 90108, 59652 Villeneuve d'Ascq Cedex, France highlights graphical abstract Precipitation of Uranium (III) is quantitative in molten salt LiCl-CaCl2 (30e70 mol%).
    [Show full text]
  • Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors
    Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors Prepared for U.S. Department of Energy MSR Campaign B.J. Riley,(a) J. McFarlane,(b) G.D. DelCul,(b) J.D. Vienna,(a) C.I. Contescu,(b) L.M. Hay,(a) A.V. Savino,(a) H.E. Adkins,(a) (a)Pacific Northwest National Laboratory (b)Oak Ridge National Laboratory August 15, 2018 NTRD-MSR-2018-000379, PNNL-27723 Approved for public release. Distribution is unlimited. DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors iv August 15, 2018 SUMMARY The overall summary of the waste management envelope discussed in this report is represented by the diagram shown in Figure S1. The
    [Show full text]
  • Synthesis of Uranium Fluorosulfates and the Group VI B Difluorophosphates
    Portland State University PDXScholar Dissertations and Theses Dissertations and Theses 1973 Synthesis of Uranium Fluorosulfates and the Group VI B Difluorophosphates Larry McCain Emme Portland State University Follow this and additional works at: https://pdxscholar.library.pdx.edu/open_access_etds Part of the Chemistry Commons Let us know how access to this document benefits ou.y Recommended Citation Emme, Larry McCain, "Synthesis of Uranium Fluorosulfates and the Group VI B Difluorophosphates" (1973). Dissertations and Theses. Paper 1593. https://doi.org/10.15760/etd.1593 This Thesis is brought to you for free and open access. It has been accepted for inclusion in Dissertations and Theses by an authorized administrator of PDXScholar. Please contact us if we can make this document more accessible: [email protected]. '\ AN ABSTRACT OF THE THESIS OF Larry ~1cCain Emme for the Master of Science in Chemistry August 10, 1973. Title: Synthesis of Uranium Fluorosulfates and Group VI B Difluoro­ phosphates APPROVED BY MEMBERS OF THE THESIS COMMITTEE: Gary L: Gard, Chairman M.-B. Silverman D. W. Barnum Some reactions leading to several anhydrous Uranium fluorosul­ fates through the use of fluorosulfonic acid or peroxydisulfuryl di- fluoride have been studied. It was found that HS0 F can oxidize uranium 3 metal to the +4 state or the +2 state depending on the reaction condi­ tions. The synthesis of the tan solid; U(S03F)4' and the pale green solid thought to be U(S03F)2 were prepa~ed in this manner. It was found that S206F2 can also oxidize uranium to yield the green solid U(S03F)3.
    [Show full text]