Octanol As Diluent in a Grouped Actinide Extraction Process

Total Page:16

File Type:pdf, Size:1020Kb

Octanol As Diluent in a Grouped Actinide Extraction Process Octanol as Diluent in a Grouped ActiNide EXtraction Process Mu Lin Department of Chemistry and Chemical Engineering CHALMERS UNIVERSITY OF TECHNOLOGY Gothenburg, Sweden 2016 I Octanol as Diluent in a Grouped ActiNide EXtraction Process Mu Lin © Mu Lin, 2016 Examiner: Christian Ekberg Supervisor: Jenny Halleröd Department of Chemistry and Chemical Engineering Chalmers University of Technology SE-412 96 Gothenburg Sweden Telephone: +46 (0)31-7721000 Chalmers Reproservice Gothenburg, Sweden 2016 II Octanol as Diluent in a Grouped ActiNide EXtraction Process MU LIN Nuclear Chemistry & Industrial Materials Recycling Department of Chemistry and Chemical Engineering Chalmers University of Technology Abstract Since the beginning of the development of nuclear power plants nuclear energy has played a significant role in the worldwide electricity supply. More than 20% of the total electricity in the world comes from nuclear power plants. Nuclear energy has both advantages and disadvantages. On one hand, it contributes to clean energy in terms of low greenhouse gas emissions, and on the other hand, it causes problems with radioactive waste. By the end of May 2016, 444 nuclear reactors were in operation for the worldwide electricity generation. 63 new reactors are under construction, meaning that a large amount of nuclear waste has to be handled every year. Used nuclear fuel is highly radiotoxic when it is discharged from the reactor and has to be stored for at least 100,000 years for the radiotoxicity to reach the same level as the natural uranium needed to produce one tonne of enriched fuel. The storage time could, however, be reduced to around 1,000 years if the long-lived actinides are separated from the rest of the used nuclear fuel and transmuted into the short-lived or even stable isotopes. One of the separation methods are liquid-liquid extraction, where several different processes have been developed during the years. One of them is the GANEX (Grouped ActiNide EXtraction) process, which is still under development with the purpose of extracting all the actinides together as a group from the lanthanides and the other fission products. In order to reach a promising separation, different diluents and extraction agents are under investigation. In this work, the Chalmers GANEX process has been investigated using 6,6´-bis(5,5,8,8-tetramethyl- 5,6,7,8-tetrahydro-benzo[1,2,4]triazin-3-yl)[2,2´]bipyridine (CyMe4-BTBP) and tri-butyl phosphate (TBP) as extraction agents and 1-octanol as diluent. This system has also been compared with another system using FS13 (Phenyl Trifluoromethyl Sulfone) as diluent. Extraction of both active and inactive metal ions has been investigated. The experiments shows that both systems have a high actinide extraction and low extraction of the majority of both the lanthanides and the other fission products. In comparison with the FS13 based GANEX system the 1-octanol based GANEX system has a slightly higher extraction of both americium and curium but a lower extraction of both uranium and plutonium. The time to reach extraction equilibrium is slower for all actinides in the 1-octanol based GANEX system compared to the FS13 based GANEX system. Investigations with different volumes of TBP in the 1- octanol based GANEX system shows that the extraction of plutonium and europium increases with an increasing TBP concentration while the there is no big difference in the europium extraction. Keywords: Solvent Extraction, GANEX, 1-octanol, CyMe4-BTBP and TBP. III Contents 1. Introduction and Background ............................................................................................................ 1 1.1 Nuclear Waste ............................................................................................................................... 1 1.2 Once through ................................................................................................................................. 2 1.3 Reprocessing.................................................................................................................................. 2 1.4 Recycling ........................................................................................................................................ 3 1.5 Chalmers GANEX ........................................................................................................................... 3 1.5.1 Extractants .............................................................................................................................. 3 1.5.2 Diluents ................................................................................................................................... 4 2. Theory ................................................................................................................................................. 6 2.1 Liquid-Liquid Extraction ................................................................................................................. 6 2.1.1 Distribution Ratio and Separation Factor ............................................................................... 6 2.1.2 Kinetics and Equilibrium ......................................................................................................... 6 2.1.3 Stripping ................................................................................................................................. 7 2.2 Lanthanides, Actinides and Fission Products ................................................................................ 7 3. Experimental ....................................................................................................................................... 9 3.1 Solvent Extraction Experiments .................................................................................................... 9 3.2 Analysis .......................................................................................................................................... 9 3.2.1 Gamma Spectrometry ............................................................................................................ 9 3.2.2 Liquid Scintillation Counting ................................................................................................. 10 3.2.3 Inductively Coupled Plasma Mass Spectrometry ................................................................. 10 4. Results and Discussions .................................................................................................................... 11 4.1 Equilibrium Kinetics ..................................................................................................................... 11 4.1.1 Extraction of actinides and europium .................................................................................. 11 4.1.2 Extraction of fission products ............................................................................................... 13 4.2 Separate Ligand Extraction .......................................................................................................... 19 4.3 Varying TBP volume in the octanol based GANEX system .......................................................... 21 4.4 Stripping ...................................................................................................................................... 22 5. Summary and Conclusions ............................................................................................................... 25 6. Future work ....................................................................................................................................... 26 7. Acknowledgements .......................................................................................................................... 27 Bibliography .......................................................................................................................................... 28 Appendix 1 ............................................................................................................................................ 31 IV LIST OF ABBREVIATIONS ADS Accelerator Driven System BTBP Bis-triazine bi-pyridine CHON Carbon, Hydrogen, Oxygen and Nitrogen CyMe4-BTBP 6,6´-bis(5,5,8,8-tetramethyl-5,6,7,8-tetrahydro-benzo[1,2,4]triazin-3- yl)[2,2´]bipyridine D Distribution ratio DEHBA N,N-di-2(ethylhexyl)-butyramide DIAMEX DIAMide Extraction DMDOHEMA N,N’-(dimethyl)-N,N’-dioctyl-hexylethoxy-malonamide FP Fission Products FS13 Phenyl trifluoromethyl sulfone GANEX Grouped ActiNide Extraction HDEHP di(2-ethylhexyl)phosphoric acid HPGe High Purity Germanium HSAB Hard Soft Acid Base IAEA International Atomic Energy Agency ICP-MS Inductively Coupled Plasma Mass Spectrometry ICRP International Commission on Radiological Protection LSC Liquid Scintillation Counting MOX-fuel Mixed Oxide Fuel NEA Nuclear Energy Agency NEI Nuclear Energy Institute OECD Organization for Economic Co-operation and Development PUREX Plutonium Uranium Reduction EXtraction P&T Partitioning and Transmutation SANEX Selective ActiNide Extraction SF Separation Factor TBP Tri-Butyl Phosphate tHM Tonne of Heavy Metals TODGA N,N,N’,N’-tetraoctyl diglycolamide V 1. Introduction and Background The worldwide electrical energy demand is high and is increasing every day due to an increasing population [1]. Electrical energy has played an important role for both developed and developing countries [2]. Developing countries need a big amount of energy to keep developing and developed countries needs energy to maintain the
Recommended publications
  • Development of a Solvent Extraction Process for Group Actinide Recovery from Used Nuclear Fuel
    THESIS FOR THE DEGREE OF DOCTOR OF PHILOSOPHY Development of a Solvent Extraction Process for Group Actinide Recovery from Used Nuclear Fuel EMMA H. K. ANEHEIM Department of Chemical and Biological Engineering CHALMERS UNIVERSITY OF TECHNOLOGY Gothenburg, Sweden, 2012 Development of a Solvent Extraction Process for Group Actinide Recovery from Used Nuclear Fuel EMMA H. K. ANEHEIM ISBN 978-91-7385-751-2 © EMMA H. K. ANEHEIM, 2012. Doktorsavhandlingar vid Chalmers tekniska högskola Ny serie Nr 3432 ISSN 0346-718X Department of Chemical and Biological Engineering Chalmers University of Technology SE-412 96 Gothenburg Sweden Telephone + 46 (0)31-772 1000 Cover: Radiotoxicity as a function of time for the once through fuel cycle (left) compared to one P&T cycle using the GANEX process (right) (efficiencies: partitioning from Table 5.5.4, transmutation: 99.9%). Calculations performed using RadTox [HOL12]. Chalmers Reproservice Gothenburg, Sweden 2012 Development of a Solvent Extraction Process for Group Actinide Recovery from Used Nuclear Fuel EMMA H. K. ANEHEIM Department of Chemical and Biological Engineering Chalmers University of Technology Abstract When uranium is used as fuel in nuclear reactors it both undergoes neutron induced fission as well as neutron capture. Through successive neutron capture and beta decay transuranic elements such as neptunium, plutonium, americium and curium are produced in substantial amounts. These radioactive elements are mostly long-lived and contribute to a large portion of the long term radiotoxicity of the used nuclear fuel. This radiotoxicity is what makes it necessary to isolate the used fuel for more than 100,000 years in a final repository in order to avoid harm to the biosphere.
    [Show full text]
  • The Actinide Research Quarterly Is Published Quarterly to Highlight Recent Achievements and Ongoing Programs of the Nuclear Materials Technology Division
    1st quarter 2000 TheLos Actinide Alamos National Research Laboratory N u c l e a r M aQuarterly t e r i a l s R e s e a r c h a n d T e c h n o l o g y a U.S. Department of Energy Laboratory Organizers Issue an Invitation to In This Issue Plutonium Futures 1 —The Science Organizers Issue an Invitation to Plutonium Futures —The Science The second of a series of international con- have an exciting collection of some 180 invited ferences on plutonium will be held in Santa Fe, and contributed papers with topics ranging 2 NM, this summer, July 10–13. It follows the very broadly in materials science, transuranic 238Pu Aqueous highly successful 1997 conference, “Plutonium waste forms, nuclear fuels and isotopes, separa- Processing Line Will Futures - The Science,” which attracted over 300 tions, actinides in the environment, detection Provide New NMT participants representing 14 countries. The U.S. and analysis, actinide compounds and com- Capability participants, who made up about 70 percent of plexes, and condensed matter physics of ac- the total participants, came from Department of tinides. These papers, presented in separate 4 Energy national laboratories and a score of uni- oral and poster sessions, will give attendees a Editorial: versities and industries. As in 1997, the confer- chance to learn about current research outside Transactinium ence is sponsored by the Los Alamos National of their particular specialties and provide an Science Needs Laboratory in cooperation with the American opportunity for interdisciplinary discussions Educational Nuclear Society.
    [Show full text]
  • Chapter 2 Proposed Action and Alternatives
    Final Environmental Assessment for Actinide Chemistry and Repository Science Laboratory CHAPTER 2 PROPOSED ACTION AND ALTERNATIVES The WIPP facility, in addition to serving its primary mission as a TRU waste disposal site, needs to perform a variety of actinide chemistry experiments to (1) support WIPP’s recertification efforts, (2) address scientific questions important to WIPP, (3) improve TRU waste characterization techniques, and (4) improve DOE’s understanding of how the waste interacts with the natural environment in order to better understand waste isolation performance. In the past, WIPP-related actinide chemistry experiments have taken place at DOE laboratory facilities at other DOE sites such as LANL. However, due to reductions in travel budgets and additional security requirements being imposed on DOE weapons laboratories, DOE believes it would be better able to maintain the budget, schedule, and quality of experiments conducted in support of the WIPP program if they were performed in Carlsbad. DOE is preparing this document to inform decision makers about the potential environmental impacts of the actinide chemistry experiments associated with the Proposed Action, one alternative laboratory location, and a no action alternative, each of which are described in more detail in this chapter. Under the Proposed Action, DOE would construct and operate the ACRSL facility adjacent to the CEMRC in Carlsbad. An alternative is to construct and operate a new actinide chemistry laboratory on the WIPP site. The No Action Alternative is to continue experimental activities in actinide chemistry at existing laboratory facilities at LANL. The descriptions of the design, construction, and operation of the proposed ACRSL facility were obtained from the proposal submitted by the CEMRC (2000).
    [Show full text]
  • Detection of Missing Low-Lying Atomic States in Actinium
    Detection of missing low-lying atomic states in actinium Ke Zhang,1, 2, ∗ Dominik Studer,2 Felix Weber,2 Vadim M. Gadelshin,2, 3 Nina Kneip,2 Sebastian Raeder,1, 2 Dmitry Budker,1, 2, 4 Klaus Wendt,2 Tom Kieck,2, 1 Sergey G. Porsev,5, 6 Charles Cheung,5 Marianna S. Safronova,5, 7 and Mikhail G. Kozlov6, 8 1Helmholtz Institute Mainz, GSI Helmholtzzentrum f¨urSchwerionenforschung, 55099 Mainz, Germany 2Johannes Gutenberg-University Mainz, 55099 Mainz, Germany 3Institute of Physics and Technology, Ural Federal University, 620002 Yekaterinburg, Russia 4Department of Physics, University of California at Berkeley, California 94720-300, USA 5Department of Physics and Astronomy, University of Delaware, DE, 19716, USA 6Petersburg Nuclear Physics Institute of NRC \Kurchatov Institute", Gatchina 188300, Russia 7Joint Quantum Institute, NIST and the University of Maryland, College Park, MD, 20742, USA 8Petersburg Electrotechnical University \LETI", Prof. Popov Str. 5, 197376 St. Petersburg, Russia 2 2 o 2 2 o Two lowest-energy odd-parity atomic levels of actinium, 7s 7p P1=2, 7s 7p P3=2, were observed via two-step resonant laser-ionization spectroscopy and their respective energies were measured to be 7477:36(4) cm−1 and 12 276:59(2) cm−1. The lifetimes of these states were determined as 668(11) ns and 255(7) ns, respectively. In addition, these properties were calculated using a hybrid approach that combines configuration interaction and coupled-cluster methods in good agreement. The data are of relevance for understanding the complex atomic spectra of actinides and for developing efficient laser-cooling and ionization schemes for actinium, with possible applications for high-purity medical- isotope production and future fundamental physics experiments with this atom.
    [Show full text]
  • BERRIES Issue: 1 SAC Date: Nov 2020 Page: 1 of 22
    Doc No: DLS-SACDISCo-BERRIES Issue: 1 SAC Date: Nov 2020 Page: 1 of 22 BERRIES (Bright Environment for x-ray Raman, Resonance Inelastic and Emission Spectroscopies) Prepared for Diamond SAC/DISCo November 2020 1 Doc No: DLS-SACDISCo-BERRIES Issue: 1 SAC Date: Nov 2020 Page: 2 of 22 1. Acknowledgements Working Group members: Dr Silvia Ramos, University of Kent (Champion) Prof. Andrea Russell, Southampton University (DUC representative) Dr Philip Ash, University of Leicester Dr Mike Baker, University of Manchester Dr Nathan Hollingsworth, Infineum UK Ltd. Dr Tim Hyde, Johnson Matthey Dr Bhoopesh Mishra, University of Leeds Dr Thomas Penfold, Newcastle University Prof. Sven Schroeder, University of Leeds Prof. Susannah Speller, University of Oxford Dr Gosia Swadzba-Kwasny, Queen’s University Belfast Prof. Robert Weatherup, University of Oxford Dr Sofia Diaz-Moreno, Diamond Light Source (Spectroscopy Science Group Leader) Dr Monica Amboage, Diamond Light Source (Diamond’s Lead) Dr Diego Gianolio, Diamond Light Source (Diamond’s Lead) Additional contributors: Dr Peter Wells (Southampton University), Dr Feng Ryan Wang (University College London), Dr Anna Kroner, Dr John Sutter, Martin Burt, Steve Millward (Diamond Light Source). UWG meetings: 2nd September 2020, 30th September 2020, 12th October 2020, 26th October 2020. Webinar: 14th October 2020 2 Doc No: DLS-SACDISCo-BERRIES Issue: 1 SAC Date: Nov 2020 Page: 3 of 22 2. Executive Summary This proposal sets out the case for developing internationally competitive photon-in/photon-out spectroscopy capabilities in the UK. The proposed beamline, BERRIES, will bring two new techniques to Diamond, pink-beam X-ray emission spectroscopy (pink-beam XES) and X-ray Raman scattering (XRS), whilst also enhancing the provision of high energy resolution fluorescence detection XAS (HERFD-XAS) and resonance XES (RXES).
    [Show full text]
  • Fiscal Year 2016 Award Abstracts
    DOE Office of Science Early Career Research Program Awardee Abstracts Fiscal Year 2016 Laser Driven X‐ray Sources for High Energy Density Science Experiments Dr. Félicie Albert, Research Scientist Hohlraum Physics and Optical Diagnostics Group High Energy Density Science and Technology Division National Ignition Facility and Photon Science Directorate Lawrence Livermore National Laboratory Livermore, CA 94551 Understanding the relationships between temperature, pressure, and density in extreme environments is one of the grand challenges of high energy density (HED) plasma science. Lasers and x‐ ray free electron laser (XFEL) facilities are now capable of driving matter to extreme states of temperature and pressure. However, these HED plasmas are extremely difficult to probe because most of the time they are in a non‐equilibrium state and are transient in nature. Hence, there is a critical need to configure and test new diagnostic tools to measure the properties and dynamics of HED plasmas. This project brings one of the most promising applications of laser‐based plasma accelerators (betatron x‐ray radiation) to probe HED plasmas with unprecedented sub‐picosecond resolution. Our research will generate new data on sub‐picosecond dynamics of electron‐ion equilibration in warm dense matter, laser‐driven shocks, and opacity in HED plasmas that cannot be measured by other existing methods. Our integrated experimental approach, combined with a host of theoretical models and tools, will allow us to probe radiation‐matter interactions under extreme conditions to accelerate breakthroughs in frontier plasma science. This research was selected for funding by the Office of Fusion Energy Sciences. 1 DOE Office of Science Early Career Research Program Awardee Abstracts Fiscal Year 2016 Ultrafast Dynamics of Molecules on Surfaces Studied with Time‐Resolved XUV Photoelectron Spectroscopy Dr.
    [Show full text]
  • Index of Descriptors
    Index of Descriptors actinide complexes : Humic Acids by means of Radioactive Tracers GFR20000025 Compatibility of organic waste forms with geological disposal in Boom clay The ALINA-process for BEL20000017 actinides(III)/lanthanides(III) group separation from acidic radioactive waste solutions. Fundamental Investigation of Complexation and Migration of studies and counter current extraction experiments. Actinides and Non-radioactive Substances with GFR20000027 Humic Acids under Natural Conditions - Complexation of Humic Acids with Tetravalent adsorption : Actinides (Th, U, Np)- GFR20000013 Investigation of the geochemical stability of clays in underground repositories in salt formations Investigations on the complexation behaviour of GFR20000004 humic acids and their influence on the migration of radioactive and non-radioactive substances Development of a Computer Code to Model Three- GFR20000017 Dimensional Pollutant Transport GFR20000007 TRANCOM-CLAY-II: Transport of Radionuclides in a reducing clay sediment advanced software technology and algorit : BEL20000008 Component (CCA) Extensions to SciTL actinides : USA20000115 A fast method for determining alpha active nuclide in advisory and assistance services : concrete near the clearance level by direct measurement of large and thin sources - DOE-CH Site Technology Coordination Group automatisation of the method USA20000038 GFR20000037 aging : Compatibility of organic waste forms with geological disposal in Boom clay The sealing effect of backfilling materials: bench BEL20000017 scale
    [Show full text]
  • Actinide Nanoparticle Research
    Actinide Nanoparticle Research . Stepan N. Kalmykov l Melissa A. Denecke Editors Actinide Nanoparticle Research Editors Prof.Dr. Stepan N. Kalmykov Dr. Melissa A. Denecke Lomonosov Moscow State University Forschungszentrum Karlsruhe Dept. Chemistry Inst. Nukleare Leninskie Gory 1/3 Entsorgungstechnik 119991 Moscow Postfach 36 40 Russia 76021 Karlsruhe [email protected] Germany [email protected] ISBN 978-3-642-11431-1 e-ISBN 978-3-642-11432-8 DOI 10.1007/978-3-642-11432-8 Springer Heidelberg Dordrecht London New York Library of Congress Control Number: 2011924898 # Springer-Verlag Berlin Heidelberg 2011 This work is subject to copyright. All rights are reserved, whether the whole or part of the material is concerned, specifically the rights of translation, reprinting, reuse of illustrations, recitation, broadcasting, reproduction on microfilm or in any other way, and storage in data banks. Duplication of this publication or parts thereof is permitted only under the provisions of the German Copyright Law of September 9, 1965, in its current version, and permission for use must always be obtained from Springer. Violations are liable to prosecution under the German Copyright Law. The use of general descriptive names, registered names, trademarks, etc. in this publication does not imply, even in the absence of a specific statement, that such names are exempt from the relevant protective laws and regulations and therefore free for general use. Cover design: eStudio Calamar S.L. Printed on acid-free paper Springer is part of Springer ScienceþBusiness Media (www.springer.com) Foreword A challenge for most of the countries that developed nuclear fuel cycles is the problem of safe and economically reasonable methods for management of spent nuclear fuel (SNF) and radioactive wastes.
    [Show full text]
  • Actinide Separation Chemistry in Nuclear Waste Streams and Materials, December 1997
    NEA/NSC/DOC(97)19 NEA NUCLEAR SCIENCE COMMITTEE ACTINIDE SEPARATION CHEMISTRY IN NUCLEAR WASTE STREAMS AND MATERIALS December 1997 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT FOREWORD The separation of actinide elements from various waste materials is a significant problem facing developed countries. The issue arises primarily because of the potential long-term hazard of many of the actinides, but is also due to the regulatory requirements associated with actinide waste disposal, which are different from those associated with other radioactive wastes. The different regulations are in turn related to the different health hazards and generally longer half lives of the actinides. This issue is of continuing interest to the OECD/NEA Member countries primarily in relation to waste produced within power station fuel recycle. Similar problems exist for waste produced in the past as a result of nuclear weapons production programmes and wastes likely to be produced in the future emerging from operations required for waste disposal. The Nuclear Science Committee, representing the interests of the basic R&D in the OECD/NEA Member countries, has established a task force of experts in actinide chemistry to review the current and developing separation techniques and chemical processes of interest in separating actinides. This task force was commissioned with the preparation of a report on the subject. The task force members are listed in Annex 1. This report is intended to provide a timely and representative guide to technical journals and other sources of separation chemistry information on the actinide elements. An important objective is to provide information that may be used to conserve energy and protect humans and the environment.
    [Show full text]
  • Quantum Chemical Studies of Actinides and Lanthanides: from Small Molecules to Nanoclusters
    Quantum Chemical Studies of Actinides and Lanthanides: From Small Molecules to Nanoclusters A DISSERTATION SUBMITTED TO THE FACULTY OF THE GRADUATE SCHOOL OF THE UNIVERSITY OF MINNESOTA BY Bess Vlaisavljevich IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF Doctor of Philosophy Professor Laura Gagliardi June, 2013 c Bess Vlaisavljevich 2013 ALL RIGHTS RESERVED Acknowledgements There are many people that I would like to thank for all of their support through my graduate school years. First of all, I'd like to thank my advisor Prof. Laura Gagliardi for her encouragement, advice, and providing me with countless opportunities to develop as a scientist. Additionally, I'd like to thank Prof. David Blank and Prof. Chris Cramer for taking the time to be great mentors in teaching. I would also like to thank Prof. Chris Cramer for all of the helpful discussions in research as well. I'd also like to thank the Chemistry faculty at the University of Minnesota { Twin Cities for all they have taught me. I'd also like to thank Profs. Joe Alia, Nancy Carpenter, Jenn Goodnough, Ted Pappenfus, and Jim Togeas at the University of Minnesota { Morris for starting me off on the right foot in my chemistry career. I would like thank all of the collaborators from outside the University of Minnesota for the very useful discussions especially Prof. Thomas Albrecht-Schmidt, Prof. Lester Andrews, Prof. Carles Bo, Prof. Peter Burns, Prof. Scott Daly, Prof. Paula Diaconescu, Prof. Greg Girolami, Dr. Ivan Infante, Dr. Jason Keith, Prof. Stephen Liddle, Prof. May Nyman, Dr. Jie Qiu, Dr.
    [Show full text]
  • Production and Chemical Processing of 177Lu for Nuclear Medicine at the Munich Research Reactor FRM-II
    Institut f¨urRadiochemie Production and chemical processing of 177Lu for nuclear medicine at the Munich research reactor FRM-II Dissertation of Zuzana Dvoˇr´akov´a Technische Universit¨atM¨unchen Institut f¨urRadiochemie der Technischen Universit¨atM¨unchen Production and chemical processing of 177Lu for nuclear medicine at the Munich research reactor FRM-II Zuzana Dvoˇr´akov´a Vollst¨andiger Abdruck der von der Fakult¨at f¨urChemie der Technischen Universit¨atM¨unchen zur Erlangung des akademischen Grades eines Doktors der Naturwissenschaften (Dr. rer. nat.) genehmigten Dissertation. Vorsitzender: Univ.-Prof. Dr. Dr. h. c. B. Rieger Pr¨ufer der Dissertation: 1. Univ.-Prof. Dr. A. T¨urler 2. Univ.-Prof. Dr. K. K¨ohler Die Dissertation wurde am 13.8.2007 bei der Technischen Universit¨at M¨unchen eingere- icht und durch die Fakult¨at f¨urChemie am 20.9.2007 angenommen. Abstract The main goal of the present dissertation was to investigate the feasibility of pro- ducing the radionuclide 177Lu at the Munich research reactor FRM-II. Lutetium-177 represents an ideal therapeutic radioisotope with suitable chemical properties and nuclear decay characteristics. Radiopharmaceuticals containing 177Lu are currently under development and tested for the treatment of various cancers in dozens of clin- ical trials around the world. The radionuclide 177Lu can be produced either directly by the 176Lu(n, γ)177Lu β− reaction or indirectly by the 176Yb(n, γ)177Yb → 177Lu reaction. The irradiation yield of 177Lu in both production routes was experimentally determined and compared with theoretical calculations. A reliable method for the calculation of the 177Lu yield, based on the Westcott convention, was established, which is more accurate than the methods published in the literature.
    [Show full text]
  • Experimental Studies of Actinides in Molten Salts
    LA-10340 UC-4 Issued: June 1985 LA—10340 DE85 015368 Experimental Studies of Actinides in Molten Salts James G. Reavis 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 responsi- bility fcr the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents 'hat its use would not infringe privately owned rights. Refer- ence herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom- mendation, 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. Los Alamos National Laboratory Los Alamos, New Mexico 87545 !IT"ISUnOS OF THIS DOCUMENT IS ONLIMfTW t> EXPERIMENTAL STUDIES OF ACTINIDES IN MOLTEN SALTS by J. G. Reavis ABSTRACT This review stresses techniques used in studies of molten salts containing multigram amounts of actinides exhibiting intense alpha activity but little or no penetrating gamma radiation. The preponderance of studies have used halides because oxygen- containing actinide compounds (other than oxides) are generally unstable at high temperatures. Topics discussed here include special enclosures, materials problems, preparation and purification of acticide elements and compounds, and measurements of various properties of the molten volts. Property measurements discussed are phase relationships, vapor pressure, density, viscosity, absorption spectra, electromotive force, and conductance.
    [Show full text]