Laser Isotope Separation (LIS), Technical and Economic
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The Behaviour of Polytetrafluoroethylene at High Pressure
THE BEHAVIOUR OF POLYTETRAFLUOROETHYLENE AT HIGH PRESSURE by Haroun Mahgerefteh A dissertation submitted to the University of London for the degree of Doctor of Philosophy Department of Chemical Engineering and Chemical Technology, Imperial College, London SW7 2BY. October 1984 If a man will begin with certainties, he shall end in doubts, but if he will be content to begin with doubts, he shall end in certainties. Robin Hyman TO MY PARENTS PREFACE This dissertation is a description of the work carried out in the Department of Chemical Engineering and Chemical Technology, Imperial College, London between October 1981 and October 1984. Except where acknowledged, the material presented is the original work of the author and includes nothing which is the outcome of work done in collaboration, and no part of it has been submitted for a degree at any other Univer sity. I am deeply indebted to Dr. Brian Briscoe for his excellent super vision during the course of my research. His help and guidance have been invaluable. It has been a pleasure to receive the help of many members of the Department, in particular Messrs. D. Wood and M. Dix of Electronics and Mr. B. Lucas of the Workshop. The help and support from all the members of my family especially my sister Deborah have been invaluable. I also thank Mrs. Joyce Burberry for patiently typing the manuscript. I gratefully acknowledge the support of the Science and Engineering Research Council and Imperial Chemical Industries PLC for the provision of a CASE studentship. Imperial College, H. Margerefteh -
The Taming of “49” Big Science in Little Time
The Taming of “49” Big science in little time Recollections of Edward F. Hammel During the Manhattan Project, plutonium was often referred to, simply, as 49. Number 4 was for the last digit in 94 (the atomic number of plutonium) and 9 for the last digit in plutonium-239, the isotope of choice for nuclear weapons. The story that unfolds was adapted from Plutonium Metallurgy at Los Alamos, 1943–1945, as Edward F. Hammel remembers the events of those years. 48 Los Alamos Science Number 26 2000 The Taming of “49” he work in plutonium chemistry tion work was an inevitable conse- the metal could be fabricated into and metallurgy carried out at quence of the nuclear and physical satisfactory weapon components. TLos Alamos (Site Y) between research that was still to be conducted In addition, not until January 1944 1943 and 1945 had a somewhat contro- on the metal. It would clearly have did the first few milligrams of pile- versial history. The controversy was been inefficient and time consuming to produced plutonium arrive at Los about who was going to do what. ship small amounts of plutonium metal Alamos. The first 1-gram shipment At the time Los Alamos was being back to Chicago for repurification and arrived in February 1944, and quantity organized, most of the expertise in plu- refabrication into different sizes and shipments of plutonium did not begin to tonium chemistry resided at Berkeley, shapes for the next-scheduled nuclear arrive at Los Alamos until May 1945. where plutonium was discovered in physics experiment. From the outset, it was clear that the December 1940, and at the Met Lab in Minimizing the time spent to solve purification of plutonium was the most Chicago. -
Extensive Interest in Nuclear Fuel Cycle Technologies
Institute for Science and International Security ISIS REPORT March 19, 2012 Department 70 and the Physics Research Center: Extensive Interest in Nuclear Fuel Cycle Technologies By David Albright, Paul Brannan, Mark Gorwitz, and Andrew Ortendahl On February 23, 2012, ISIS released the report, The Physics Research Center and Iran’s Parallel Military Nuclear Program, in which ISIS evaluated a set of 1,600 telexes outlining a set of departments or buying centers of the former Physics Research Center (PHRC). These departments appeared to be purchasing a variety of goods for specific nuclear technologies, including gas centrifuges, uranium conversion, uranium exploration and perhaps mining, and heavy water production. Figure 1 is a list of the purposes of these departments. The telexes are evaluated in more depth in the February 23, 2012 ISIS report and support that, contrary to Iran’s statements to the International Atomic Energy Agency (IAEA), the PHRC ran a parallel military nuclear program in the 1990s. In the telexes, ISIS identified a department called Department 70 that is linked to the PHRC. This department tried to procure or obtained technical publications and reports from a document center, relevant know-how from suppliers, catalogues from suppliers about particular goods, and a mini- computer from the Digital Equipment Corporation. Department 70 appears to have had personnel highly knowledgeable about the existing literature on a variety of fuel cycle technologies, particularly gas centrifuges. Orders to a British document center reveal many technical publications about gas centrifuges, atomic laser isotope enrichment, the production of uranium compounds including uranium tetrafluoride and uranium hexafluoride (and precursors such as hydrofluoric acid), nuclear grade graphite, and the production of heavy water. -
Development of a Viable Route for Lithium-6 Supply of DEMO and Future Fusion Power Plants T
Fusion Engineering and Design 149 (2019) 111339 Contents lists available at ScienceDirect Fusion Engineering and Design journal homepage: www.elsevier.com/locate/fusengdes Development of a viable route for lithium-6 supply of DEMO and future fusion power plants T T. Giegerich⁎, K. Battes, J.C. Schwenzer, C. Day Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany ARTICLE INFO ABSTRACT Keywords: In the European DEMO program, the design development of a demonstration power plant (DEMO) is currently in DEMO its pre-conceptual phase. In DEMO, breeding blankets will use large quantities of lithium, enriched in the isotope Lithium-6 lithium-6 (6Li), for breeding the tritium needed to feed the DT fusion reaction. Unfortunately, enriched lithium is Lithium enrichment commercially not available in the required quantities, which is threatening the success of future power plant ICOMAX process applications of nuclear fusion. Even if the manufacturing of the breeding blankets is still two decades ahead of Mercury us, it is now mandatory to address the topic of lithium-6 supply and to make sure that a viable supply (and HgLab reprocessing) route is available when needed. This paper presents an unbiased systems engineering approach assessing a number of available lithium iso- tope separation methods by defining requirements, rating them systematically and finally calculating a ranking number expressing the value of different methods. As a result, we suggest using a chemical exchange method based on a lithium amalgam system, but including some important improvements leading to a more efficient and ‘clean’ process (the ICOMAX process) in comparison with the formerly used COLEX process. -
Atomic Energy Je^K L'energie Atomique of Canada Umited Ksv Du Canada Li Mite E
AECL-7416 ATOMIC ENERGY JE^K L'ENERGIE ATOMIQUE OF CANADA UMITED KSV DU CANADA LI MITE E PROGRESS REPORT CHEMISTRY AND MATERIALS DIVISION 1 April -30 June, 1981 PR-CMa-57 Chalk River Nuclear Laboratories Chalk River, Ontario August 1981 PREVIOUS REPORTS IN THIS SERIES PR-CMa-56 January 1 to March 31, 1981 AECL-7332 PR-CMa-55 October 1 to December 31, 1980 AECL-7242 PR-CHa-54 July 1 to September 30, 1980 AECL-7156 PR-CMa-53 April 1 to June 30, 1980 AECL-7094 PR-CMa-57 ATOMIC ENERGY OF CANADA LIMITED PROGRESS REPORT April 1, 1981 - June 30, 1981 CHEMISTRY AND MATERIALS DIVISION The results and conclusions given here are not classified or restricted in any way; however, some of the information is of a preliminary nature. Readers interested in using the information in their own research are invited to consult with the contributors for further details. Copies of the AECL publications referred to in this report may be obtained by writing to the Scientific Document Distribution Offfee, Chalk River Nuclear Laboratories, Chalk River, Ontario, KOJ 1J0. Chalk River Nuclear Laboratories Chalk River, Ontario 1981 August AECL-7416 PROGRESS REPORT April 1, 1981 - June 30, 1981 CHEMISTRY AND MATERIALS DIVISION Director - T. A. Eastwood Secretary - Ms. A. E. Goodale Contents Page HIGHLIGHTS T.A. Eastwood (i) 1. SOLID STATE SCIENCE BRANCH I.V. Mitchell 1 2. GENERAL CHEMISTRY BRANCH I.H. Crocker 27 3. PHYSICAL CHEMISTRY BRANCH D.R. Smith 53 4. MATERIALS SCIENCE BRANCH B. Cox 71 (i) CHEMISTRY AND MATERIALS DIVISION HIGHLIGHTS T. -
Lithium Isotope Separation a Review of Possible Techniques
Canadian Fusion Fuels Technology Project Lithium Isotope Separation A Review of Possible Techniques Authors E.A. Symons Atomic Energy of Canada Limited CFFTP GENERAL CFFTP Report Number s Cross R< Report Number February 1985 CFFTP-G-85036 f AECL-8 The Canadian Fusion Fuels Technology Project represents part of Canada's overall effort in fusion development. The focus for CFFTP is tritium and tritium technology. The project is funded by the governments of Canada and Ontario, and by Ontario Hydro. The Project is managed by Ontario Hydro. CFFTP will sponsor research, development and studies to extend existing experience and capability gained in handling tritium as part of the CANDU fission program. It is planned that this work will be in full collaboration and serve the needs of international fusion programs. LITHIUM ISOTOPE SEPARATION: A REVIEW OF POSSIBLE TECHNIQUES Report No. CFFTP-G-85036 Cross Ref. Report No. AECL-8708 February, 1985 by E.A. Symons CFFTP GENERAL •C - Copyright Ontario Hydro, Canada - (1985) Enquiries about Copyright and reproduction should be addressed to: Program Manager, CFFTP 2700 Lakeshore Road West Mississauga, Ontario L5J 1K3 LITHIUM ISOTOPE SEPARATION: A REVIEW OF POSSIBLE TECHNIQUES Report No. OFFTP-G-85036 Cross-Ref Report No. AECL-87O8 February, 1985 by E.A. Symons (x. Prepared by: 0 E.A. Symons Physical Chemistry Branch Chemistry and Materials Division Atomic Energy of Canada Limited Reviewed by: D.P. Dautovich Manager - Technology Development Canadian Fusion Fuels Technology Project Approved by: T.S. Drolet Project Manager Canadian Fusion Fuels Technology Project ii ACKNOWLEDGEMENT This report has been prepared under Element 4 (Lithium Compound Chemistry) of the Fusion Breeder Blanket Program, which is jointly funded by AECL and CFFTP. -
Uranium Enrichment Plant Characteristics—A Training Manual for the IAEA
ORNL/TM-2019/1311 ISPO-553 Uranium Enrichment Plant Characteristics—A Training Manual for the IAEA J. M. Whitaker October 2019 Approved for public release. Distribution is unlimited. DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect. Website www.osti.gov Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900 E-mail [email protected] Website http://classic.ntis.gov/ Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange representatives, and International Nuclear Information System representatives from the following source: Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 Telephone 865-576-8401 Fax 865-576-5728 E-mail [email protected] Website http://www.osti.gov/contact.html 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. -
Economic Perspective for Uranium Enrichment
SIDEBAR 1: Economic Perspective for Uranium Enrichment he future demand for enriched are the customary measure of the effort uranium to fuel nuclear power required to produce, from a feed material plants is uncertain, Estimates of with a fried concentration of the desired T this demand depend on assump- isotope, a specified amount of product en- tions concerning projections of total electric riched to a specified concentration and tails, power demand, financial considerations, and or wastes, depleted to a specified concentra- government policies. The U.S. Department tion. For example, from feed material with a of Energy recently estimated that between uranium-235 concentration of 0.7 per cent now and the end of this century the gener- (the naturally occurring concentration), ation of nuclear power, and hence the need production of a kilogram of uranium enrich- for enriched uranium, will increase by a ed to about 3 per cent (the concentration factor of 2 to 3 both here and abroad. Sale of suitable for light-water reactor fuel) with tails enriched uranium to satisfy this increased depleted to 0.2 per cent requires about 4.3 demand can represent an important source SWU. of revenue for the United States, Through Gaseous diffusion is based on the greater fiscal year 1980 our cumulative revenues rate of diffusion through a porous barrier of from such sales amounted to over 7 billion the lighter component of a compressed dollars, and until recently foreign sales ac- gaseous mixture. For uranium enrichment counted for a major portion of this revenue. the gaseous mixture consists of uranium The sole source of enriched uranium until hexafluoride molecules containing 23$ 1974, the United States now supplies only uranium-235 ( UF6) or uranium-238 238 about 30 per cent of foreign demand, New ( UF6). -
Nuclear Fuel Cycle Information System
IAEA-TECDOC-1613 Nuclear Fuel Cycle Information System A Directory of Nuclear Fuel Cycle Facilities 2009 Edition April 2009 IAEA-TECDOC-1613 Nuclear Fuel Cycle Information System A Directory of Nuclear Fuel Cycle Facilities 2009 Edition April 2009 The originating Section of this publication in the IAEA was: Nuclear Fuel Cycle and Materials Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria NUCLEAR FUEL CYCLE INFORMATION SYSTEM: A DIRECTORY OF NUCLEAR FUEL CYCLE FACILITIES 2009 EDITION IAEA, VIENNA, 2009 ISBN 978–92–0–102109–0 ISSN 1011–4289 © IAEA, 2009 Printed by the IAEA in Austria April 2009 FOREWORD In recent years, there have been rising expectations for nuclear power all over the world to meet the ever increasing demand for electricity. Several countries with nuclear power have declared intentions to build new nuclear power plants to replace their existing capacities or to add new capacities. Several other countries without nuclear power are taking an active interest in launching nuclear power programmes. Nuclear power and nuclear fuel cycle go hand in hand. Hence implementations of such nuclear power programmes cannot be considered without parallel development in the nuclear fuel cycle area. The worldwide nuclear fuel cycle industry comprises several global players which are operating on a commercial basis in more than one country and many other domestic players which are active only in their respective countries. Knowing the current status and the future outlook of the nuclear fuel cycle industry is important not only for meeting the needs of global nuclear power development but also for facilitating the multilateral approach to the nuclear fuel cycle currently being discussed with a focus on ‘assurance of fuel supply’ and ‘non-proliferation of nuclear materials’. -
R:\TEMP\Bobbi\RDD-8 3-16-04 Reprint.Wpd
OFFICIAL USE ONLY RESTRICTED DATA DECLASSIFICATION DECISIONS 1946 TO THE PRESENT (RDD-8) January 1, 2002 U.S. Department of Energy Office of Health, Safety and Security Office of Classification Contains information which may be exempt from public release under the Freedom of Information Act (5 U.S.C. 552), exemption number(s) 2. Approval by the Department of Energy prior to public release is required. Reviewed by: Richard J. Lyons Date: 3/20/2002 NOTICE This document provides historical perspective on the sequence of declassification actions performed by the Department of Energy and its predecessor agencies. It is meant to convey the amount and types of information declassified over the years. Although the language of the original declassification authorities is cited verbatim as much as possible to preserve the historical intent of the declassification, THIS DOCUMENT IS NOT TO BE USED AS THE BASIS FOR DECLASSIFYING DOCUMENTS AND MATERIALS without specific authorization from the Director, Information Classification and Control Policy. Classification guides designed for that specific purpose must be used. OFFICIAL USE ONLY OFFICIAL USE ONLY This page intentionally left blank OFFICIAL USE ONLY OFFICIAL USE ONLY FOREWORD This document supersedes Restricted Data Declassification Decisions - 1946 To The Present (RDD-7), January 1, 2001. This is the eighth edition of a document first published in June 1994. This latest edition includes editorial corrections to RDD-7, all declassification actions that have been made since the January 1, 2001, publication date of RDD-7 and any additional declassification actions which were subsequently discovered or confirmed. Note that the terms “declassification” or “declassification action,” as used in this document, refer to changes in classification policy which result in a specific fact or concept that was classified in the past being now unclassified. -
Highly Enriched Uranium (HEU) Is Defined As Uranium That Has Been Enriched to 20 Percent Or Greater in the Uranium-235 Isotope
- DRAFT U.S. DEPARTMENTOF ENERGY NATIONALNUCLEAR SECURITY ADMINISTRATION OFFICEOF THE DEPUTYADMINISTRATOR FOR DEFENSEPROGRAMS OFFICIAL USE ONLY - DRAFT - DRAFT U.S. DEPARTMENTOF ENERGY NATIONALNUCLEAR SECURITY ADMINISTRATION OFFICEOF THE DEPUTYADMINISTRATOR FOR DEFENSEPROGRAMS JANUARY200 1 - DRAFT - DRAFT Highly enriched uranium (HEU) is defined as uranium that has been enriched to 20 percent or greater in the uranium-235 isotope. All HEU is considered to be weapons-usable. HEU comes in different forms, including metals, oxides, solutions, reactor fuel, and irradiated spent nuclear fuel. Pictured above is a metal disk or "button" of HEU. - DRAFT - DRAFT .TABLE OF CONTENTS YL..*--~-*..~~.. -- - &*. +"-. w-~P~zF~zr~--~-"?wa~..=-&..m~w-=..L " EXECUTIVESUMMARY ...................................................................................... 1 BACKGROUND.................................................................................................................. 1 U.S. HEU INVENTORY...................................................................................................... 2 MATERIALBALANCE .......................................................................................................... 3 NEWLYDECLASSIFIED INFORMATION ........................................................................................ 3 CORRECTIONSTO PREVIOUSLY RELEASED DATA ........................................................................ 3 SECTION2 = URANIUMPRODUCTION AND UTILIZATION........................................... 21 OVERVIEWOF -
An Access-Dictionary of Internationalist High Tech Latinate English
An Access-Dictionary of Internationalist High Tech Latinate English Excerpted from Word Power, Public Speaking Confidence, and Dictionary-Based Learning, Copyright © 2007 by Robert Oliphant, columnist, Education News Author of The Latin-Old English Glossary in British Museum MS 3376 (Mouton, 1966) and A Piano for Mrs. Cimino (Prentice Hall, 1980) INTRODUCTION Strictly speaking, this is simply a list of technical terms: 30,680 of them presented in an alphabetical sequence of 52 professional subject fields ranging from Aeronautics to Zoology. Practically considered, though, every item on the list can be quickly accessed in the Random House Webster’s Unabridged Dictionary (RHU), updated second edition of 2007, or in its CD – ROM WordGenius® version. So what’s here is actually an in-depth learning tool for mastering the basic vocabularies of what today can fairly be called American-Pronunciation Internationalist High Tech Latinate English. Dictionary authority. This list, by virtue of its dictionary link, has far more authority than a conventional professional-subject glossary, even the one offered online by the University of Maryland Medical Center. American dictionaries, after all, have always assigned their technical terms to professional experts in specific fields, identified those experts in print, and in effect held them responsible for the accuracy and comprehensiveness of each entry. Even more important, the entries themselves offer learners a complete sketch of each target word (headword). Memorization. For professionals, memorization is a basic career requirement. Any physician will tell you how much of it is called for in medical school and how hard it is, thanks to thousands of strange, exotic shapes like <myocardium> that have to be taken apart in the mind and reassembled like pieces of an unpronounceable jigsaw puzzle.