Solid State Physics for the Structure of Uranium Oxide and Zinc Arsenide

Total Page:16

File Type:pdf, Size:1020Kb

Solid State Physics for the Structure of Uranium Oxide and Zinc Arsenide SOLID STATE PHYSICS FOR THE STRUCTURE OF URANIUM OXIDE AND ZINC ARSENIDE by Lydia S Harris A senior thesis submitted to the faculty of Brigham Young University - Idaho in partial fulfillment of the requirements for the degree of Bachelor of Science Department of Physics Brigham Young University - Idaho December 2019 Copyright c 2019 Lydia S Harris All Rights Reserved BRIGHAM YOUNG UNIVERSITY - IDAHO DEPARTMENT APPROVAL of a senior thesis submitted by Lydia S Harris This thesis has been reviewed by the research committee, senior thesis coor- dinator, and department chair and has been found to be satisfactory. Date Lance J Nelson, Advisor Date David Oliphant, Senior Thesis Coordinator Date Evan Hansen, Committee Member Date Todd Lines, Chair ABSTRACT SOLID STATE PHYSICS FOR THE STRUCTURE OF URANIUM OXIDE AND ZINC ARSENIDE Lydia S Harris Department of Physics Bachelor of Science Material properties are based on the structure of the material. Two ways to determine the structure of a material are a computational search for the ground state structures, and an experimental look using X-ray diffraction. In this work, these two ways are described and utilized to find the structure of two materials, uranium dioxide and zinc arsenide. Experimental techniques such as X-ray diffraction are used in order to better understand existing materials, but computational searches can be used in materials discovery. The consequences of using computational techniques is that new alloys with desirable properties can be discovered using inexpensive computer resources, however, the existence of such alloys must be validated experimentally. ACKNOWLEDGMENTS I would like to thank my parents, family, and friends for their support in my life, a.k.a. getting me through all the things that aren't schooling. As far as schooling is concerned, I would like to thank Richard Hatt for converting me to the pure science of physics and for inviting me to repent of disliking coding. I have grown greatly as a physicist in my classes under the guidance of many professors in the physics department at BYU-Idaho. Special thanks to Evan Hansen, Lance Nelson, and Jon Johnson for helping me learn to do research in many different fields using many different techniques. These experiences have been helpful in my development as a physicist and for building my resume. This helped me to get the two internships I was able to complete: the first at the Idaho National Laboratory with Lance Nelson and the second at BYU with John Colton. Another thanks to Lance Nelson for helping me out by reading and editing my thesis, as well as the other students that did the same. For anyone reading this far, I may as well also offer my unsolicited advice: start research as soon as possible in your physics career. It's great for your resume and especially for your development. Don't be afraid to ask for help from your peers and professors on homework and in life. And remember, physics is hard, but worth doing. Contents Table of Contents xi List of Figures xiii 1 Introduction1 1.1 Finding the Structure...........................1 1.1.1 Experimentally..........................2 1.1.2 Computationally.........................3 1.1.3 Verification............................4 1.2 Three Problems..............................4 1.2.1 Ag-Au \Toy Problem"......................4 1.2.2 Uranium Oxide Ground State Search..............5 1.2.3 Crystalline Structure of Zinc Arsenide.............5 2 Methodology7 2.1 Computational Methods.........................7 2.1.1 Density Functional Theory....................7 2.1.2 Machine Learning for Exhaustive Searches........... 10 2.2 Experimental Methods.......................... 19 2.2.1 Symmetries in Crystals...................... 19 2.2.2 X-ray Diffraction......................... 24 2.2.3 Single Crystal XRD........................ 26 2.2.4 Powder XRD........................... 27 3 Experiments 33 3.1 Ag-Au................................... 33 3.2 Uranium Oxide.............................. 34 3.2.1 DFT and Uranium........................ 34 3.3 Zinc Arsenide............................... 39 3.3.1 Collecting and Analyzing Data................. 40 4 Results and Discussion 43 4.1 Ag-Au................................... 43 4.2 Uranium Oxide.............................. 46 xi xii CONTENTS 4.3 Zinc Arsenide............................... 49 4.3.1 Initial P-XRD Results...................... 49 4.3.2 Single Crystal XRD Results................... 49 4.3.3 Later Powder XRD Results................... 51 4.3.4 DFT results............................ 52 5 Conclusion 55 5.1 Metals................................... 55 5.2 Uranium Dioxide Potential........................ 56 5.3 Zinc and Cadmium Arsenide....................... 57 Bibliography 59 A Zinc Arsenide Structural Information 65 B VASP settings 75 List of Figures 1.1 A convex hull (in green) for an A-B system. Blue points indicate phases that are not on the hull and therefore unstable. Red points indicate stable phases. Figure from Ref [10]....................2 2.1 Iterative workflow to solve a transcendental equation..........9 2.2 Comparison of atomic wave functions of Mn using the PAW method (solid line) with the exact result (bullets) for a given energy and angular momentum. Shown also are their differences magnified by a factor of 10 (dash-dotted line), and their pseudo wave functions (dashed line). Figure from Ref [2]............................ 11 2.3 The ith atom's neighborhood is made up of each atom within some Rcut of itself. The total energy E is made up of the contributions from individual neighborhoods. The energy contribution, Vi, of neighbor- hood ni depends on the separation between atoms i and j, rij, and a discrete variable, zj, that represents the species of the atom in the neighborhood (I or II in this illustration). Figure from Ref [8].... 13 2.4 Simple 2-dimensional visualization of configuration space vs. energy with a best fit \line". Each configuration is on the x-axis with it's corresponding energy on the y-axis. In reality this graph would be N+1 dimensional, where N is the number of basis functions Bα (n).. 14 2.5 An illustration of the filling of configuration space. As more structures are added to the training set, finer details present themselves in the model.................................... 17 2.6 Active learning during relaxation. If MTP extrapolates too much (γ ≥ γtsh), the configuration is added to the pre-selected set, and MTP predicts the energies, fores, and stresses of the configuration. If a second threshold is reached (γ ≥ Γtsh), relaxation is terminated and no predictions are completed. Figure from Ref [8]............ 18 2.7 Anti-fluorite structure of oxides such as Li2O or Na2O......... 20 xiii xiv LIST OF FIGURES 2.8 Structure of Zn3As2 proposed by Dr. Campbell, isomorphic to struc- ture of Cd3As2 given in Ref [1], a 25% cation deficient 2x2x4 anti- fluorite structure, referred to in this work as SymSG-A. Note that va- cancies accounting for the zinc (grey) deficiencies can be seen in several places.................................... 20 2.9 A crystal from each of the 230 space groups. Figure from Ref [35]... 23 2.10 Low background sample holder for powder X-ray diffraction scans... 29 2.11 Cone of diffracted light that is recorded in P-XRD. Figure from Ref [23]. 30 3.1 Preferred structure of UO2, the fluorite structure with uranium (blue) atoms located on the face centered cubic sites, and oxygen (red) atoms located on the simple cubic sites..................... 35 3.2 Two equivalent structures, with different directions for the layers. No- tice that on the right, every \1" atom lies in an uncircled layer, but on the left side, \1" atoms lie in both circled and uncircled layers. Choos- ing the correct direction preserves the layers and makes them able to be modeled as anti-ferromagnetic..................... 37 3.3 An example of a super periodic structure (right) of the unit cell (left). The structures are equivalent, but are represented by different lattice and basis vectors.............................. 38 4.1 Convex hull of Ag-Au system as determined by 294 high-throughput ab initio calculations. The 50% concentration structure is the B10 structure shown in Fig 4.2. Figure from Ref [6]............. 44 4.2 The B10 crystal structure. It is similar to the fcc crystal structure. It is the structure of Ag-Au at 50% concentration. Figure from Ref [6]. 44 4.3 Convex hull of Ag-Au system as determined by the ML potential relax- ation of 38,109 structures. This convex hull has shallow ground states that were not found in the high-throughput search of the same system shown in Fig 4.1. This may be due to fitting errors (this fitting has a mean absolute error of 0.8 meV/atom), as a few meV would place some of these structures above the convex hull. The training set for this model had 1556 configurations in it................. 45 4.4 One plane of a derivative fluorite structure with 2:1 oxygen (red) to uranium (blue) stoichiometry. Shown also are the forces on these atoms calculated by VASP (solid pink arrows) and predicted by the ML po- tential (dashed black arrows)....................... 48 4.5 Powder XRD data for 99.9% (blue) and 99.999% (red) pure Zn3As2.. 50 4.6 Powder XRD data for 99.999% pure Zn3As2 (red) fit to the structure obtained from SC-XRD analysis (green peaks, blue profile)....... 53 Chapter 1 Introduction The crystalline structures of materials give them their properties. Some of these prop- erties include strength, hardness, heat and electrical conduction, magnetic properties, and even color. This means that there is great power in knowing the structure of a material because it determines their properties. Searching for materials with specific properties is easier if their structures are already known. 1.1 Finding the Structure Materials science is the study of materials and their properties. With recent increases in computing power, a large part of this science has become theoretical and computa- tional, but experimental validation is still necessary to verify the results.
Recommended publications
  • Measurement of Uranium Dioxide Thermophysical Properties by the Laser Flash Method
    2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 MEASUREMENT OF URANIUM DIOXIDE THERMOPHYSICAL PROPERTIES BY THE LASER FLASH METHOD Pablo Andrade Grossi 1, Ricardo Alberto Neto Ferreira 2, Denise das Mercês Camarano 3, Roberto Márcio de Andrade 4 1,2,3 Centro de Desenvolvimento da Tecnologia Nuclear-CDTN Comissão Nacional de Energia Nuclear-CNEN Av. Presidente Antônio Carlos 6627 Cidade Universitária-Pampulha-Caixa Postal 941 CEP: 31.161-970 Belo Horizonte, MG 1 [email protected] 2 [email protected] 3 [email protected] 4 Departamento de Engenharia Mecânica Escola de Engenharia da Universidade Federal de Minas Gerais Av. Presidente Antônio Carlos 6627-Cidade Universitária-Pampulha CEP: 31.270-901 - Belo Horizonte – MG - Brasil 4 [email protected] ABSTRACT The evaluation of the thermophysical properties of uranium dioxide (UO 2), including a reliable uncertainty assessment, are required by the nuclear reactor design. These important informations are used by thermohydraulic codes to define operational aspects and to assure the safety, when analyzing various potential situations of accident. The Laser Flash Method had become the most popular method to measure the thermophysical properties of materials. Despite its several advantages, some experimental obstacles have been found due to the difficulty to obtain experimentally the ideals initial and boundary conditions required by the original method. An experimental apparatus and a methodology for estimating uncertainties of thermal diffusivity, thermal conductivity and specific heat measurements based on the Laser Flash Method are presented. A stochastic thermal diffusion modeling has been developed and validated by Standard Samples.
    [Show full text]
  • Depleted Uranium Technical Brief
    Disclaimer - For assistance accessing this document or additional information,please contact [email protected]. Depleted Uranium Technical Brief United States Office of Air and Radiation EPA-402-R-06-011 Environmental Protection Agency Washington, DC 20460 December 2006 Depleted Uranium Technical Brief EPA 402-R-06-011 December 2006 Project Officer Brian Littleton U.S. Environmental Protection Agency Office of Radiation and Indoor Air Radiation Protection Division ii iii FOREWARD The Depleted Uranium Technical Brief is designed to convey available information and knowledge about depleted uranium to EPA Remedial Project Managers, On-Scene Coordinators, contractors, and other Agency managers involved with the remediation of sites contaminated with this material. It addresses relative questions regarding the chemical and radiological health concerns involved with depleted uranium in the environment. This technical brief was developed to address the common misconception that depleted uranium represents only a radiological health hazard. It provides accepted data and references to additional sources for both the radiological and chemical characteristics, health risk as well as references for both the monitoring and measurement and applicable treatment techniques for depleted uranium. Please Note: This document has been changed from the original publication dated December 2006. This version corrects references in Appendix 1 that improperly identified the content of Appendix 3 and Appendix 4. The document also clarifies the content of Appendix 4. iv Acknowledgments This technical bulletin is based, in part, on an engineering bulletin that was prepared by the U.S. Environmental Protection Agency, Office of Radiation and Indoor Air (ORIA), with the assistance of Trinity Engineering Associates, Inc.
    [Show full text]
  • (12) United States Patent (10) Patent No.: US 8,333,879 B2 M00re Et Al
    US0083.33879B2 (12) United States Patent (10) Patent No.: US 8,333,879 B2 M00re et al. (45) Date of Patent: Dec. 18, 2012 (54) ELECTRODEPOSITION OF DELECTRIC (56) References Cited COATINGS ON SEMCONDUCTIVE SUBSTRATES U.S. PATENT DOCUMENTS 3,455,806 A 7/1969 Spoor et al. (75) Inventors: Kelly L. Moore, Dunbar, PA (US); 3,663,389 A 5, 1972 Koral et al. Michael J. Pawlik, Glenshaw, PA (US); 3,749,657 A 7, 1973 Le Bras et al. Michael G. Sandala, Pittsburgh, PA 3,793,278 A 2f1974 De Bona (US); Craig A. Wilson, Allison Park, PA 3,928, 157 A 12/1975 Suematsu et al. 3,947.338 A 3, 1976 Jerabek et al. (US) 3,947,339 A 3, 1976 Jerabek et al. 3,962,165 A 6, 1976 Bosso et al. (73) Assignee: PPG Industries Ohio, Inc., Cleveland, 3,975,346 A 8, 1976 Bosso et al. OH (US) 3,984,299 A 10, 1976 Jerabek (*) Notice: Subject to any disclaimer, the term of this (Continued) patent is extended or adjusted under 35 FOREIGN PATENT DOCUMENTS U.S.C. 154(b) by 0 days. EP OO12463 A1 6, 1980 (21) Appl. No.: 13/240,455 OTHER PUBLICATIONS (22) Filed: Sep. 22, 2011 Kohler, E. P. "An Apparatus for Determining Both the Quantity of Gas Evolved and the Amount of Reagent Consumed in Reactions (65) Prior Publication Data with Methyl Magnesium Iodide'. J. Am. Chem. Soc., 1927, 49 (12), US 2012/OOO6683 A1 Jan. 12, 2012 3181-3188, American Chemical Society, Washington, D.C. Related U.S.
    [Show full text]
  • Safety Data Sheet
    SAFETY DATA SHEET Revision Date 29-Jun-2018 Revision Number 1 SECTION 1: IDENTIFICATION OF THE SUBSTANCE/MIXTURE AND OF THE COMPANY/UNDERTAKING 1.1. Product identification Product Description: Cadmium arsenide Cat No. : 22773 CAS-No 12006-15-4 Molecular Formula As2 Cd3 1.2. Relevant identified uses of the substance or mixture and uses advised against Recommended Use Laboratory chemicals. Uses advised against No Information available 1.3. Details of the supplier of the safety data sheet Company Alfa Aesar . Avocado Research Chemicals, Ltd. Shore Road Port of Heysham Industrial Park Heysham, Lancashire LA3 2XY United Kingdom Office Tel: +44 (0) 1524 850506 Office Fax: +44 (0) 1524 850608 E-mail address [email protected] www.alfa.com Product Safety Department 1.4. Emergency telephone number Call Carechem 24 at +44 (0) 1865 407333 (English only); +44 (0) 1235 239670 (Multi-language) SECTION 2: HAZARDS IDENTIFICATION 2.1. Classification of the substance or mixture CLP Classification - Regulation (EC) No 1272/2008 Physical hazards Based on available data, the classification criteria are not met Health hazards Acute oral toxicity Category 3 (H301) Acute Inhalation Toxicity - Dusts and Mists Category 2 (H330) Environmental hazards ______________________________________________________________________________________________ ALFAA22773 Page 1 / 10 SAFETY DATA SHEET Cadmium arsenide Revision Date 29-Jun-2018 ______________________________________________________________________________________________ Acute aquatic toxicity Category 1 (H400) Chronic
    [Show full text]
  • High-Density Concrete with Ceramic Aggregate Based on Depleted Uranium Dioxide
    HIGH-DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DIOXIDE S.G. Ermichev, V.I. Shapovalov, N.V.Sviridov (RFNC-VNIIEF, Sarov, Russia) V.K. Orlov, V.M. Sergeev, A. G. Semyenov, A.M. Visik, A.A. Maslov, A. V. Demin, D.D. Petrov, V.V. Noskov, V. I. Sorokin, O. I. Uferov (VNIINM, Moscow, Russia) L. Dole (ORNL, Oak Ridge, USA) Abstract - Russia is researching the production and testing of concretes with ceramic aggregate based on depleted uranium dioxide (UO2). These DU concretes are to be used as structural and radiation-shielded material for casks for A-plant spent nuclear fuel transportation and storage. This paper presents the results of studies aimed at selection of ceramics and concrete composition, justification of their production technology, investigation of mechanical properties, and chemical stability. This Project is being carried out at the A.A. Bochvar All-Russian Scientific-Research Institute of inorganic materials (VNIINM, Russia) and Russian Federal Nuclear Center – All-Russia Scientific Research Institute of Experimental Physics (RFNC-VNIIEF, Russia). This Project #2691 is financed by the International Science and Technology Center (ISTC) under collaboration of the Oak- Ridge National Laboratory (USA) I. INTRODUCTION The current practice of ensuring the required gamma conduction, thermo-, radiation and corrosion resistance, shielding and strength of metal-concrete casks is based on service life and water resistance. concrete density. For this purpose high-density rocks Specific characteristics of UO2’s chemical activity (magnetite, iron glance, barium sulfate, etc.) as well as because of its small size of particles and thus great specific scrap, scale, broken metal chips and others are introduced surface area prevent the use of traditional methods of UO2 into concrete as coarse aggregates.
    [Show full text]
  • I -F??TI O08'w –Gçanooog –Ggan
    Feb. 27, 1962 L. BURRIS, JR., ETA 3,023,097 REPROCESSING URANIUM DIOXDE FUES Filed Nov. 23, 1959 2 Sheets-Sheet I-F??TI OOOG–ggan O08’w–gçan no?opa8 (g?20%OG) INVENTOR. Les lie 8urris, Jr. Af r e di S c h n e i der Attorney Feb. 27, 1962 L. BURRIS, JR., ETA 3,023,097 REPROCESSING URANIUM DIOXDE FUELS Filed Nov. 23, 1959 2 Sheets-Sheet 2 - 4O - 5 ? - 6 O - 8O - 9 O - OO - , ? - 2 O - 3 O Nd 2O Gnd Sm2O3 - 4 O - 150 Pr2O3 and Ce2O3 O 3OO 5OO IOOO 5OO 2OOO 25 OO Temperature (K) F I Leslie Burris,INVENTOR. Jr. Alfred Schneid er BY ????? C???-e Attorney - 3,023,097 United States Patent Office Patented Feb. 27, 1962 2 of the dioxide fuel and its commingled substances in prep 3,323,097 aration for the next step about to be described; this size REPROCESSING GUARNUM DIXE FUELS Lesie Burris, Jr., and Alfred Schneider, Naperville, H., reduction is best carried out by successive oxidations and aSsigi nors to the United States of America as rere reductions which cause crumbling by reason of the suc sented by the United States Atomic Energy Cons cessive changes in crystal structure. After the particle ?$$??? size has been reduced sufficiently, a molten reducing i Fied Nov. 23, 1959, Ser. No. 854,989 metal of the group consisting of zinc and cadmium is 4 Claims. (C. 75-84.) introduced to the crumbled mixture, and this causes quite a number of metals to go into the metallic state, where The invention relates to a novel pyrometalurgical O upon they alloy with the reducing metal and the molten method of reprocessing uranium dioxide fuels after they metal phase may then be separated from the solid oxide have become contaminated by ª fission products in i nu phase consisting of the oxides of metals such as uranium, clear reactors, and more particularly, to a novel method rare earths and plutonium which are still not reduced.
    [Show full text]
  • 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]
  • Experimental Studies of Neutron Irradiated Uranium Dioxide at High Temperatures
    NL90C1051 lNIS-mi— 12739 Experimental studies of neutron irradiated uranium dioxide at high temperatures R.H.J. Tanke EXPERIMENTAL STUDIES OF NEUTRON IRRADIATED URANIUM DIOXIDE AT HIGH TEMPERATURES EXPERIMENTELE STUDIES VAN MET NEUTRONEN BESTRAALD URANIUMDIOXIDE BIJ HOGE TEMPERATUREN (met een samenvatting in het Nederlands) PROEFSCHRIFT TER VERKRIJGING VAN DE GRAAD VAN DOCTOR AAN DE RIJKSUNIVERSITEIT TE UTRECHT, OP GEZAG VAN DE RECTOR MAGNIFICUS PROF.DR. J.A. VAN GÏNKEL, VOLGENS BESLUIT VAN HET COLLEGE VAN DEKANEN IN HET OPENBAAR TE VERDEDIGEN OP WOENSDAG 20 JUNI 1990 DES NAMIDDAGS TE 4.15 UUR. door Richardus Hendrikus Johannes Tanke geboren op 19 april 1957 te Hengelo (O) Promotor: Prof.Dr. CD. Andriesse Aan Pien CIP-GEGEVENS KONINKLIJKE BIBLIOTHEEK DEN HAAG Tanke, Richardus Hend. ^kus Johannes Experimental studies of neutron irradiated uranium dioxide at high temperatures / Richardus Hendrikus Johannes Tanke. - Arnhem : KEMA. - 111. Thesis Utrecht. - With index, ref. - With summary in Dutch. ISBN 90-353-1023-3 pbk. ISBN 90-353-1024-1 geb. SISO 538 UDC [539.125.06:546.791-31:536.45](043.3) Subject headings: uranium dioxide / gamma tomography. Contents Summary and outline 7 Outline of this thesis 9 Chapter 1: Introduction 11 The safety issue during the development of nuclear power 11 Experimental programmes on the release of fission products 15 from overheated fuel The KEMA source term experiment 17 References 18 Chapter 2: Experimental equipment and laboratory facilities 21 The hot cell 23 Measurement equipment for the evaporation experiment
    [Show full text]
  • Nuclear Fuel Cycle
    Quality and Standards for your converted material Hex Business at Springfields • Westinghouse will deliver on its promise of providing quality assurance for your company. • We pride ourselves on our engineering expertise and technical ability working to international standards including ISO 9001, 14001 and 18001. • Springfields has a long and successful history in the fuel cycle with over 40 years expertise in Hex conversion. Natural Mining Enrichment Fuel Fabrication Milling Nuclear Conversion Fuel Cycle Power Plant Reprocessing Electricity High Level Waste Storage Spent Fuel Storage www.westinghousenuclear.com Hex Business Rotary Kiln Plant Hex Plant Modern nuclear reactor designs such as Pressurised Water and Light Water Reactors To Atmosphere Uranium Trioxide UO – UF Conversion UF – UF Conversion UO 3 4 4 6 need nuclear fuel, made from Uranium Dioxide. 3 UO3 is transported to Kiln Plant in drums where it Uranium Hexafluoride is produced by the reaction UO To Atmosphere 3 is transferred onto a conveyor system. From here of UF with elemental gaseous fluorine in a Uranium Hexafluoride (UF6 ) is an essential intermediate product used in the Feed Hopper 4 Run Off Discharge the drums are delivered into the process via a fluidised bed reactor at 475°C. The fluorine manufacture of Uranium Dioxide fuels. Water UF6 mechanised tipping system. is produced by the electrolysis of anhydrous Condensers Hydration is the first stage in the treatment of hydrofluoric acid (AHF) in a potassium bi-fluoride Vac Back Air UO for the production of UF . electrolyte. 3 4 Secondary Meeting World Demands Advanced Technology Water Glycol Hydrator Heating & Cooling UO2 Transfer AHF Primary The Springfields Hex facilities are capable of Both plants demonstrate proven and state- To Scrubbers Hopper To Scrubbers H2 Transport Rotary Off-Gas Cylinder producing up to 5,500 tU of (UF6) annually, of-the-art technology.
    [Show full text]
  • The Carbon Reduction of Uranium Oxide" (1964)
    View metadata, citation and similar papers at core.ac.uk brought to you by CORE provided by Digital Repository @ Iowa State University Ames Laboratory Technical Reports Ames Laboratory 10-1964 The ac rbon reduction of uranium oxide H. A. Wilhelm Iowa State University Follow this and additional works at: http://lib.dr.iastate.edu/ameslab_isreports Part of the Ceramic Materials Commons, and the Metallurgy Commons Recommended Citation Wilhelm, H. A., "The carbon reduction of uranium oxide" (1964). Ames Laboratory Technical Reports. 86. http://lib.dr.iastate.edu/ameslab_isreports/86 This Report is brought to you for free and open access by the Ames Laboratory at Iowa State University Digital Repository. It has been accepted for inclusion in Ames Laboratory Technical Reports by an authorized administrator of Iowa State University Digital Repository. For more information, please contact [email protected]. The ac rbon reduction of uranium oxide Abstract The preparation of uranium metal directly from its oxides has been studied by a number of investigators. Various approaches have been pursued in these studies. Some attempts to produce the metal by electrolysis of the oxide in fused salt have been made; however, the reductions of the oxides by another metal and by carbon have attracted most attention. Although no entirely satisfactory method has yet been developed for preparation of uranium metal directly from oxide, the ready availability of high purity oxides makes such a process of interest. An investigation dealing with an approach to this problem is reported here. Disciplines Ceramic Materials | Metallurgy This report is available at Iowa State University Digital Repository: http://lib.dr.iastate.edu/ameslab_isreports/86 IS-1023 IOWA STATE UNIVERSITY THE CARBON REDUCTION OF URANIUM OXIDE by H.
    [Show full text]
  • March 8, 1966 F. H. DIL, JR 3,239,393 METHOD for PRODUCING SEMICONDUCTOR ARTICLES Filed Dec
    March 8, 1966 F. H. DIL, JR 3,239,393 METHOD FOR PRODUCING SEMICONDUCTOR ARTICLES Filed Dec. 31, 1962 2. Sheets-Sheet FG. MATER ALS STEPS SEMCONDUCTOR COMPOUND CRYSTAL POLISH CHEMICAL POLISH ACCEPTOR DFFUSANT SOURCE INTRODUCE COMPOUND MEASURED CHARGE HAVING AN ON OF DFFUSANT FROM SAME PERODC COMPOUND GROUP AS CRYSTAL ANION EVACUATE HEAT TO VAPOR DIFFUSE FOR MEASURED TIME ATTACH ELECTRODES INVENTOR. FREDERICK H. DLL JR ATTORNEY March 8, 1966 F., H., DL, JR 3,239,393 METHOD FOR PRODUCING SEMCONDUCTOR ARTICLES Filed Dec. 31, 962 2. Sheets-Sheet 2 Šes is series NNNNN r N NNNNNNNN 3,239,393 United States Patent Office Patented Mar. 8, 1966 2. to produce precisely the desired results. For instance, 3,239,393 when metallic zinc is used as the diffusant material for METHOD FOR PRODUCING SEMCONDUCTOR a gallium arsenide substrate, it is very difficult to obtain ARTICLES the pure zinc metal with no zinc oxide film upon the metal. Frederick H. Dii, Jr., Patnam Waley, N.Y., assigor to 5 Furthermore, the metal is so tough that it is difficult to International Business Machines Corporation, New divide a pure metal sample into smaller pieces in order York, N.Y., a corporation of New York to obtain exactly the correct quantity for the diffusion Filed Dec. 31, 1962, Ser. No. 248,679 process. The zinc oxide on the surface of the metallic Zinc 7 Claims. (C. 48-189) diffusant material is very undesirable for a number of This invention relates to an improved diffusion process IO reasons. The oxygen is not wanted in the diffusion Vapor, for the production of Semiconductor devices, and more and the zinc oxide tends to form a protective coating particularly to an improved vapor diffusion process in over the zinc which inhibits the formation of the desired which the introduction of unwanted impurities is very zinc metal vapor which is required for the diffusion proc effectively and simply avoided, and which possesses other CSS.
    [Show full text]
  • Chemical Names and CAS Numbers Final
    Chemical Abstract Chemical Formula Chemical Name Service (CAS) Number C3H8O 1‐propanol C4H7BrO2 2‐bromobutyric acid 80‐58‐0 GeH3COOH 2‐germaacetic acid C4H10 2‐methylpropane 75‐28‐5 C3H8O 2‐propanol 67‐63‐0 C6H10O3 4‐acetylbutyric acid 448671 C4H7BrO2 4‐bromobutyric acid 2623‐87‐2 CH3CHO acetaldehyde CH3CONH2 acetamide C8H9NO2 acetaminophen 103‐90‐2 − C2H3O2 acetate ion − CH3COO acetate ion C2H4O2 acetic acid 64‐19‐7 CH3COOH acetic acid (CH3)2CO acetone CH3COCl acetyl chloride C2H2 acetylene 74‐86‐2 HCCH acetylene C9H8O4 acetylsalicylic acid 50‐78‐2 H2C(CH)CN acrylonitrile C3H7NO2 Ala C3H7NO2 alanine 56‐41‐7 NaAlSi3O3 albite AlSb aluminium antimonide 25152‐52‐7 AlAs aluminium arsenide 22831‐42‐1 AlBO2 aluminium borate 61279‐70‐7 AlBO aluminium boron oxide 12041‐48‐4 AlBr3 aluminium bromide 7727‐15‐3 AlBr3•6H2O aluminium bromide hexahydrate 2149397 AlCl4Cs aluminium caesium tetrachloride 17992‐03‐9 AlCl3 aluminium chloride (anhydrous) 7446‐70‐0 AlCl3•6H2O aluminium chloride hexahydrate 7784‐13‐6 AlClO aluminium chloride oxide 13596‐11‐7 AlB2 aluminium diboride 12041‐50‐8 AlF2 aluminium difluoride 13569‐23‐8 AlF2O aluminium difluoride oxide 38344‐66‐0 AlB12 aluminium dodecaboride 12041‐54‐2 Al2F6 aluminium fluoride 17949‐86‐9 AlF3 aluminium fluoride 7784‐18‐1 Al(CHO2)3 aluminium formate 7360‐53‐4 1 of 75 Chemical Abstract Chemical Formula Chemical Name Service (CAS) Number Al(OH)3 aluminium hydroxide 21645‐51‐2 Al2I6 aluminium iodide 18898‐35‐6 AlI3 aluminium iodide 7784‐23‐8 AlBr aluminium monobromide 22359‐97‐3 AlCl aluminium monochloride
    [Show full text]