Temperature Dependent Gibbs Free Energies of Reaction of Uranyl
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Paulscherrerite from the Number 2 Workings, Mount Painter Inlier, Northern Flinders Ranges, South Australia: “Dehydrated Schoepite” Is a Mineral After All
American Mineralogist, Volume 96, pages 229–240, 2011 Paulscherrerite from the Number 2 Workings, Mount Painter Inlier, Northern Flinders Ranges, South Australia: “Dehydrated schoepite” is a mineral after all JOËL BRUGGER,1,2,* NICOLAS MEISSER,3 BAR B ARA ETSCH M A nn ,1 STEFA N AN SER M ET ,3 A N D ALLA N PRI N G 2 1Tectonics, Resources and Exploration (TRaX), School of Earth and Environmental Sciences, University of Adelaide, SA-5005 Adelaide, Australia 2Division of Mineralogy, South Australian Museum, SA-5000 Adelaide, Australia 3Musée Géologique and Laboratoire des Rayons-X, Institut de Minéralogie et de Géochimie, UNIL—Anthropole, CH-1015 Lausanne-Dorigny, Switzerland AB STRACT Paulscherrerite, UO2(OH)2, occurs as an abundant dehydration product of metaschoepite at the Number 2 Workings at Radium Ridge, Northern Flinders Ranges, South Australia. The mineral name honors the contribution of Swiss physicist Paul Scherrer (1890–1969) to mineralogy and nuclear physics. Individual paulscherrerite crystals are tabular, reaching a maximum of 500 nm in length. Paulscherrerite has a canary yellow color and displays no fluorescence under UV light. Chemically, paulscherrerite is a pure uranyl hydroxide/hydrate, containing only traces of other metals (<1 wt% in total). Bulk (mg) samples always contain admixtures of metaschoepite (purest samples have ~80 wt% paulscherrerite). A thermogravimetric analysis corrected for the presence of metaschoepite contamina- tion leads to the empirical formula UO3·1.02H2O, and the simplified structural formula UO2(OH)2. Powder diffraction shows that the crystal structure of paulscherrerite is closely related to that of synthetic orthorhombic α-UO2(OH)2. However, splitting of some X-ray diffraction lines suggests a monoclinic symmetry for type paulscherrerite, with a = 4.288(2), b = 10.270(6), c = 6.885(5) Å, β = 3 90.39(4)°, V = 303.2(2) Å , Z = 4, and possible space groups P2, P21, P2/m, or P21/m. -
Mineral Processing
Mineral Processing Foundations of theory and practice of minerallurgy 1st English edition JAN DRZYMALA, C. Eng., Ph.D., D.Sc. Member of the Polish Mineral Processing Society Wroclaw University of Technology 2007 Translation: J. Drzymala, A. Swatek Reviewer: A. Luszczkiewicz Published as supplied by the author ©Copyright by Jan Drzymala, Wroclaw 2007 Computer typesetting: Danuta Szyszka Cover design: Danuta Szyszka Cover photo: Sebastian Bożek Oficyna Wydawnicza Politechniki Wrocławskiej Wybrzeze Wyspianskiego 27 50-370 Wroclaw Any part of this publication can be used in any form by any means provided that the usage is acknowledged by the citation: Drzymala, J., Mineral Processing, Foundations of theory and practice of minerallurgy, Oficyna Wydawnicza PWr., 2007, www.ig.pwr.wroc.pl/minproc ISBN 978-83-7493-362-9 Contents Introduction ....................................................................................................................9 Part I Introduction to mineral processing .....................................................................13 1. From the Big Bang to mineral processing................................................................14 1.1. The formation of matter ...................................................................................14 1.2. Elementary particles.........................................................................................16 1.3. Molecules .........................................................................................................18 1.4. Solids................................................................................................................19 -
Uraninite Alteration in an Oxidizing Environment and Its Relevance to the Disposal of Spent Nuclear Fuel
TECHNICAL REPORT 91-15 Uraninite alteration in an oxidizing environment and its relevance to the disposal of spent nuclear fuel Robert Finch, Rodney Ewing Department of Geology, University of New Mexico December 1990 SVENSK KÄRNBRÄNSLEHANTERING AB SWEDISH NUCLEAR FUEL AND WASTE MANAGEMENT CO BOX 5864 S-102 48 STOCKHOLM TEL 08-665 28 00 TELEX 13108 SKB S TELEFAX 08-661 57 19 original contains color illustrations URANINITE ALTERATION IN AN OXIDIZING ENVIRONMENT AND ITS RELEVANCE TO THE DISPOSAL OF SPENT NUCLEAR FUEL Robert Finch, Rodney Ewing Department of Geology, University of New Mexico December 1990 This report concerns a study which was conducted for SKB. The conclusions and viewpoints presented in the report are those of the author (s) and do not necessarily coincide with those of the client. Information on SKB technical reports from 1977-1978 (TR 121), 1979 (TR 79-28), 1980 (TR 80-26), 1981 (TR 81-17), 1982 (TR 82-28), 1983 (TR 83-77), 1984 (TR 85-01), 1985 (TR 85-20), 1986 (TR 86-31), 1987 (TR 87-33), 1988 (TR 88-32) and 1989 (TR 89-40) is available through SKB. URANINITE ALTERATION IN AN OXIDIZING ENVIRONMENT AND ITS RELEVANCE TO THE DISPOSAL OF SPENT NUCLEAR FUEL Robert Finch Rodney Ewing Department of Geology University of New Mexico Submitted to Svensk Kämbränslehantering AB (SKB) December 21,1990 ABSTRACT Uraninite is a natural analogue for spent nuclear fuel because of similarities in structure (both are fluorite structure types) and chemistry (both are nominally UOJ. Effective assessment of the long-term behavior of spent fuel in a geologic repository requires a knowledge of the corrosion products produced in that environment. -
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. -
Studtite UO4 • 4H2O C 2001-2005 Mineral Data Publishing, Version 1
Studtite UO4 • 4H2O c 2001-2005 Mineral Data Publishing, version 1 Crystal Data: Monoclinic, pseudohexagonal. Point Group: 2/m, m, or 2. Needlelike crystals, elongated along [001], to 1 mm, in radial fibrous aggregates and crusts. Physical Properties: Tenacity: Flexible. Hardness = Soft. D(meas.) = 3.58 (synthetic). D(calc.) = 3.64 Radioactive. Optical Properties: Translucent to transparent. Color: Yellow to pale yellow; nearly colorless in transmitted light. Luster: Vitreous. Optical Class: Biaxial (+). Orientation: Z = elongation. α = 1.537–1.551 β = 1.555–1.686 γ = 1.680–1.690 2V(meas.) = Small. Cell Data: Space Group: C2/m, Cm, or C2. a = 11.85(2) b = 6.80(1) c = 4.25(1) β =93◦51(20)0 Z=2 X-ray Powder Pattern: Menzenschwand, Germany. 5.93 (10), 3.40 (8), 2.96 (6), 2.23 (6), 2.02 (5), 1.970 (5b), 4.27 (4) Chemistry: Qualitative microchemical and electron microprobe analyses typically show major U with traces of Pb, H2O, CO3 attributed to impurities. Characterization of naturally-occurring material thus rests on equivalence of the X-ray pattern and optical properties with the synthetic compound, and chemical behavior as a peroxide. Occurrence: A very rare mineral in the oxidized zone of some uranium-bearing mineral deposits. Association: Uranophane, rutherfordine, lepersonnite (Shinkolobwe, Congo); billietite, uranophane, rutherfordine, barite, quartz, hematite, “limonite” (Menzenschwand, Germany); tengchongite, calcurmolite, kivuite (Tengchong Co., China). Distribution: From Shinkolobwe, Katanga Province, Congo (Shaba Province, Zaire). At Menzenschwand, Black Forest, Germany. From Mitterberg, Salzburg, Austria. In France, at Davignac, Corr`eze,and from the Mas-d’Alary uranium deposit, three km south-southeast of Lod`eve, H´erault.In Tengchong Co., and at Tongbiguan village, Yingjiang Co., Yunnan Province, China. -
Thermodynamics of Uranyl Minerals: Enthalpies of Formation of Rutherfordine, UO2CO3
American Mineralogist, Volume 90, pages 1284–1290, 2005 Thermodynamics of uranyl minerals: Enthalpies of formation of rutherfordine, UO2CO3, andersonite, Na2CaUO2(CO3)3(H2O)5, and grimselite, K3NaUO2(CO3)3H2O KARRIE-ANN KUBATKO,1 KATHERYN B. HELEAN,2 ALEXANDRA NAVROTSKY,2 AND PETER C. BURNS1,* 1Department of Civil Engineering and Geological Sciences, University of Notre Dame, 156 Fitzpatrick Hall, Notre Dame, Indiana 46556, U.S.A. 2Thermochemistry Facility and NEAT ORU, University of California at Davis, One Shields Avenue, Davis, California 95616, U.S.A. ABSTRACT Enthalpies of formation of rutherfordine, UO2CO3, andersonite, Na2CaUO2(CO3)3(H2O)5, and grimselite, K3NaUO2(CO3)3(H2O), have been determined using high-temperature oxide melt solution Δ calorimetry. The enthalpy of formation of rutherfordine from the binary oxides, Hr-ox, is –99.1 ± 4.2 Δ kJ/mol for the reaction UO3 (xl, 298 K) + CO2 (g, 298 K) = UO2CO3 (xl, 298 K). The Hr-ox for ander- sonite is –710.4 ± 9.1 kJ/mol for the reaction Na2O (xl, 298 K) + CaO (xl, 298 K) + UO3 (xl, 298 K) Δ + 3CO2 (g, 298 K) + 5H2O (l, 298 K) = Na2CaUO2(CO3)3(H2O)6 (xl, 298 K). The Hr-ox for grimselite is –989.3 ± 14.0 kJ/mol for the reaction 1.5 K2O (xl, 298 K) + 0.5Na2O (xl, 298 K) + UO3 (xl, 298 K) + 3CO2 (g, 298 K) + H2O (l, 298 K) = K3NaUO2(CO3)3H2O (xl, 298 K). The standard enthalpies of Δ formation from the elements, Hº,f are –1716.4 ± 4.2, –5593.6 ± 9.1, and –4431.6 ± 15.3 kJ/mol for rutherfordine, andersonite, and grimselite, respectively. -
Periodic DFT Study of the Structure, Raman Spectrum and Mechanical
Periodic DFT Study of the Structure, Raman Spectrum and Mechanical Properties of Schoepite Mineral Francisco Colmeneroa*, Joaquín Cobosb and Vicente Timóna aInstituto de Estructura de la Materia (IEM-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 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 structure and Raman spectrum of schoepite mineral, [(UO2)8O2(OH)12] · 12 H2O, was studied by means of theoretical calculations. The computations were carried out by using Density Functional Theory with plane waves and pseudopotentials. A norm-conserving pseudopotential specific for the uranium atom developed in a previous work was employed. Since it was not possible to locate hydrogen atoms directly from X-ray diffraction data by structure refinement in the previous experimental studies, all the positions of the hydrogen atoms in the full unit cell were determined theoretically. The structural results, including the lattice parameters, bond lengths, bond angles and X-ray powder pattern were found in good agreement with their experimental counterparts. However, the calculations performed using the unit cell designed by Ostanin and Zeller in 2007, involving half of the atoms of the full unit cell, leads to significant errors in the computed X-ray powder pattern. Furthermore, Ostanin and Zeller’s unit cell contains hydronium ions, + H3O , that are incompatible with the experimental information. Therefore, while the use of this schoepite model may be a very useful approximation requiring a much smaller amount of computational effort, the full unit cell should be used to study this mineral accurately. -
Study of the Thermal Stability of Studtite by in Situ Raman Spectroscopy And
Study of the thermal stability of studtite by in situ Raman spectroscopy and DFT calculations Francisco Colmeneroa*, Laura J. Bonalesb, Joaquín Cobosb, 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 * Corresponding author. Tel.+34 915616800 Ext. 941033 E-mail address: [email protected] Abstract The design of a safe spent nuclear fuel repository requires the knowledge of the stability of the secondary phases which precipitate when water reaches the fuel surface. Studtite is recognized as one of the secondary phases that play a key-role in the mobilization of the radionuclides contained in the spent fuel. Thereby, it has been identified as a product formed under oxidation conditions at the surface of the fuel, and recently found as a corrosion product in the Fukushima-Daiichi nuclear plant accident. Thermal stability is one of the properties that should be determined due to the high temperature of the fuel. In this work we report a detailed analysis of the structure and thermal stability of studtite. The structure has been studied both by experimental techniques (SEM, TGA, XRD and Raman spectroscopy) and theoretical DFT electronic structure and spectroscopic calculations. The comparison of the results allows us to perform for the first time the Raman bands assignment of the whole spectrum. The thermal stability of studtite has been analyzed by in situ Raman spectroscopy, with the aim of studying the effect of the heating rate and the presence of water. -
Identification and Occurrence of Uranium and Vanadium Minerals from the Colorado Plateaus
SpColl £2' 1 Energy I TEl 334 Identification and Occurrence of Uranium and Vanadium Minerals from the Colorado Plateaus ~ By A. D. Weeks and M. E. Thompson ~ I"\ ~ ~ Trace Elements Investigations Report 334 UNITED STATES DEPARTMENT OF THE INTERIOR GEOLOGICAL SURVEY IN REPLY REFER TO: UNITED STATES DEPARTMENT OF THE INTERIOR GEOLOGICAL SURVEY WASHINGTON 25, D. C. AUG 12 1953 Dr. PhilUp L. Merritt, Assistant Director Division of Ra1'r Materials U. S. AtoTILic Energy Commission. P. 0. Box 30, Ansonia Station New· York 23, Nei< York Dear Phil~ Transmitted herewith are six copies oi' TEI-334, "Identification and occurrence oi' uranium and vanadium minerals i'rom the Colorado Plateaus," by A , D. Weeks and M. E. Thompson, April 1953 • We are asking !41'. Hosted to approve our plan to publish this re:por t as a C.i.rcular .. Sincerely yours, Ak~f777.~ W. H. ~radley Chief' Geologist UNCLASSIFIED Geology and Mineralogy This document consists or 69 pages. Series A. UNITED STATES DEPARTMENT OF TEE INTERIOR GEOLOGICAL SURVEY IDENTIFICATION AND OCCURRENCE OF URANIUM AND VANADIUM MINERALS FROM TEE COLORADO PLATEAUS* By A• D. Weeks and M. E. Thompson April 1953 Trace Elements Investigations Report 334 This preliminary report is distributed without editorial and technical review for conformity with ofricial standards and nomenclature. It is not for public inspection or guotation. *This report concerns work done on behalf of the Division of Raw Materials of the u. s. Atomic Energy Commission 2 USGS GEOLOGY AllU MINEFALOGY Distribution (Series A) No. of copies American Cyanamid Company, Winchester 1 Argulllle National La:boratory ., ., ....... -
SIMPLE URANIUM OXIDES, HYDROXIDES U4+ + U6+, SIMPLE and COMPLEX URANYL HYDROXIDES in ORES Andrey A
New Data on Minerals. 2011. Vol. 46 71 SIMPLE URANIUM OXIDES, HYDROXIDES U4+ + U6+, SIMPLE AND COMPLEX URANYL HYDROXIDES IN ORES Andrey A. Chernikov Fersman Mineralogical Museum, Russian Academy of Sciences, Moscow, [email protected], [email protected] The review of published and new own data of simple uranium oxides revealed that the formation of five simple oxides is probable: nasturan, sooty pitchblende, uraninite, uranothorianite, and cerianite. Among simple oxides, nasturan, sooty pitchblende, and uraninite are the most abundant in ores varied in genesis and mineralogy. Uranothorianite or thorium uraninite (aldanite) is occasional in the ores, while cerianite is believed in U-P deposits of Northern Kazakhstan. Hydrated nasturan is the most abundant among three uranium (IV+VI) hydroxides in uranium ores. Insignificant ianthinite was found in few deposits, whereas cleusonite was indentified only in one deposit. Simple uranyl hydroxides, schoepite, metaschoepite, and paraschoepite, are widespread in the oxidized ores of the near-surface part of the Schinkolobwe deposit. They are less frequent at the deeper levels and other deposits. Studtite and metastudtite are of insignificant industrial importance, but are of great inter- est to establish genesis of mineral assemblages in which they are observed, because they are typical of strongly oxidized conditions of formation of mineral assemblages and ores. The X-ray amorphous urhite associated with hydrated nasturan and the X-ray amorphous hydrated matter containing ferric iron and U6+ described for the first time at the Lastochka deposit, Khabarovsk krai, Russia are sufficiently abundant uranyl hydroxides in the oxidized uranium ores. Significant complex uranyl hydroxides with interlayer K, Na, Ca, Ba, Cu, Pb, and Bi were found basically at a few deposits: Schinkolobwe, Margnac, Wölsendorf, Sernyi, and Tulukuevo, and are less frequent at the other deposits, where quite large monomineralic segregations of nasturan and crystals of uraninite were identified. -
Thermodynamic Properties of Uranyl Containing Materials Based On
Thermodynamic Properties 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 were studied. These materials are among the most important secondary phases arising from corrosion of spent nuclear fuel under the final geological disposal conditions, and γ − UO3 is the main oxide of hexavalent uranium. The crystal structures of the dehydrated schoepite and metastudtite were determined by means of density functional theory using a new norm-conserving pseudopotential for uranium atom. The resulting structural properties and X-Ray powder patterns were found to be in very good agreement with the experimental data. By using the optimized structures of these materials, as well as of those obtained in previous works for studtite and soddyite, the thermodynamic properties of dehydrated schoepite, metastudtite, studtite and soddyite were determined, including specific heats, entropies, enthalpies and Gibbs free energies. Finally, the computed thermodynamic properties of these materials together with those reported previously for rutherfordine and γ − UO3 were used to determine their enthalpies and free energies of formation, and their variation with temperature. -
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.