Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors
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Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel
University of Tennessee, Knoxville TRACE: Tennessee Research and Creative Exchange Masters Theses Graduate School 5-2004 Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel Jennifer L. Ladd-Lively University of Tennessee - Knoxville Follow this and additional works at: https://trace.tennessee.edu/utk_gradthes Part of the Chemical Engineering Commons Recommended Citation Ladd-Lively, Jennifer L., "Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel. " Master's Thesis, University of Tennessee, 2004. https://trace.tennessee.edu/utk_gradthes/2557 This Thesis is brought to you for free and open access by the Graduate School at TRACE: Tennessee Research and Creative Exchange. It has been accepted for inclusion in Masters Theses by an authorized administrator of TRACE: Tennessee Research and Creative Exchange. For more information, please contact [email protected]. To the Graduate Council: I am submitting herewith a thesis written by Jennifer L. Ladd-Lively entitled "Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel." I have examined the final electronic copy of this thesis for form and content and recommend that it be accepted in partial fulfillment of the equirr ements for the degree of Master of Science, with a major in Chemical Engineering. Robert M. Counce, Major Professor We have read this thesis and recommend its acceptance: Barry B. Spencer, Paul Bienkowski, Fred Weber Accepted for the Council: Carolyn R. Hodges Vice Provost and Dean of the Graduate School (Original signatures are on file with official studentecor r ds.) To the Graduate Council: I am submitting herewith a thesis written by Jennifer L. -
Oct. 14, 1958 J. M. CARTER ET AL 2,856,263 PROCESS for the RECOVERY and PURIFICATION of URANIUM DEPOSITS Original Filed April 21, 1944 ‘7 Sheets-Sheet 1
Oct. 14, 1958 J. M. CARTER ET AL 2,856,263 PROCESS FOR THE RECOVERY AND PURIFICATION OF URANIUM DEPOSITS Original Filed April 21, 1944 ‘7 Sheets-Sheet 1 IN VEN TORS James M Car/‘er Mar?n D. ?ame/7 BY ATTORNEY Oct. 14, 1958 J. M. CARTER ET AL 2,856,263 PROCESS FOR THE RECOVERY AND PURIFICATION OF URANIUM DEPOSITS Original Filed April 21, 1944 7 Sheets-Sheet 55 QQOUMM,vRMmG w.9386mmE IN VEN TORS James M. Car fer By Marfin 0 Home/7 W4 W ATTORNEY Oct. 14,1958 J. M. CARTER ET AL 2,856,263 PROCESS FOR THE RECOVERY AND PURIFICATION _ OF URANIUM DEPOSITS Origlnal Filed April 21, 1944 7 Sheets-Sheet 4 SCRUBBYING. AND WASHING PARTS OF CALUTRON ' WITH HOT WATER Lf- WASH WATER :FCONDENSATE ' \WATERANDMAKE UP snevmc SOL/D IMPUR/ TIES — WASH WA TER -—p>- CONDENSING To DISCARD I OXIDIZING ORSALVAGE SOLUTION U02” Cu?! Few’! Cr!!! Ni“ FILTERING‘ - '3 PREC/P/TATE 0* |——‘———/ F/LTRA TE _ U024!- TO DISCARD __ EVAPORATING gel”,++ OR SALVAGE PRECIPITATING Z/VH OH AND F'LTER'NG gFlLTRA TE TO FURTHER T REATMENT Fig. 4 I INVENTORS ‘James M Cor fer, BY Mar/7'0 D. Kama/7 ' @ M A TTORNEY Oct. 14,1958 J. M. CARTER ET AL . 2,356,263 PROCESS FOR THE RECOVERY AND PURIFICATION 0F URANIUM DEPOSITS Original Filed April 21, 1944 7 Sheets-Sheet s DISSOLVING URANIUM METAL DEPOSITED ON COPPER COLLECTOR IN COLD HNo3 (8N) CONDENSATE I AND MAKE UP SOLUTION HNO3 U02" ' Cu ** 7—>— CONDENSING ' HN03 . EVAPORATI NG CONCENTRA TED \ soburj'o/v _ F/LTRA TE C35 cu {NHJLF H PRECIPITATING ‘ -[—-~’—NH4OH A ND F ILTERING ' f/RECIP/ TA TES *Cu/‘OHZH4 :0 01 ORTO SALVAGEDISCARD *Trace T__>_ DISSOLVING HN 0 3 ' - SOLUTION U02 +4 *cuvf *Tme F/LTRA TE PRECIPITATING _l—_'_NH OH AND FILTERING 4 { PREClP/TATE NH U 0 TO DISCARD ( ‘)2 2 ’ OR SALVAGE , r---‘“—? TO FURTHER TREATMENT 5 I N V EN TORS' James M Car/‘er ' Mar/"in D. -
(VI) and Chromium (V) Oxide Fluorides
Portland State University PDXScholar Dissertations and Theses Dissertations and Theses 1976 The chemistry of chromium (VI) and chromium (V) oxide fluorides Patrick Jay Green Portland State University Follow this and additional works at: https://pdxscholar.library.pdx.edu/open_access_etds Part of the Chemistry Commons Let us know how access to this document benefits ou.y Recommended Citation Green, Patrick Jay, "The chemistry of chromium (VI) and chromium (V) oxide fluorides" (1976). Dissertations and Theses. Paper 4039. https://doi.org/10.15760/etd.5923 This Thesis is brought to you for free and open access. It has been accepted for inclusion in Dissertations and Theses by an authorized administrator of PDXScholar. Please contact us if we can make this document more accessible: [email protected]. All ABSTRACT OF THE TllESIS OF Patrick Jay Green for the Master of Science in Chemistry presented April 16, 1976. Title: Chemistry of Chromium(VI) and Chromium(V) Oxide Fluorides. APPROVEO BY MEMBERS OF THE THESIS CO'"o\l TIEE: y . • Ii . ' I : • • • • • New preparative routes to chromyl fluoride were sought. It was found that chlorine ironofluoride reacts with chromium trioxide and chromyl chlo ride to produce chromyl fluoride. Attempts were ~ade to define a mechan ism for the reaction of ClF and Cr0 in light of by-products observed 3 and previous investigations. Carbonyl fluoride and chromium trioxide react to fom chro·yl fluoride and carbo:i dioxide. A mechanism was also proposed for this react10n. Chromium trioxide 11itl\ l~F6 or WF5 reacts to produce chromyl fluoride and the respective oxide tetrafluoride. 2 Sulfur hexafluoride did not react with Cr03. -
ORGANOMETAT,T,TC CHEMISTRY of URANIUM a Thesis Submitted By
ORGANOMETAT,T,TC CHEMISTRY OF URANIUM A thesis submitted by R1TN R. SIGURDSON, B.Sc. for the DEGREE of DOCTOR of PHILOSOPHY of the UNIVERSITY of LONDON Royal College of Science Imperial College of Science and Technology London, SW7 ?AY August 1976 TO MY PARENTS 3 ACKNOWLEDGEMENTS I would like to express my gratitude to Professor Geoffrey Wilkinson, F.R.S. for his guidance and enthusiastic support throughout the course of this work. Many thanks are also extended to Drs. Dick Andersen, Ernesto Carmona-Guzman and David Cole-Hamilton for their suggestionS, encouragement and advice, and to Dr. Kostas Mertis for his patient help during the first months. I am indebted to the Canadian Research Council of Canada for financial support during the past three years. 4 CONTENTS ABSTRACT 6 INTRODUCTION I. The Chemistry of Uranium(IV) 8 .II. The Chemistry of Uranium(V) 15 III. The Chemistry of Uranium(VI) 16 CHAPTER I. DILITHIUMHEXAALKYLURANATE(IV) COMPLEXES I. Introduction 19 II. Results and Discussion 27 III. Experimental 35 CHAPTER II. TRILITHIUMOCTAALKYLURANATE(V) COMPLEXES I. Introduction 54 II. Results and Discussion 55 III. Experimental 60 CHAPTER III. ADDITION COMPOUNDS OF URANIUM(VI) HEXAISO-PROPDXIDE WITH LITHIUM, MAGNESIUM AND ALUMINIUM ALKYLS I. Introduction 70 II. Results and Discussion 71 III. Experimental 77 CHAPTER IV. ORGANOMETALLIC CHEMISTRY OF ADAMANTANE I. Introduction 84 II. Results and Discussion 85 III. Experimental 87 REFERENCES 92 5 ABBREVIATIONS Me - methyl Et - ethyl Prn- normal-propyl Pri- iso-propyl Bun- normal-butyl But- iso-butyl But- tertiary-butyl Ph - phenyl CP cyclopentadienyl DME - dimethoxyethane tmed - N,N,NI,N'-tetramethylethylenediamine pmdt - N,N,Nt,N",N"-pentamethyldiethylenetriamine g.l.c. -
Sources, Effects and Risks of Ionizing Radiation
SOURCES, EFFECTS AND RISKS OF IONIZING RADIATION United Nations Scientific Committee on the Effects of Atomic Radiation UNSCEAR 2016 Report to the General Assembly, with Scientific Annexes UNITED NATIONS New York, 2017 NOTE The report of the Committee without its annexes appears as Official Records of the General Assembly, Seventy-first Session, Supplement No. 46 and corrigendum (A/71/46 and Corr.1). The report reproduced here includes the corrections of the corrigendum. The designations employed and the presentation of material in this publication do not imply the expression of any opinion whatsoever on the part of the Secretariat of the United Nations concerning the legal status of any country, territory, city or area, or of its authorities, or concerning the delimitation of its frontiers or boundaries. The country names used in this document are, in most cases, those that were in use at the time the data were collected or the text prepared. In other cases, however, the names have been updated, where this was possible and appropriate, to reflect political changes. UNITED NATIONS PUBLICATION Sales No. E.17.IX.1 ISBN: 978-92-1-142316-7 eISBN: 978-92-1-060002-6 © United Nations, January 2017. All rights reserved, worldwide. This publication has not been formally edited. Information on uniform resource locators and links to Internet sites contained in the present publication are provided for the convenience of the reader and are correct at the time of issue. The United Nations takes no responsibility for the continued accuracy of that information or for the content of any external website. -
Molten-Salt Technology and Fission Product Handling
Molten-Salt Technology and Fission Product Handling Kirk Sorensen Flibe Energy, Inc. ORNL MSR Workshop October 4, 2018 2018-10-16 Hello, my name is Kirk Sorensen and I’d like to talk with you today about fission products and their handling in molten-salt reactors. One of the things that initially attracted me to molten-salt reactor technology was the array of options that it gave for the intelligent handling of fission products. It represented such a contrast to solid-fueled systems, which mixed fission products in with unburned nuclear fuel in a form that was difficult to separate, one from another. While my focus will be on our work on molten-salt reactor fission product handling, many of the principles are general to molten-salt reactors as a whole. Fundamental Nuclear Reactor Concept In its simplest form, a nuclear reactor generates thermal energy that is carried away by a coolant. That coolant heats the working fluid of a power conversion system, which generates electricity from part of the thermal energy and rejects the remainder to the environment. coolant working fluid fresh fuel electricity Power Nuclear Heat Conversion Reactor Exchanger System spent fuel heated water or air coolant working fluid The primary coolant chosen for a nuclear reactor determines, in large part, its size and manufacturability. The temperature of the coolant determines the efficiency of electrical generation. Fundamental Nuclear Reactor Concept In its simplest form, a nuclear reactor generates thermal energy that is carried away by a coolant. That coolant heats the working fluid of a power conversion system, which generates electricity from part of the thermal energy and rejects the remainder to the environment. -
A Comparison of Advanced Nuclear Technologies
A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D MARCH 2017 B | CHAPTER NAME ABOUT THE CENTER ON GLOBAL ENERGY POLICY The Center on Global Energy Policy provides independent, balanced, data-driven analysis to help policymakers navigate the complex world of energy. We approach energy as an economic, security, and environmental concern. And we draw on the resources of a world-class institution, faculty with real-world experience, and a location in the world’s finance and media capital. Visit us at energypolicy.columbia.edu facebook.com/ColumbiaUEnergy twitter.com/ColumbiaUEnergy ABOUT THE SCHOOL OF INTERNATIONAL AND PUBLIC AFFAIRS SIPA’s mission is to empower people to serve the global public interest. Our goal is to foster economic growth, sustainable development, social progress, and democratic governance by educating public policy professionals, producing policy-related research, and conveying the results to the world. Based in New York City, with a student body that is 50 percent international and educational partners in cities around the world, SIPA is the most global of public policy schools. For more information, please visit www.sipa.columbia.edu A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D* MARCH 2017 *Andrew C. Kadak is the former president of Yankee Atomic Electric Company and professor of the practice at the Massachusetts Institute of Technology. He continues to consult on nuclear operations, advanced nuclear power plants, and policy and regulatory matters in the United States. He also serves on senior nuclear safety oversight boards in China. He is a graduate of MIT from the Nuclear Science and Engineering Department. -
Preparation of Anhydrous Uranium Tetrachloride and Measurements on Its Magnetic Susceptibility
Journal of NUCLEAR SCIENCE and TECHNOLOGY, 8 〔9〕, p. 498~502 (September 1971). Preparation of Anhydrous Uranium Tetrachloride and Measurements on Its Magnetic Susceptibility Tetsuhiko YOSHIMURA*, Chie MIYAKE* and Shosuke IMOTO* Received May 24, 1971 The reaction of UO2 with CCl4 vapor was carried out in a vacuum of 10-5 mmHg at 500℃ in order to prepare UCl4 of high purity. The lattice parameters were calculated from X-ray analysis to be a0=8.278±0.002, c0=7.460±0.009. The product thus ohtained was verified by chemical and X-ray analyses to be of anhydride form. The magnetic susceptibility was measured over the temperature range from liquid N2 to liquid He temperature, which revealed a deviation from the straight 1/X-T relation toward lower temperature. and that the anhydrous compound had ortho- I. INTRODUCTION rhombic symmetry. Since the same morpho- In the U-Cl system, there are known to logy may also exist for the chloride also, the exist four compounds, UCl3, UCl4, UCl5 and UCl4 is required to be of high purity. UCl6. Their chemical, physical and thermo- Table 1 Physical properties of UCl4 dynamic properties have been extensively investigated(1)(2) as well as those of the fluo- rides. Among these compounds UCl4 is used as the starting material for the synthesis of various uranous complexes, for its high solubility in many organic polar solvents such as methanol, ethanol, acetone, as reported by Selbin et al. (3)~(5) and Bagnall et al. (6) This com- pound is also used as the starting material for the preparation of UC(7), UN, US2(1)(8),USe2(1) etc. -
Properties of Selected Radioisotopes
CASE FILE COPY NASA SP-7031 Properties of Selected Radioisotopes A Bibliography PART I: UNCLASSIFIED LITERATURE NATIONAL AERONAUTICS AND SPACE ADMINISTRATION NASA SP-7031 PROPERTIES OF SELECTED RADIOISOTOPES A Bibliography Part I: Unclassified Literature A selection of annotated references to technical papers, journal articles, and books This bibliography was compiled and edited by DALE HARRIS and JOSEPH EPSTEIN Goddard Space Flight Center Greenbelt, Maryland Scientific and Technical Information Division / OFFICE OF TECHNOLOGY UTILIZATION 1968 USP. NATIONAL AERONAUTICS AND SPACE ADMINISTRATION Washington, D.C. PREFACE The increasing interest in the application of substantial quantities of radioisotopes for propulsion, energy conversion, and various other thermal concepts emphasizes a need for the most recent and most accurate information available describing the nuclear, chemical, and physical properties of these isotopes. A substantial amount of progress has been achieved in recent years in refining old and developing new techniques of measurement of the properties quoted, and isotope processing. This has resulted in a broad technological base from which both the material and information about the material is available. Un- fortunately, it has also resulted in a multiplicity of sources so that information and data are either untimely or present properties without adequately identifying the measurement techniques or describing the quality of material used. The purpose of this document is to make available, in a single reference, an annotated bibliography and sets of properties for nine of the more attractive isotopes available for use in power production. Part I contains all the unclassified information that was available in the literature surveyed. Part II is the classified counterpart to Part I. -
0409-TOFE-Elguebaly
BBenenefitsefits ooff RRadadialial BBuuildild MinMinimimizatioizationn anandd RReqequuirirememenentsts ImImposedposed onon AARRIEIESS CComompapacctt SStetellallararatotorr DDeesigsignn Laila El-Guebaly (UW), R. Raffray (UCSD), S. Malang (Germany), J. Lyon (ORNL), L.P. Ku (PPPL) and the ARIES Team 16th TOFE Meeting September 14 - 16, 2004 Madison, WI Objectives • Define radial builds for proposed blanket concepts. • Propose innovative shielding approach that minimizes radial standoff. • Assess implications of new approach on: – Radial build – Tritium breeding – Machine size – Complexity – Safety – Economics. 2 Background • Minimum radial standoff controls COE, unique feature for stellarators. • Compact radial build means smaller R and lower Bmax fi smaller machine and lower cost. • All components provide shielding function: – Blanket protects shield Magnet Shield FW / Blanket – Blanket & shield protect VV Vessel Vacuum – Blanket, shield & VV protect magnets Permanent Components • Blanket offers less shielding performance than shield. • Could design tolerate shield-only at Dmin (no blanket)? • What would be the impact on T breeding, overall size, and economics? 3 New Approach for Blanket & Shield Arrangement Magnet Shield/VV Shield/VV Blanket Plasma Blanket Plasma 3 FP Configuration WC-Shield Dmin Magnet Xn through nominal Xn at Dmin blanket & shield (magnet moves closer to plasma) 4 Shield-only Zone Covers ~8% of FW Area 3 FP Configuration Beginning of Field Period f = 0 f = 60 Middle of Field Period 5 Breeding Blanket Concepts Breeder Multiplier Structure FW/Blanket Shield VV Coolant Coolant Coolant ARIES-CS: Internal VV: Flibe Be FS Flibe Flibe H2O LiPb – SiC LiPb LiPb H2O * LiPb – FS He/LiPb He H2O Li4SiO4 Be FS He He H2O External VV: * LiPb – FS He/LiPb He or H2O He Li – FS He/Li He He SPPS: External VV: Li – V Li Li He _________________________ * With or without SiC inserts. -
Medical Isotope Production in Liquid-Fluoride Reactors
Medical Isotope Production in Liquid-Fluoride Reactors Kirk Sorensen Flibe Energy Huntsville, Alabama kirk.sorensen@flibe-energy.com 256 679 9985 Flibe Energy was formed in order to develop liquid-fluoride reactor technology and to supply the world with affordable and sustainable energy, water and fuel. Liquid-Fluoride Reactor Concept Reactor Containment Boundary Turbine Coolant LiF-BeF2-UF4 LiF-BeF2 outlet Primary HX Gas Heater Gas Cooler Generator Reactor core Compressor Coolant inlet Drain Freeze valve Tank Electrical Warm Recompressor Main Compressor Turbine Generator Saturated Air Cool Dry Air Gas Heater High-Temp Low-Temp Gas Cooler Recuperator Recuperator Cooling Water Accum Surge Short-Term Gas Holdup Cryogenic Long-Term Gas Holdup Storage Accum Surge ea Fluor Decay Scrub Decay Tank KOH Bi(Th) Bi(Pa,U) Isotopic Quench metallic Th feed H2 ulFluorinator Fuel 2Reduction H2 HF Electro Bi(Th,FP) Bi(Li) Cell metallic HDLi feed F2 Water Water Coolant Coolant Torus Torus Drain Tank Waste Tank 7 Fuel Salt ( LiF-BeF2-UF4) Fresh Offgas UF6-F2 200-bar CO2 7 Blanket Salt ( LiF-ThF4-BeF2) 1-day Offgas F2 77-bar CO2 7 Coolant salt ( LiF-BeF2) 3-day Offgas HF-H2 Water 7 Decay Salt ( LiF-BeF2-(Th,Pa)F4) 90-day Offgas H2 Waste Salt (LiF-CaF2-(FP)F3) Helium Bismuth The Molten-Salt Reactor Experiment was an experimental reactor system that demonstrated key technologies. Lanthanide Fission Products Alkali- and Alkaline-Earth Fission Product Fluorides c ORNL-TM-3884 THE MIGRATION OF A CLASS OF FISSION PRODUCTS (NOBLE METALS) IN THE MOLTEN-SALT REACTOR EXPERIMENT R. -
WO 2016/074683 Al 19 May 2016 (19.05.2016) W P O P C T
(12) INTERNATIONAL APPLICATION PUBLISHED UNDER THE PATENT COOPERATION TREATY (PCT) (19) World Intellectual Property Organization International Bureau (10) International Publication Number (43) International Publication Date WO 2016/074683 Al 19 May 2016 (19.05.2016) W P O P C T (51) International Patent Classification: (81) Designated States (unless otherwise indicated, for every C12N 15/10 (2006.01) kind of national protection available): AE, AG, AL, AM, AO, AT, AU, AZ, BA, BB, BG, BH, BN, BR, BW, BY, (21) International Application Number: BZ, CA, CH, CL, CN, CO, CR, CU, CZ, DE, DK, DM, PCT/DK20 15/050343 DO, DZ, EC, EE, EG, ES, FI, GB, GD, GE, GH, GM, GT, (22) International Filing Date: HN, HR, HU, ID, IL, IN, IR, IS, JP, KE, KG, KN, KP, KR, 11 November 2015 ( 11. 1 1.2015) KZ, LA, LC, LK, LR, LS, LU, LY, MA, MD, ME, MG, MK, MN, MW, MX, MY, MZ, NA, NG, NI, NO, NZ, OM, (25) Filing Language: English PA, PE, PG, PH, PL, PT, QA, RO, RS, RU, RW, SA, SC, (26) Publication Language: English SD, SE, SG, SK, SL, SM, ST, SV, SY, TH, TJ, TM, TN, TR, TT, TZ, UA, UG, US, UZ, VC, VN, ZA, ZM, ZW. (30) Priority Data: PA 2014 00655 11 November 2014 ( 11. 1 1.2014) DK (84) Designated States (unless otherwise indicated, for every 62/077,933 11 November 2014 ( 11. 11.2014) US kind of regional protection available): ARIPO (BW, GH, 62/202,3 18 7 August 2015 (07.08.2015) US GM, KE, LR, LS, MW, MZ, NA, RW, SD, SL, ST, SZ, TZ, UG, ZM, ZW), Eurasian (AM, AZ, BY, KG, KZ, RU, (71) Applicant: LUNDORF PEDERSEN MATERIALS APS TJ, TM), European (AL, AT, BE, BG, CH, CY, CZ, DE, [DK/DK]; Nordvej 16 B, Himmelev, DK-4000 Roskilde DK, EE, ES, FI, FR, GB, GR, HR, HU, IE, IS, IT, LT, LU, (DK).