Comparative Study on Precipitation Methods of Yellow
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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. -
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. -
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. -
Final Report
BNL-52661 Formal Report MECHANISMS OF RADIONUCLIDE-HYROXYCARBOXYLIC ACID INTERACTIONS FOR DECONTAMINATION OF METALLIC SURFACES A.J. FRANCIS, C.J. DODGE, AND J.B. GILLOW Brookhaven National Laboratory, Upton, NY 11973 G.P. HALADA AND C.R. CLAYTON Department of Materials Science, SUNY at Stony Brook, NY 11794 FINAL REPORT PROJECT PERIOD: 10/1/98 TO 9/30/01 PROJECT NUMBER: 64946 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United State Government nor any agency thereof, nor any of their employees, not any of their contractors, subcontractors, or 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, contractor, or subcontractor thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency, contractor or subcontractor thereof. MECHANISMS OF RADIONUCLIDE-HYROXYCARBOXYLIC ACID INTERACTIONS FOR DECONTAMINATION OF METALLIC SURFACES* A.J. FRANCIS, C.J. DODGE, AND J.B. GILLOW Brookhaven National Laboratory, Upton, NY 11973 G.P. HALADA AND C.R. CLAYTON Department of Materials Science, SUNY at Stony Brook, NY 11794 FINAL REPORT PROJECT PERIOD: 10/1/98 TO 9/30/01 PROJECT NUMBER: 64946 *This work was performed under the auspices of the U.S. -
Inis: Terminology Charts
IAEA-INIS-13A(Rev.0) XA0400071 INIS: TERMINOLOGY CHARTS agree INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUGUST 1970 INISs TERMINOLOGY CHARTS TABLE OF CONTENTS FOREWORD ... ......... *.* 1 PREFACE 2 INTRODUCTION ... .... *a ... oo 3 LIST OF SUBJECT FIELDS REPRESENTED BY THE CHARTS ........ 5 GENERAL DESCRIPTOR INDEX ................ 9*999.9o.ooo .... 7 FOREWORD This document is one in a series of publications known as the INIS Reference Series. It is to be used in conjunction with the indexing manual 1) and the thesaurus 2) for the preparation of INIS input by national and regional centrea. The thesaurus and terminology charts in their first edition (Rev.0) were produced as the result of an agreement between the International Atomic Energy Agency (IAEA) and the European Atomic Energy Community (Euratom). Except for minor changesq the terminology and the interrela- tionships btween rms are those of the December 1969 edition of the Euratom Thesaurus 3) In all matters of subject indexing and ontrol, the IAEA followed the recommendations of Euratom for these charts. Credit and responsibility for the present version of these charts must go to Euratom. Suggestions for improvement from all interested parties. particularly those that are contributing to or utilizing the INIS magnetic-tape services are welcomed. These should be addressed to: The Thesaurus Speoialist/INIS Section Division of Scientific and Tohnioal Information International Atomic Energy Agency P.O. Box 590 A-1011 Vienna, Austria International Atomic Energy Agency Division of Sientific and Technical Information INIS Section June 1970 1) IAEA-INIS-12 (INIS: Manual for Indexing) 2) IAEA-INIS-13 (INIS: Thesaurus) 3) EURATOM Thesaurusq, Euratom Nuclear Documentation System. -
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. -
Uranium, Cesium, and Mercury Leaching and Recovery from Cemented Radioactive Wastes in Sulfuric Acid and Iodide Media
Article Uranium, Cesium, and Mercury Leaching and Recovery from Cemented Radioactive Wastes in Sulfuric Acid and Iodide Media Nicolas Reynier 1,*, Rolando Lastra 1, Cheryl Laviolette 1, Jean-François Fiset 1, Nabil Bouzoubaâ 1 and Mark Chapman 2 Received: 28 September 2015 ; Accepted: 10 November 2015 ; Published: 20 November 2015 Academic Editor: Mostafa Fayek 1 CanmetMINING, Natural Resources Canada, 3484 Limebank Rd., Ottawa, ON K1A 0E4, Canada; [email protected] (R.L.); [email protected] (C.L.); jean-francois.fi[email protected] (J.-F.F.); [email protected] (N.B.) 2 Canadian Nuclear Laboratories, Chalk River Laboratories, Plant Road, Chalk River, ON K0J 1 J0, Canada; [email protected] * Correspondence: [email protected]; Tel.: +1-613-954-5602; Fax: +1-613-954-6929 Abstract: The Canadian Nuclear Laboratories (CNL) is developing a long-term management strategy for its existing inventory of solid radioactive cemented wastes, which contain uranium, mercury, fission products, and a number of minor elements. The composition of the cemented radioactive waste poses significant impediments to the extraction and recovery of uranium using conventional technology. The goal of this research was to develop an innovative method for uranium, mercury and cesium recovery from surrogate radioactive cemented waste (SRCW). Leaching using sulfuric acid and saline media significantly improves the solubilization of the key elements from the SRCW. Increasing the NaCl concentration from 0.5 to 4 M increases the mercury solubilization from 82% to 96%. The sodium chloride forms a soluble mercury complex when mercury is present as HgO or metallic mercury but not with HgS that is found in 60 ˝C cured SRCW. -
Uranium Co-Precipitation with Iron Oxide Minerals
This document was prepared in conjunction with work accomplished under Contract No. DE-AC09-96SR18500 with the U. S. Department of Energy. 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 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. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. This report has been reproduced directly from the best available copy. Available for sale to the public, in paper, from: U.S. Department of Commerce, National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161, phone: (800) 553-6847, fax: (703) 605-6900 email: [email protected] online ordering: http://www.ntis.gov/support/index.html Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of Energy, Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831-0062, phone: (865)576-8401, fax: (865)576-5728 email: [email protected] WSRC-MS-2002-00322 Uranium Co-precipitation with Iron Oxide Minerals MARTINE C. -
Modification of Base-Side 99Mo Production Processes for Leu Metal-Foil Targets
MODIFICATION OF BASE-SIDE 99MO PRODUCTION PROCESSES FOR LEU METAL-FOIL TARGETS G. F. Vandegrift, R. A. Leonard, S. Aase, J. Sedlet, Y. Koma, C. Conner, C. R. Clark, and M. K. Meyer Argonne National Laboratory Argonne, Illinois, and Idaho Falls, Idaho, U.S.A. ABSTRACT Argonne National Laboratory is cooperating with the National Atomic Energy Commission of the Argentine Republic (CNEA) to convert their 99Mo production process, which uses high enriched uranium (HEU), to low-enriched uranium (LEU). The program is multifaceted; however, discussed in this paper are (1) results of laboratory experiments to develop means for substituting LEU metal-foil targets into the current process and (2) preparation of uranium-alloy or uranium-metal/aluminum-dispersion targets. Although 99Mo production is a multi-step process, the first two steps (target dissolution and primary molybdenum recovery) are by far the most important in the conversion. Commonly, once molybdenum is separated from the bulk of the uranium, the remainder of the process need not be modified. Our results show that, up to this point in our study, conversion of the CNEA process to LEU appears viable. INTRODUCTION A number of current producers dissolve uranium-aluminide/aluminum-dispersion plates in alkaline solution as an initial step to recovering fission-product 99Mo from irradiated high- enriched uranium (HEU). These producers include Argentine Comisión Nacional de Energía Atómica (CNEA), Institut National des Radioéléments (IRE), Mallinckrodt, and the Atomic Energy Corporation of South Africa Limited (AEC). Argonne National Laboratory (ANL) has begun a cooperation with one of these producers, CNEA, to convert their process to low- enriched uranium (LEU). -
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. -
Precipitation Kinetics of a Continuous Precipitator, with Application to the Precipitation of Ammonium Polyuranate Richard Conrad Hoyt Iowa State University
Iowa State University Capstones, Theses and Retrospective Theses and Dissertations Dissertations 1978 Precipitation kinetics of a continuous precipitator, with application to the precipitation of ammonium polyuranate Richard Conrad Hoyt Iowa State University Follow this and additional works at: https://lib.dr.iastate.edu/rtd Part of the Nuclear Engineering Commons Recommended Citation Hoyt, Richard Conrad, "Precipitation kinetics of a continuous precipitator, with application to the precipitation of ammonium polyuranate" (1978). Retrospective Theses and Dissertations. 6459. https://lib.dr.iastate.edu/rtd/6459 This Dissertation is brought to you for free and open access by the Iowa State University Capstones, Theses and Dissertations at Iowa State University Digital Repository. It has been accepted for inclusion in Retrospective Theses and Dissertations by an authorized administrator of Iowa State University Digital Repository. For more information, please contact [email protected]. INFORMATION TO USERS This material was produced from a microfilm copy of the original document. While the most advanced technological means to photograph and reproduce this document have been used, the quality is heavily dependent upon the quality of the original submitted. The following explanation of techniques is provided to help you understand markings or patterns which may appear on this reproduction. 1.The sign or "target" for pages apparently lacking from the document photographed is "Missing Page(s)". if it was possible to obtain the missing page(s) or section, they are spliced into the film along with adjacent pages. This may have necessitated cutting thru an image and duplicating adjacent pages to insure you complete continuity. 2. When an image on the film is obliterated with a large round black mark, it is an indication that the photographer suspected that the copy may have moved during exposure and thus cause a blurred image.