Preparation and Electrocatalytic Property of Triuranium Octoxide Supported on Reduced Graphene Oxides

Total Page:16

File Type:pdf, Size:1020Kb

Preparation and Electrocatalytic Property of Triuranium Octoxide Supported on Reduced Graphene Oxides Nano Research 1 DOINano 10.1007/s12274Res -014-0668-8 Preparation and Electrocatalytic Property of Triuranium Octoxide Supported on Reduced Graphene Oxides Dongliang Gao1, 2, Zhenyu Zhang1, Li Ding1, Juan Yang1, and Yan Li1, 2 () Nano Res., Just Accepted Manuscript • DOI: 10.1007/s12274-014-0668-8 http://www.thenanoresearch.com on December 2 2014 © Tsinghua University Press 2014 Just Accepted This is a “Just Accepted” manuscript, which has been examined by the peer-review process and has been accepted for publication. A “Just Accepted” manuscript is published online shortly after its acceptance, which is prior to technical editing and formatting and author proofing. Tsinghua University Press (TUP) provides “Just Accepted” as an optional and free service which allows authors to make their results available to the research community as soon as possible after acceptance. After a manuscript has been technically edited and formatted, it will be removed from the “Just Accepted” Web site and published as an ASAP article. Please note that technical editing may introduce minor changes to the manuscript text and/or graphics which may affect the content, and all legal disclaimers that apply to the journal pertain. In no event shall TUP be held responsible for errors or consequences arising from the use of any information contained in these “Just Accepted” manuscripts. To cite this manuscript please use its Digital Object Identifier (DOI®), which is identical for all formats of publication. TABLE OF CONTENTS (TOC) Preparation and Electrocatalytic Property of Triuranium Octoxide Supported on Reduced Graphene Oxides Dongliang Gao1, 2, Zhenyu Zhang1, Li Ding1, Juan Yang1, and Yan Li1, 2* 1 Key Laboratory for the Physics and Chemistry of Nanodevices, Beijing National Laboratory for Molecular Science, College of Chemistry and Molecular Engineering, State Key Laboratory of Rare Earth Materials Chemistry and Applications, Peking University, Beijing100871, China A two-step solution-phase method was used to prepare triuranium octoxides-reduced graphene oxides hybrids, which exhibited superior electrocatalytic activity for oxygen 2 Academy for Advanced Interdisciplinary reduction reaction. Studies, Peking University, Beijing100871, China Provide the authors’ webside if possible. Author 1, webside 1 Author 2, webside 2 Nano Research DOI (automatically inserted by the publisher) Research Article Preparation and Electrocatalytic Property of Triuranium Octoxide Supported on Reduced Graphene Oxides Dongliang Gao1, 2, Zhenyu Zhang1, Li Ding1, Juan Yang1, and Yan Li1, 2 () Received: day month year ABSTRACT Revised: day month year Triuranium octoxides-reduced graphene oxides (U3O8/rGO) hybrids were Accepted: day month year prepared by a two-step solution-phase method. The presence of GO is essential (automatically inserted by for obtaining pure phase U3O8. The U3O8/rGO hybrids exhibited superior the publisher) electrocatalytic activity for oxygen reduction reaction. The electron transfer number was calculated to be ~3.9 at -0.7 V (v.s. Ag/AgCl) from the slope of © Tsinghua University Press Koutecky-Levich plots. The U3O8/rGO hybrids were more stable than the and Springer-Verlag Berlin commercial Pt/C catalysts. When methanol existed, the U3O8/rGO hybrids still Heidelberg 2014 kept high activity. Besides, the U3O8/rGO hybrids can also catalyze the reduction of hydrogen peroxide. KEYWORDS Triuranium Octoxide, Reduced Graphene Oxides, Oxygen Reduction Reaction, Electrocatalysis of 99.275%, 0.720%, and 0.005%, respectively [1]. 1 Introduction Uranium-dioxide with enriched 235U is normally used as a fuel in the nuclear reactors. So large amount of 238U, which has a very long half-life period of ~4.5 Uranium is an important element in nuclear industry. billion years and hence is safe to be used Uranium consists of several natural isotopes conventionally [2], is left. Therefore, the application including 238U, 235U, and 234U, with natural abundance Address correspondence to Yan Li, [email protected] Nano Res. 2 of residual 238U is of great importance. [19]. In these studies, it is always difficult to avoid the formation of impurity uranium oxides with Uranium is an actinide element which has 5f different valence. The introducing of different electrons. The 5f-orbital can hybridize with the organic molecules which act as reductants or capping 6d-orbital, giving the actinides a broader range of agents is also a big problem, which depresses the oxidation states. Thus uranium possesses +2, +3, +4, catalytic performance of uranium oxides [20]. +5, and +6 valence [3-9]. Besides the most outside orbitals in the 7th shell, both 5f and 6d orbitals can Graphene oxide (GO) presents high specific also partake in chemical bonding, therefore, the surface area and contains carboxylic, hydroxyl, bonding of uranium is quite complicated. In addition, epoxide and other hydrophilic functional groups on chemical bonds consisting of uranium ions are often the surface. Therefore, GO has been widely used as less ionic due to the large radius and high charge substrates to prepare inorganics-GO hybrids. Dai’s number [10]. So uranium has different coordination group has developed a general two-step method to numbers and bonding modes from the lanthanide or prepare hybrids of inorganic nanomaterials and transition elements [11]. Owing to the special graphene oxides. First, metal ions absorb onto GO structural features and chemical properties, uranium and hydrolyze in situ; then the pre-products are oxides may be used as good catalysts for different treated under hydrothermal or solvothermal kinds of reactions [10, 12-16]. conditions to obtain the final hybrids [22-30]. This method may be used to prepare hybrids of uranium It is found that the oxidation state of uranium is a oxides and GO. crucial factor influencing its catalytic performance. For instance, U3O8 can catalyze the aldolization With the outstanding properties of high electrical reaction of acetaldehyde to form crotonaldehyde. conductivity, surface area, flexibility, thermal However, when β-UO3 was used as catalysts, conductivity, and mechanical strength, graphene can acetaldehyde conducted condensation reaction to be used as electrode materials or supports for form furan [17]. U3O8 nanocrystals have a better electrocatalysts [31-33]. Due to the scarcity and high catalytic performance for benzyl alcohol conversion price of Pt for large scale application of fuel cells, to benzadlehyde than UO2 nanocrystals [18]. electrocatalysts without Pt have attracted much Nanoplates of uranium oxide hydroxide hydrate attention [34-36]. Very recently, M. Pumera et al. exhibit a higher catalytic activity than U3O8 for reported that uranium doped graphene hybrids benzyl alcohol oxidation [15]. The oxygen-defected exhibited electrocatalytic properties towards oxygen UO2 (111) single crystal reduces coupling of CO reduction [37]. They found UO3 and U3O8 co-exist in molecules to acetylene and ethylene compounds on their catalysts. It is unclear which component acts as its surface [12]. the catalytic species and the performance of the catalysts is not optimized. In this paper, we prepared Thus synthesis of pure phase uranium oxides with hybrids of pure phase triuranium octoxide and different oxidation states is very important for reduced GO (U3O8/rGO) and studied their studying their catalytic property. A few literatures electrocatalytic property. It was found that the have reported about the preparation of uranium U3O8/rGO hybrids showed very good activity toward oxides nanomaterial [15, 18-21]. For instance, using oxygen reduction reaction (ORR) and were more different organic amines as reducing reagents, UO2 stable than the commercial Pt/C catalysts. U3O8/rGO nanospheres and U3O8 nanorods have been hybrid catalysts might be used as a substitute of Pt/C synthesized [18]. By the addition of hydrazine, electrocatalyst for oxygen reduction reaction in fuel spherical UO2 nanoparticles with diameter from 30 to cells. 250 nm and U3O8 nanocuboids have been synthesized | www.editorialmanager.com/nare/default.asp Nano Res. 3 voltammetry. The catalyst-modified electrode was 2 Experimental prepared by transferring 20 μl of 2 mg/ml suspension of the samples onto the glassy carbon 2.1 Preparation of U3O8/rGO nanocrystals electrode with a diameter of 5.0 mm. A thin layer of Nafion was added to cover the electrode when it GO was synthesized by an improved hummers was dried. ORR was carried out in O2-saturated 0.1 method [38] (see details in the supporting M KOH aqueous solution at room temperature. information). Typically, 6 mg GO was dispersed in Hydrogen peroxide reduction was carried in 10 ml ethanol. 1 ml of 30 mg/mL UO2(NO3)2 N2-saturated 50 mM phosphate buffer saline (PBS) aqueous solution and 0.9 mL of concentrated aqueous solution at room temperature. NH3·H2O was injected into the suspension at 60 ºC, respectively. After stirring at 60 ºC for 6 hours, the 3 Results and discussion precipitates were collected by centrifugation and washed with water. Then the precipitates were Figures 1 (a) & (c) shows the TEM and SEM images re-dispersed in 10 ml water and transferred into a of the products obtained under typical conditions 20 ml Teflon-lined stainless steel autoclaves to carry with the hydrolysis temperature of 60 ºC. HRTEM out hydrothermal reaction at 200 ºC for 4 hours. The image in Fig. 1(b) clearly exhibits the fringes with product was collected by centrifugation, washed the inter-plane distance of (0 0 1) plane of U3O8 (0.42 with water, frozen by liquid nitrogen and nm). The selected area electron diffraction (SAED) lyophilized overnight. Using lyophilization process pattern also matches the structure of single crystal other than normal drying can avoid the aggregation U3O8 well. So the product we obtained is U3O8/rGO. of the products. The morphologies of the U3O8 nanoparticles are approximately cuboid with the dimensions of 2.2 Characterization 100-200 nm in length and 20-100 nm in width. X-ray diffraction (XRD) measurements were performed on a Rigaku Dmax-2400 diffractometer using Cu-Kα radiation (λ = 1.5406 Å ) with an accelerating voltage of 40kV.
Recommended publications
  • Dissolution of Uranium Dioxide in Nitric Acid Media: What Do We Know?
    EPJ Nuclear Sci. Technol. 3, 13 (2017) Nuclear © Sciences P. Marc et al., published by EDP Sciences, 2017 & Technologies DOI: 10.1051/epjn/2017005 Available online at: http://www.epj-n.org REGULAR ARTICLE Dissolution of uranium dioxide in nitric acid media: what do we know? Philippe Marc1, Alastair Magnaldo1,*, Aimé Vaudano1, Thibaud Delahaye2, and Éric Schaer3 1 CEA, Nuclear Energy Division, Research Department of Mining and Fuel Recycling Processes, Service of Dissolution and Separation Processes, Laboratory of Dissolution Studies, 30207 Bagnols-sur-Cèze, France 2 CEA, Nuclear Energy Division, Research Department of Mining and Fuel Recycling Processes, Service of Actinides Materials Fabrication, Laboratory of Actinide Conversion Processes, 30207 Bagnols-sur-Cèze, France 3 Laboratoire Réactions et Génie des Procédés, UMR CNRS 7274, University of Lorraine, 54001 Nancy, France Received: 16 March 2016 / Received in final form: 15 November 2016 / Accepted: 14 February 2017 Abstract. This article draws a state of knowledge of the dissolution of uranium dioxide in nitric acid media. The chemistry of the reaction is first investigated, and two reactions appear as most suitable to describe the mechanism, leading to the formation of monoxide and dioxide nitrogen as reaction by-products, while the oxidation mechanism is shown to happen before solubilization. The solid aspect of the reaction is also investigated: manufacturing conditions have an impact on dissolution kinetics, and the non-uniform attack at the surface of the solid results in the appearing of pits and cracks. Last, the existence of an autocatalytic mechanism is questionned. The second part of this article presents a compilation of the impacts of several physico-chemical parameters on the dissolution rates.
    [Show full text]
  • Inventory for Geological Disposal Main Report October 2018 DSSC/403/02
    DSSC/403/02 Inventory for geological disposal Main Report October 2018 DSSC/403/02 Inventory for geological disposal Main Report October 2018 DSSC/403/02 Conditions of Publication This report is made available under the Radioactive Waste Management Ltd (RWM) Transparency Policy. In line with this policy, RWM is seeking to make information on its activities readily available, and to enable interested parties to have access to and influence on its future programmes. The report may be freely used for non-commercial purposes. RWM is a wholly owned subsidiary of the Nuclear Decommissioning Authority (NDA), accordingly all commercial uses, including copying and re publication, require permission from the NDA. All copyright, database rights and other intellectual property rights reside with the NDA. Applications for permission to use the report commercially should be made to the NDA Information Manager. Although great care has been taken to ensure the accuracy and completeness of the information contained in this publication, the NDA cannot assume any responsibility for consequences that may arise from its use by other parties. © Nuclear Decommissioning Authority 2018 All rights reserved. ISBN 978-1-84029-584-9. Other Publications If you would like to see other reports available from RWM and the NDA, a complete listing can be viewed at our website www.nda.gov.uk, or please write to us at the address below. Feedback Readers are invited to provide feedback on this report and on the means of improving the range of reports published. Feedback should be addressed to: RWM Feedback Radioactive Waste Management Ltd Building 587 Curie Avenue Harwell Campus Didcot OX11 0RH UK email: [email protected] ii DSSC/403/02 Preface Radioactive Waste Management Limited (RWM) has been established as the delivery organisation responsible for the implementation of a safe, sustainable and publicly acceptable programme for the geological disposal of the higher activity radioactive wastes in the UK.
    [Show full text]
  • DEPLETED URANIUM HEXAFLUORIDE (Current Situation, Safe Handling and Prospects)
    DEPLETED URANIUM HEXAFLUORIDE (current situation, safe handling and prospects) 2020 Authors: Alexander Nikitin, Head of Bellona Foundation Oleg Muratov, nuclear physicist, Head of Radiation Technology Dept., TVEL JSC Ksenia Vakhrusheva, Cand. Sci. Econ., Expert, BELLONA International Foundation Editor: Elena Verevkina Design: Alexandra Solokhina This Report was prepared with support and participation of Environmental Board of the Public Council of Rosatom State Atomiс Energy Corporation Publishers: Bellona Foundation Environmental Protection NGO ‘Ecopravo’ Expert and Legal Center TABLE OF CONTENTS Abbreviations ............................................................................................................................. 4 Foreword ..................................................................................................................................... 5 Introduction ................................................................................................................................ 6 Chapter 1. A few words about nuclear physics and radioactivity for non-specialists............... 8 Chapter 2. Uranium hexafluoride and its properties ..................................................................... 11 2.1. Physical properties of uranium hexafluoride .................................................................. 12 2.2. Chemical properties of uranium hexafluoride ................................................................ 13 Chapter 3. What is DUHF ..................................................................................................................
    [Show full text]
  • Fifth Canadian National Report for the Joint Convention
    Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management © Canadian Nuclear Safety Commission (CNSC) 2014 PWGSC catalogue number CC172-23/2014E-PDF ISSN 2368-4828 Extracts from this document may be reproduced for individual use without permission provided the source is fully acknowledged. However, reproduction in whole or in part for purposes of resale or redistribution requires prior written permission from the Canadian Nuclear Safety Commission. Également publié en français sous le titre: Rapport national du Canada pour la Convention commune sur la sûreté de la gestion du combustible usé et sur la sûreté de la gestion des déchets radioactifs Document availability This document can be viewed on the CNSC website at nuclearsafety.gc.ca. To request a copy of the document in English or French, please contact: Canadian Nuclear Safety Commission 280 Slater Street P.O. Box 1046, Station B Ottawa, Ontario K1P 5S9 CANADA Tel.: 613-995-5894 or 1-800-668-5284 (in Canada only) Facsimile: 613-995-5086 Email: [email protected] Website: nuclearsafety.gc.ca Facebook: facebook.com/CanadianNuclearSafetyCommission YouTube: youtube.com/cnscccsn Publishing history October, 2011 Fourth Report October, 2008 Third Report October, 2005 Second Report October, 2002 First Report ii Preface Information in this report covers the period up to March 31, 2014. However, in some instances the reporting period extends beyond this to the time of writing the report: July 31, 2014. Examples include the current status of the Canadian Nuclear Safety Commission’s regulatory documents, the Nuclear Waste Management Organization’s (NWMO) Adaptive Phased Management (APM) approach, and Ontario Power Generation’s (OPG) Deep Geologic Repository (DGR).
    [Show full text]
  • Fuel Cycle Processes Directed Self-Study Course! This Is the Third of Nine Modules Available in This Directed Self-Study Course
    MODULE 3.0: URANIUM CONVERSION Introduction Welcome to Module 3.0 of the Fuel Cycle Processes Directed Self-Study Course! This is the third of nine modules available in this directed self-study course. The purpose of this module is to be able to discuss the NRC regulations of and describe conversion facilities; identify the basic steps of the dry fluoride volatility conversion process and contrast with the wet acid digestion conversion process; identify sampling and measurement activities for the dry conversion process and the radiological and non-radiological hazards associated with the dry conversion process. This self-study module is designed to assist you in accomplishing the learning objectives listed at the beginning of the module. There are five learning objectives in this module. The module has self-check questions and activities to help you assess your understanding of the concepts presented in the module. Before you Begin It is recommended that you have access to the following materials: ◙ Trainee Guide ◙ Sequoyah Fuels Accident Slides (on CD accompanying course manual) ◙ “Release of UF6 from a Ruptured Model 48Y Cylinder at Sequoyah Fuels Corporation Facility: Lessons-Learned Report," U.S. Nuclear Regulatory Commission, NUREG-1198, June 1986. ◙ “Assessment of the Public Health Impact from the Accidental Release of UF6 at the Sequoyah Fuels Corporation Facility at Gore, Oklahoma," U.S. Nuclear Regulatory Commission, NUREG-1189, Vol. 1, March 1986. Complete the following prerequisites: ◙ Module 1.0: Overview of the Nuclear Fuel Cycle How to Complete this Module 1. Review the learning objectives. 2. Read each section within the module in sequential order.
    [Show full text]
  • Lockheed Martin Energy Systems, Inc. for the United States Department of Energy
    Y/ES-014/R4 Y-12 ASSESSMENT BEC2Q OF OAK RIDGE Y-12 ENRICHED URANIUM STORAGE PLANT SAFETY ISSUES LOCKHEED HI A H T I N / AT THE OAK RIDGE Y-12 PLANT Uranium Storage Assessment Team August 1996 Prepared by the Oak Ridge Y-12 Plant Oak Ridge, Tennessee 37831 managed by Lockheed Martin Energy Systems, Inc. for the U.S. Department of Energy Under contract DE-AC05-84OR21400 MANAGED BY LOCKHEED MARTIN ENERGY SYSTEMS, INC. FOR THE UNITED STATES DEPARTMENT OF ENERGY Jt, aSSTRIBUTiON OF THIS DOCUMENT IS UNLIMITED UCN-13S72 (26 6-55) DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or use- fulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manu- facturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. .»-•:•:•• •»-<.„-:.>•• Y/ES-014/R4 ASSESSMENT OF ENRICHED URANIUM STORAGE SAFETY ISSUES AT THE OAK RIDGE Y-12 PLANT Uranium Storage Assessment Team August 1996 Prepared by the Oak Ridge Y-12 Plant Oak Ridge, Tennessee 37831 managed by Lockheed Martin Energy Systems, Inc.
    [Show full text]
  • United States Patent Office Patented Nov
    3,288,568 United States Patent Office Patented Nov. 29, 1966 1. 2 3,288,568 tion and extraction can be effected combinedly in one pro DIRECT DISSOLUTION OF WATER. INSOLUBLE cedure, and that stirring or agitation for dissolution and URANUM COMPOUNDS BY CONTACT WITH extraction is not necessarily continued, thus a simpler NEUTRAL, ORGANIC SOLVENTS PRETREATED apparatus suffices, are advantages of the method of the WITH NTRIC ACD invention. Ordinarily, when the water-insoluble nuclear Hiroshi Tomijima, Totsuka-ku, Yokohama, Kazushige fuel material is converted to a water-soluble compound or Tsukui, Tokyo, and Yoshimi Okoshi, Kawasaki-shi, a compound extractable with an extracting organic sol Japan, assignors to Tokyo Shibaura Electric Co., Ltd., vent, an excess amount of an acid is to be used, so that it Kawasaki-shi, Japan, a corporation of Japan causes a wasteful spending and needs apparatus and labor No Drawing. Filed Oct. 20, 1961, Ser. No. 146,447 10 Claims priority, application Japan, Nov. 18, 1960, for the recovery. According to the purifying method of 35/45,357 the invention, however, spending amount of the inorganic 9 Claims. (CI. 23-319) acid is limited to the theoretical amount, or an amount somewhat larger than that, for converting the material to This invention relates to the method for purifying nu 5 a compound extractable by the extracting solvent, thereby clear fuel materials. More particularly, it relates to a the amount of the inoganic acid required being smaller method for purifying nuclear fuel materials by contacting and the cost for recovering the acid being not needed.
    [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]
  • Alternatives to MOX Direct-Disposal Options for Stockpiles of Separated Plutonium
    Alternatives to MOX Direct-disposal options for stockpiles of separated plutonium Frank von Hippel and Gordon MacKerron April 2015 Research Report No. 13 International Panel on Fissile Materials Alternatives to MOX Direct-disposal options for stockpiles of separated plutonium Frank von Hippel and Gordon MacKerron 2015 International Panel on Fissile Materials This work is licensed under the Creative Commons Attribution-Noncommercial License To view a copy of this license, visit www.creativecommons.org/licenses/by-nc/3.0 On the cover: the map shows the states with large plutonium stockpiles covered in this report. Table of Contents About the IPFM 1 Summary 2 Introduction 4 France and Japan 12 United Kingdom 17 United States 22 Direct disposal options 34 International transparency 41 Conclusions 42 Endnotes 44 Authors 60 Table 1. Global stocks of separated plutonium as of the end of 2013 5 Figures 1. Growth of global stockpile of separated plutonium 4 2. Average uranium prices paid by U.S. utilities, 1965 – 2013 8 3. Growth of France’s stock of unirradiated civilian plutonium 13 4. Growth of Japan’s stock of unirradiated plutonium 15 5. Growth of the UK’s stock of unirradiated civilian plutonium 17 6. UK Sellafield Product and Residue Store 18 7. Plutonium storage containers in the U.S. DOE’s Savannah River Site 22 8. U.S. MOX Fuel Fabrication Facility under construction 25 9. The U.S. Department of Energy’s Waste Isolation Pilot Plant (WIPP) 27 10. Glovebox line at the Sellafield MOX Fuel Fabrication Plant 28 11. Emplacement of immobilized plutonium in a deep borehole 38 About the IPFM The International Panel on Fissile Materials (IPFM) was founded in January 2006.
    [Show full text]
  • Temperature Dependent Gibbs Free Energies of Reaction of Uranyl
    Temperature Dependent Gibbs Free Energies of Reaction of Uranyl Containing Materials Based on Density Functional Theory Francisco Colmeneroa*, Ana María Fernándezb, Joaquín Cobosb and Vicente Timóna aInstituto de Estructura de la Materia (CSIC). C/ Serrano, 113. 28006 – Madrid, Spain. bCentro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT). Avda/ Complutense, 40. 28040 – Madrid, Spain. Orcid Francisco Colmenero: https://orcid.org/0000-0003-3418-0735 Orcid Ana María Fernández: https://orcid.org/0000-0002-8392-0165 Orcid Joaquín Cobos: https://orcid.org/0000-0003-0285-7617 Orcid Vicente Timón: https://orcid.org/0000-0002-7460-7572 *E-mail: [email protected] 1 ABSTRACT The thermodynamic properties of uranyl containing materials including dehydrated schoepite, metastudtite, studtite, soddyite, rutherfordine and γ − UO3, determined by means of density functional theory using a new norm-conserving pseudopotential for uranium atom in previous works, were used to obtain the enthalpies and Gibbs free energies of eight reactions involving these materials and its variation with the temperature. The first five reactions represent the formation of the first five considered materials in terms of the corresponding oxides, and the remaining reactions are the transformations of rutherfordine into dehydrated schoepite, studtite into metastudtite and uranium trioxide into triuranium octoxide, respectively. The experimental values of the enthalpies of these reactions, which are only known at the standard state (temperature of 298.15 K and pressure of 1 bar), were reproduced accurately by these calculations, the errors being 2.5, 2.5, 0.2, 0.0, 12.3, -1.1, 0.9 and 4.0 kJ · mol−1, respectively.
    [Show full text]
  • Uranium, Inorganic and Soluble Salts
    Uranium, inorganic and soluble salts Evaluation of health hazards and proposal of a health based quality criteria for drinking water Environmental Project No. 1527, 2013 Title: Author: Uranium, inorganic and soluble salts Elsa Nielsen, Krestine Greve, Ole Ladefoged. Division of Toxicology and Risk Assessment. National Food Institute, Technical University of Denmark. Published by: The Danish Environmental Protection Agency Strandgade 29 1401 Copenhagen K Denmark www.mst.dk/english Year: ISBN no. Authored in 2008 978-87-93026-82-7 Published in 2013 Disclaimer: When the occasion arises, the Danish Environmental Protection Agency will publish reports and papers concerning research and development projects within the environmental sector, financed by study grants provided by the Danish Environmental Protection Agency. It should be noted that such publications do not necessarily reflect the position or opinion of the Danish Environmental Protection Agency. However, publication does indicate that, in the opinion of the Danish Environmental Protection Agency, the content represents an important contribution to the debate surrounding Danish environmental policy. Sources must be acknowledged. 2 Uranium, inorganic and soluble salts Content CONTENT 3 PREFACE 5 GENERAL DESCRIPTION 6 1.1 IDENTITY 6 1.2 PHYSICAL / CHEMICAL PROPERTIES 7 1.3 PRODUCTION AND USE 7 1.4 ENVIRONMENTAL OCCURRENCE AND FATE 8 1.4.1 Air 8 1.4.2 Water 8 1.4.3 Soil 10 1.4.4 Bioaccumulation 10 1.4.5 Foodstuffs 11 1.5 HUMAN EXPOSURE 11 2 TOXICOKINETICS 12 2.1 ABSORPTION, DISTRIBUTION
    [Show full text]
  • United States Patent (19) 11 Patent Number: 4,832,924 Tomoshige Et Al
    United States Patent (19) 11 Patent Number: 4,832,924 Tomoshige et al. (45) Date of Patent: May 23, 1989 54 PROCESS FOR PRODUCING URANIUM 4,292,279 9/1981 Reusser ................................. 423/15 4,375,452 3/1983 Jan et al. ................................. 423/7 OXIDES 4,517,096 5/1985 Sekine et al. ... 210/668 75) Inventors: Shozo Tomoshige; Hideto Obara; 4,696,768 9/1987 Ali et al. ............................. 42.3/7 X Kozo Kondo, all of Uji; Keiichiro Otomura, Kurayoshi; Soichiro Yano, Primary Examiner-John F. Terapane Okayama, all of Japan Assistant Examiner-Virginia B. Caress Attorney, Agent, or Firm-Wenderoth, Lind & Ponack 73) Assignee: Doryokuro Kakunenryo Kaihatsu Jigyodan, Tokyo, Japan 57 ABSTRACT The present invention provides a process for producing (21) Appl. No.: 127,913 a uranium oxide by dissolving a yellow cake in sulfuric 22 Filed: Dec. 2, 1987 acid or hydrochloric acid, bringing the obtained solu (30) Foreign Application Priority Data tion into contact with a chelating resin of diaminocar boxylic acid type and subjecting the product to neutral Dec. 26, 1986 JP Japan ................................ 61-3102 izing precipitation followed by heat treatment. By the 51 Int. Cl. .................... C01G 43/01; CO1G 43/025; contact of the solution with the chelating resin, iron, C22B 60/02 copper, molybdenum and Vanadium among the metallic 52 U.S. Cl. ........................................ 423/7; 423/260; impurities are removed and in the subsequent neutraliz 423/15 ing precipitation step, other metallic impurities such as 58) Field of Search ........................ 423/260, 7, 11, 15 aluminum, calcium, magnesium, sodium and potassium are removed. This process can easily produce uranium 56 References Cited oxide having a high purity using a simple apparatus.
    [Show full text]