Production of Yellow Cake and Uranium Fluorides
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Vanadium Pentoxide and Other Inorganic Vanadium Compounds
This report contains the collective views of an international group of experts and does not necessarily represent the decisions or the stated policy of the United Nations Environment Programme, the International Labour Organization, or the World Health Organization. Concise International Chemical Assessment Document 29 VANADIUM PENTOXIDE AND OTHER INORGANIC VANADIUM COMPOUNDS Note that the layout and pagination of this pdf file are not identical to the printed CICAD First draft prepared by Dr M. Costigan and Mr R. Cary, Health and Safety Executive, Liverpool, United Kingdom, and Dr S. Dobson, Centre for Ecology and Hydrology, Huntingdon, United Kingdom Published under the joint sponsorship of the United Nations Environment Programme, the International Labour Organization, and the World Health Organization, and produced within the framework of the Inter-Organization Programme for the Sound Management of Chemicals. World Health Organization Geneva, 2001 The International Programme on Chemical Safety (IPCS), established in 1980, is a joint venture of the United Nations Environment Programme (UNEP), the International Labour Organization (ILO), and the World Health Organization (WHO). The overall objectives of the IPCS are to establish the scientific basis for assessment of the risk to human health and the environment from exposure to chemicals, through international peer review processes, as a prerequisite for the promotion of chemical safety, and to provide technical assistance in strengthening national capacities for the sound management -
Getinge Lancer LSS 590 Laboratory Steam Sterilizer Specifications GETINGE LANCER LSS 590 2 Basic Specifications
Getinge Lancer LSS 590 Laboratory Steam Sterilizer Specifications GETINGE LANCER LSS 590 2 Basic specifications Top Top, Recessed 64.7 39.5 63.9 26 63 51 26.5 74 Front Side, Recessed LSS 590 • Internal Volume 20.7 cu. ft. (586 L) • Door Configurations Single Door or Double Door, Pass-through • Design Operating Temperature Gravity/Vacuum Cycles: 230°–275°F (110°–135°C) Liquid Cycles: 219°–275°F (104°–135°C) Optional Low Temp Cycle: 169°–212°F (76°–100°C) • Interior Dimensions (w × h × d) 26.5" × 26.5" × 51" (672 × 672 × 1300 mm) • Exterior Dimensions (w × h × d) Single Door: 39.5" × 74" × 63.9” (1003 × 1880 × 1623 mm) Double Door: 39.5" × 74" × 64.7" (1003 × 1880 × 1643 mm) GETINGE LANCER LSS 590 3 Part 1: Selection Guide Door Configuration • single door • double door, pass-through Steam Source • facility/house steam (standard) • steam generator(s) - 208V, AC, 50/60Hz, 3-phase - 240V, AC, 50/60Hz, 3-phase - 380V, AC, 50Hz, 3-phase - 480V, AC, 60Hz, 3-phase - 600V, AC, 60Hz, 3-phase - carbon steel (standard) - stainless steel - manual blowdown (standard) - automatic blowdown Steam generator is located integral to the sterilizer (possible in combination with vacuum pump for LSS 590). Remotely located Air Removal • ejector (standard) • vacuum pump, liquid ring - 208V, AC, 60Hz, 3-phase - 380V, AC, 50Hz, 3-phase - 480V, AC, 60Hz, 3-phase Additional Programs • Sealed liquids and low temp cycles (vacuum pump and load probe required) Recesses and Barriers • recessed, one-wall • recessed, two-wall • freestanding (cabinet enclosure panels required) • with cross contamination barrier flange GETINGE LANCER LSS 590 DATE: CUSTOMER / FACILITY: 4 Part 2: General Specifications The Getinge Lancer LSS 590 Steam Sterilizer is designed Specifications Index for high- performance sterilization of labware, media and Sterilizer 6 laboratory byproducts used in research, analytical, environ- mental and industrial laboratories. -
In Situ Leach (ISL) Mining of Uranium
In Situ Leach (ISL) Mining of Uranium (June 2009) l Most uranium mining in the USA and Kazakhstan is now by in situ leach methods, also known as in situ recovery (ISR). l In USA ISL is seen as the most cost effective and environmentally acceptable method of mining, and Australian experience supports this. l Australia's first ISL uranium mine is Beverley, which started operation late in 2000. The proposal for Honeymoon has government approval and it is expected to be operating in 2008. Conventional mining involves removing mineralised rock (ore) from the ground, breaking it up and treating it to remove the minerals being sought. In situ leaching (ISL), also known as solution mining, or in situ recovery (ISR) in North America, involves leaving the ore where it is in the ground, and recovering the minerals from it by dissolving them and pumping the pregnant solution to the surface where the minerals can be recovered. Consequently there is little surface disturbance and no tailings or waste rock generated. However, the orebody needs to be permeable to the liquids used, and located so that they do not contaminate ground water away from the orebody. Uranium ISL uses the native groundwater in the orebody which is fortified with a complexing agent and in most cases an oxidant. It is then pumped through the underground orebody to recover the minerals in it by leaching. Once the pregnant solution is returned to the surface, the uranium is recovered in much the same way as in any other uranium plant (mill). In Australian ISL mines (Beverley and the soon to be opened Honeymoon Mine) the oxidant used is hydrogen peroxide and the complexing agent sulfuric acid. -
Gas Phase Chemical Evolution of Uranium, Aluminum, and Iron Oxides Received: 22 January 2018 Batikan Koroglu1, Scott Wagnon 1, Zurong Dai1, Jonathan C
www.nature.com/scientificreports OPEN Gas Phase Chemical Evolution of Uranium, Aluminum, and Iron Oxides Received: 22 January 2018 Batikan Koroglu1, Scott Wagnon 1, Zurong Dai1, Jonathan C. Crowhurst1, Accepted: 19 June 2018 Michael R. Armstrong1, David Weisz1, Marco Mehl1,2, Joseph M. Zaug1, Harry B. Radousky1 & Published: xx xx xxxx Timothy P. Rose1 We use a recently developed plasma-fow reactor to experimentally investigate the formation of oxide nanoparticles from gas phase metal atoms during oxidation, homogeneous nucleation, condensation, and agglomeration processes. Gas phase uranium, aluminum, and iron atoms were cooled from 5000 K to 1000 K over short-time scales (∆t < 30 ms) at atmospheric pressures in the presence of excess oxygen. In-situ emission spectroscopy is used to measure the variation in monoxide/atomic emission intensity ratios as a function of temperature and oxygen fugacity. Condensed oxide nanoparticles are collected inside the reactor for ex-situ analyses using scanning and transmission electron microscopy (SEM, TEM) to determine their structural compositions and sizes. A chemical kinetics model is also developed to describe the gas phase reactions of iron and aluminum metals. The resulting sizes and forms of the crystalline nanoparticles (FeO-wustite, eta-Al2O3, UO2, and alpha-UO3) depend on the thermodynamic properties, kinetically-limited gas phase chemical reactions, and local redox conditions. This work shows the nucleation and growth of metal oxide particles in rapidly-cooling gas is closely coupled to the kinetically-controlled chemical pathways for vapor-phase oxide formation. Gas phase nucleation and growth of metal oxide nanoparticles is an important topic for many areas of chemistry, physics, material science, and engineering1–6. -
The Role of Pe, Ph, and Carbonate on the Solubility of UO2 and Uraninite Under Nominally Reducing Conditions
Geochimica et Cosmochimica Acta, Vol. 62, No. 13, pp. 2223–2231, 1998 Copyright © 1998 Elsevier Science Ltd Pergamon Printed in the USA. All rights reserved 0016-7037/98 $19.00 1 .00 PII S0016-7037(98)00140-9 The role of pe, pH, and carbonate on the solubility of UO2 and uraninite under nominally reducing conditions 1 1 1 1 2 2 3, IGNASI CASAS, JOAN DE PABLO, JAVIER GIMENEZ´ , M. ELENA TORRERO, JORDI BRUNO, ESTHER CERA, ROBERT J. FINCH, * and 3,† RODNEY C. EWING 1Department of Chemical Engineering, Polytechnic University of Catalunya, Barcelona 08028, Spain 2QuantiSci SL, Parc Tecnolo`gic del Valle`s, Cerdanyola 08290, Spain 3Department of Earth and Planetary Sciences, University of New Mexico, Albuquerque, New Mexico 87131, USA (Received August 14, 1997; accepted in revised form March 26, 1998) Abstract—Experimental data obtained from uranium dioxide solubility studies as a function of pH and under nominally reducing conditions in a 0.008 mol dm23 perchlorate medium and in a 1 mol dm23 chloride solution are presented. The solubility of extensively characterized uraninite samples from Cigar Lake (Canada), Jachymov (Czech Republic), and Oklo (Gabon) was determined in a solution matching the composition of a groundwater associated with granitic terrain. The redox potential of the test solution was monitored throughout the experimental period. The results obtained were modeled using aqueous formation constants compiled by the NEA, using stability constants corrected to appropriate ionic strengths. The solubility curves have been adjusted by calculating the 1 N value of Ks4 (UO2(s) 2H2O U(OH)4(aq)) that gave the best fit with the experimental data. -
Depleted Uranium Hexafluoride: Waste Or Resource?
UCRGJC-120397 PREPRINT Depleted Uranium Hexafluoride: Waste or Resource? N. Schwertz J. Zoller R Rosen S. Patton C. Bradley A. Murray This paper was prepared for submittal to the Global ‘95 International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems Versailles, France September 11-14,1995 July 1995 This isa preprint of apaper intended for publication in a jaurnal orproceedings. Since changes may be made before publication, this preprint is made available with the understanding that it will not be cited or reproduced without the permiasion of the anthor. DISCLAIMER This document was prepared as an account of work sponsored by an agency of the United Stat= Government. Neither theunited States Governmentmor theuniversity of California nor any oftheir employees, makes any warranty, express or implied, or assumesanylegalliabilityorrespomibility forthe accuracy,completeness,orusefuin~ of any information, apparatus, pduct, or process disdosed, or represents that its use wouldnotinfringe privatelyowned rights. Referencehemin to anyspe&c commercial prodocis, proms, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constituteor imply its endorsement, reconunendation, or favoring by the United States Government or the University of California. The views and opinions of authors expressed herein do not necessady state or reflect those of the United States Government or the University of California, and shall not be used for adveltising or product endorsement purposes. DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document . DEPLETED URANIUM HEXAFLUORIDE: WASTE OR RESOURCE? N. Schwertz, J. Zoller, R. Rosen, S. Patton LAWRENCE LIVERMORE NATIONAL LABORATORY P. -
Molecular Characterization of Uranium(VI) Sorption Complexes on Iron(III)-Rich Acid Mine Water Colloids
Geochimica et Cosmochimica Acta 70 (2006) 5469–5487 www.elsevier.com/locate/gca Molecular characterization of uranium(VI) sorption complexes on iron(III)-rich acid mine water colloids Kai-Uwe Ulrich a,*, Andre´ Rossberg a,b, Harald Foerstendorf a, Harald Za¨nker a, Andreas C. Scheinost a,b a Institute of Radiochemistry, FZ Rossendorf e.V., P.O. Box 510119, D-01314 Dresden, Germany b Rossendorf Beamline at ESRF, B.P. 220, F-38043 Grenoble, France Received 7 November 2005; accepted in revised form 21 August 2006 Abstract A mixing of metal-loaded acid mine drainage with shallow groundwater or surface waters usually initiates oxidation and/or hydrolysis of dissolved metals such as iron (Fe) and aluminum (Al). Colloidal particles may appear and agglomerate with increasing pH. Likewise chemical conditions may occur while flooding abandoned uranium mines. Here, the risk assessment of hazards requires reliable knowl- edge on the mobility of uranium (U). A flooding process was simulated at mesocosm scale by mixing U-contaminated acid mine water with near-neutral groundwater under oxic conditions. The mechanism of U-uptake by fresh precipitates and the molecular structure of U bonding were determined to estimate the mobility of U(VI). Analytical and spectroscopic methods such as Extended X-ray Absorption Fine-Structure (EXAFS) spectroscopy at the Fe K-edge and the U LIII-edge, and Attenuated Total Reflectance Fourier Transform Infra- red (ATR-FTIR) spectroscopy were employed. The freshly formed precipitate was identified as colloidal two-line ferrihydrite. It removed U(VI) from solution by sorption processes, while surface precipitation or structural incorporation of U was not observed. -
Kinetic Studies of Sodium and Metforminium Decavanadates Decomposition and in Vitro Cytotoxicity and Insulin- Like Activity
inorganics Article Kinetic Studies of Sodium and Metforminium Decavanadates Decomposition and In Vitro Cytotoxicity and Insulin- Like Activity Aniela M. Silva-Nolasco 1,2, Luz Camacho 2 , Rafael Omar Saavedra-Díaz 1, Oswaldo Hernández-Abreu 1 , Ignacio E. León 3 and Irma Sánchez-Lombardo 1,* 1 Centro de Investigación de Ciencia y Tecnología Aplicada de Tabasco, División Académica de Ciencias Básicas (CICTAT), Universidad Juárez Autónoma de Tabasco, Carretera Cunduacán-Jalpa km. 1 Col. La Esmeralda, Cunduacán 86690, Tabasco, Mexico; [email protected] (A.M.S.-N.); [email protected] (R.O.S.-D.); [email protected] (O.H.-A.) 2 Laboratorio de Nutrición Experimental, Instituto Nacional de Pediatría, Ciudad de Mexico 04530, Mexico; [email protected] 3 Centro de Química Inorgánica CEQUINOR (CONICET, UNLP), Bv 120 1465, La Plata 1900, Argentina; [email protected] * Correspondence: [email protected] Received: 22 October 2020; Accepted: 2 December 2020; Published: 8 December 2020 Abstract: The kinetics of the decomposition of 0.5 and 1.0 mM sodium decavanadate (NaDeca) and metforminium decavanadate (MetfDeca) solutions were studied by 51V NMR in Dulbecco’s modified Eagle’s medium (DMEM) medium (pH 7.4) at 25 ◦C. The results showed that decomposition products 2 4 are orthovanadate [H2VO4]− (V1) and metavanadate species like [H2V2O7] − (V2), [V4O12] − (V4) 5 and [V5O15] − (V5) for both compounds. The calculated half-life times of the decomposition reaction were 9 and 11 h for NaDeca and MetfDeca, respectively, at 1 mM concentration. The hydrolysis products that presented the highest rate constants were V1 and V4 for both compounds. -
Uranium Dioxide Is Voluminous
r>r 19 i o% ORNL-4755 UC-25 - Metals, Ceramics, and Materials s <-;. CONVERSIOH OF V&&4VWA NITRATE TO i aRAMlC-OR^Dt OXIDE>fs6t THE U&HT W4TBT J- -« .•'--• "" * -„ -' r J* - J * \ ^ --; f % ;~, <r- 4>- >» N< DMSICH0F DAfE -,i M\OH CAR6IDE COft^0tATtOR. U.S. ATOMIC *N**0T COMMAS»OIV 9>f & ^ima®tf»T^^*tB iwww® 1 PH^sarf in «*£ Uf9t«t Stress e* America. A vatfatt» from ---Sri*; -3K- >f ~ - - i ,43^>*£«* «^ ixn^ar»# ac «*, mts&mf of work {passaged b? tfw Lhnw XtitNr tfgr *}~ti$*i $**m «ar t!» untod Soto* Aflymic ^ «^ awy ^ iftw^r itT»i&y*OT« nor mf sd ihev canifiesscs.. ^iU- >*• ^H^ **•-» *-*• V .24, i *~ eta* -4-T" * iL - - IBS kfiE- r-„- 2 • «. "« J" '»' i - ^r'-s^j. •NOTICt ORNL-4755 Contract No. W-7405-eng-26 METAI5 AND CERAMICS DIVISION CONVERSION OF URANIUM NITRATE TO CERAMIC-GRADE OXIDE FOR THE LIGHT WATER ESEEDER REACTOR: PROCESS DEVELOPMENT J. M. Leitnaker M. L. Smith C. M. Fitzpatrick APRIL 1972 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATIOJN for the U.S. ATOMIC ENERGY COMMISSION W5TWBUTI0N OF THIS DOCUMENT IS UftUMflli iii CONTENTS Page Abstract 1 Introduction 1 Previous Investigations - 3 Stabilisation 4 Behavior of IXfe in Dry Air or Oxygen at Lev Tenpera&ures . 5 Behavior of UCfe in Dry Air or Oxygen at High Temperatures . 5 Behavior of DC^ in Hoist Air 7 Stabilisation of UO2 by Control of Surface Area 7 Stabilization by Addition of Moisture 11 Stabilization of UO2 with Dry Ice 12 Mechanical Stabilization of UO2 13 Reduction of Uranate to UO2 14 General Process Description . -
Vacuum Products 450 455 454 453 452
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Precipitation of Aluminum Containing Species in Tank Wastes
PNNL-13881 Precipitation of Aluminum Containing Species in Tank Wastes S.V. Mattigod K.E. Parker D.T. Hobbs D.E. McCready April 2002 Prepared for the U.S. Department of Energy under Contract DE-AC06-76RL01830 PNNL-13881 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 Battelle Memorial Institute, nor any of their employees, makes any warranty, express 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. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. PACIFIC NORTHWEST NATIONAL LABORATORY operated by BATTELLE for the UNITED STATES DEPARTMENT OF ENERGY under Contract DE-AC06-76RL01830 This document was printed on recycled paper. (8/00 PNNL-13881 Precipitation of Aluminum Containing Species in Tank Wastes S. V. Mattigod D. T. Hobbs K. E. Parker D. E. McCready April 2002 Prepared for the U.S. Department of Energy under Contract DE-AC06-76RL01830 Pacific Northwest National Laboratory Richland, Washington 99352 Summary Aluminisilicate deposit buildup experienced during the tank waste volume-reduction process at the Savannah River Site (SRS) required an evaporator to be shut down in October 1999. -
Journal of Luminescence 210 (2019) 425–434
Journal of Luminescence 210 (2019) 425–434 Contents lists available at ScienceDirect Journal of Luminescence journal homepage: www.elsevier.com/locate/jlumin Insight into the effect of A-site cations on structural and optical properties of T RE2Hf2O7:U nanoparticles ∗ Maya Abdoua, Santosh K. Guptaa,b, Jose P. Zunigaa, Yuanbing Maoa,c, a Department of Chemistry, University of Texas Rio Grande Valley, 1201 West University Drive, Edinburg, TX, 78539, USA b Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai, 400085, India c School of Earth, Environmental, and Marine Sciences, University of Texas Rio Grande Valley, 1201 West University Drive, Edinburg, TX, 78539, USA ARTICLE INFO ABSTRACT Keywords: A2B2O7 type pyrochlores have been recently proposed as a potential nuclear waste host due to their many Uranium interesting properties. To assess and understand the performance of these compounds as nuclear waste hosts, the Pyrochlore speciation and structural investigations on actinide-doped RE2Hf2O7 are needed since both are imperative from Phase-transition their application perspective. In this work, we investigated the effect of uranium doping at different con- Luminescence centrations in the range of 0–10% on the structural and optical properties of RE Hf O :U (RE = Y, Gd, Nd, and Cotunnite 2 2 7 Lu) nanoparticles (NPs). The Y2Hf2O7 NPs exist in slightly disordered pyrochlore structure and the extent of disordering increases as a function of uranium doping while the structure reaches a cotunnite phase at 10.0% doping level. The Nd2Hf2O7 NPs also exist in a distorted pyrochlore structure and their distortion increases with increasing uranium doping inducing a phase transition into a disordered fluorite structure at 10.0% uranium doping.