Extensive Interest in Nuclear Fuel Cycle Technologies
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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. -
Laser Isotope Separation (LIS), Technical and Economic
NASA TECHNICAL MEMORANDUM A STATUS OF PROGRESS FOR THL LASER lsofopE SEPARATION (11 SI PROCESS +tear 1976 NASA George C. Mdr~bdlSpace Flight Center Marshdl Space Fb$t Center, Alabama lLSFC - Form 3190 (Rev June 1971) REPORT STANDARD TITLE PACE I nEPMTn0. 3. RECIPIENT*$ CATILOC NO. NASA TM X-73345 10 TITLE UO SUTlTLt IS. REPORT DATE I September A st.tUaof for Iaser isotOpe ¶tian lS76 I Progress the (LIS) 6 PERFWYIIIG WGUIZATIO* CQOE George C. M8ralmll!3gam Flight Center I 1. COUTRUT OR am yo. I MarW Flight Center, Alabama 35812 Tecbnid Memormdum National Aemutics and Space Administration Washingtan, D.C. 20546 I I Prepared by Systems Aaalysis and Integration Iaboratory, Science and Engineering An overview of the various categories of the LE3 methodology is given together with illustrations showing a simplified version of the LIS tecbnique, an example of the two-phoiin photoionization category, and a diagram depicting how the energy levels of various isdope influence the LIS process. A&icatlons have been proposed for the LIS system which, in addition to the use to enrich uranium, could in themselves develop into programs of tremendous scope and breadth. Such applications as treatment of radioac '--ewastes from light-water nKzlear reactors, enriching the deuterlum isotope to make heavv-water, and enrlchhg tik light isotopes of such 17 KEt WORDS 18. DISTRIBUTION STATEMENT 5ECUQlTY CLASSIF. Ff thh PI*) 21 NO. OF PAbFS 22 PRICE Unclassified Unclassified I 20 NTIS PREFACE Since the publication of t& first Techid hiemomxitun (TM X-64947) on the Laser hotope Separation (LE)process in May 1975 [l], there bbeen a virtual explosion of available information on this process. -
Current & Future Uranium Enrichment Technologies
The History of the Gas Centrifuge and Its Role in Nuclear Proliferation Houston Wood, Professor Mechanical & Aerospace Engineering University of Virginia Presented at Wilson Center Washington, D.C. January 20, 2010 Early Days • Isotopes were discovered in early 1900’s. • Centrifuge separation of isotopes first suggested by Lindemann and Aston (1919) • Chapman, Mulliken, Harkens and others tried unsuccessful experiments. • First successful experiments at UVA in 1934 by Prof. Jesse Beams with isotopes of Chlorine. • Attempts to use centrifuges in Manhattan project were unsuccessful. 20 January 2010 Houston Wood Professor Jesse W. Beams University of Virginia 1898 - 1977 20 January 2010 Houston Wood Early Days at UVA • Work on centrifuges during Manhattan project had a number of failures. • Project was terminated. • Concern over potential competition from German centrifuges led AEC to restart work at UVA in 1955 under guidance of A.R. Kulthau. 20 January 2010 Houston Wood Meanwhile in Europe • German research was being led by Konrad Beyerle in Göttingen and Wilhelm Groth at University of Bonn • Research in the Netherlands was being directed by Jacob Kistemaker. 20 January 2010 Houston Wood USSR • At the end of WWII, Soviets took many POWs from Germany. • They started effort to develop nuclear weapons. • Organization at Sinop: – Von Ardenne – Electromagnetic Separation – Thiessen – Gaseous Diffusion – Steenbeck Group – Included Centrifuge 20 January 2010 Houston Wood USSR (cont’d) • Competition between gaseous diffusion and gas centrifuge. • Reputed problems with GD enriching to weapons grade level. • Centrifuge considered for “topping off.” • Competition for long rotor vs. short rotor. • Steenbeck group transferred from Sinop to Kirov plant in Leningrad (~1951). -
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. -
Gas Centrifuge Technology: Proliferation Concerns and International Safeguards Brian D
Gas Centrifuge Technology: Proliferation Concerns and International Safeguards Brian D. Boyer Los Alamos National Laboratory Trinity Section American Nuclear Society Santa Fe, NM November 7, 2014 Acknowledgment to M. Rosenthal (BNL), J.M. Whitaker (ORNL), H. Wood (UVA), O. Heinonen (Harvard Belfer School), B. Bush (IAEA-Ret.), C. Bathke (LANL) for sources of ideas, information, and knowledge UNCLASSIFIED Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA Enrichment / Proliferation / Safeguards . Enrichment technology – The centrifuge story . Proliferation of technology – Global Networks . IAEA Safeguards – The NPT Bargain Enrichment Proliferation Safeguards U.S. DOE Centrifuges – DOE / Pres. George W. Bush at ORNL B. Boyer and K. Akilimali - IAEA Zippe Centrifuge – Deutsches Museum (Munich) briefed on seized Libyan nuclear Safeguards Verifying Spent Fuel in www.deutsches-museum.de/en/exhibitions/energy/energy-technology/nuclear-energy/ equipment (ORNL) Training in Sweden (Ski-1999) UNCLASSIFIED 2 Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA The Nuclear Fuel Cycle and Proliferation Paths to WMDs IAEA Safeguards On URANIUM Path Weapon Assembly Convert UF6 to U Metal Pre-Safeguards Natural Enriched DIVERSION Material (INFCIRC/153) Uranium Uranium PATH “Open” Cycle WEAPONS PATHS Fuel – Natural Uranium or LEU In closed cycle – MOX Fuel (U and Pu) “Closed” Cycle IAEA Safeguards On PLUTONIUM Path Convert Pu Plutonium Compounds to Pu Metal DIVERSION PATH To Repository -
Groundwater Calculations for Depleted Uranium Disposed of As
ANL/EAD/TM-111 Groundwater Calculations for Depleted Uranium Disposed of as Uranium Tetrafluoride (UF4) Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States Government and operated by The University of Chicago under the provisions of a contract with the Department of Energy. This technical memorandum is a product of Argonne’s Environmental Assessment Division (EAD). For information on the division's scientific and engineering activities, contact: Director, Environmental Assessment Division Argonne National Laboratory Argonne, Illinois 60439-4832 Telephone (630) 252-3107 Presented in this technical memorandum are preliminary results of ongoing work or work that is more limited in scope and depth than that described in formal reports issued by the EAD. Publishing support services were provided by Argonne’s Information and Publishing Division (for more information, see IPD’s home page: http://www.ipd.anl.gov/). 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 The University of Chicago, nor any of their employees or officers, 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. -
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. -
Nuclear Fuel Cycle
Quality and Standards for your converted material Hex Business at Springfields • Westinghouse will deliver on its promise of providing quality assurance for your company. • We pride ourselves on our engineering expertise and technical ability working to international standards including ISO 9001, 14001 and 18001. • Springfields has a long and successful history in the fuel cycle with over 40 years expertise in Hex conversion. Natural Mining Enrichment Fuel Fabrication Milling Nuclear Conversion Fuel Cycle Power Plant Reprocessing Electricity High Level Waste Storage Spent Fuel Storage www.westinghousenuclear.com Hex Business Rotary Kiln Plant Hex Plant Modern nuclear reactor designs such as Pressurised Water and Light Water Reactors To Atmosphere Uranium Trioxide UO – UF Conversion UF – UF Conversion UO 3 4 4 6 need nuclear fuel, made from Uranium Dioxide. 3 UO3 is transported to Kiln Plant in drums where it Uranium Hexafluoride is produced by the reaction UO To Atmosphere 3 is transferred onto a conveyor system. From here of UF with elemental gaseous fluorine in a Uranium Hexafluoride (UF6 ) is an essential intermediate product used in the Feed Hopper 4 Run Off Discharge the drums are delivered into the process via a fluidised bed reactor at 475°C. The fluorine manufacture of Uranium Dioxide fuels. Water UF6 mechanised tipping system. is produced by the electrolysis of anhydrous Condensers Hydration is the first stage in the treatment of hydrofluoric acid (AHF) in a potassium bi-fluoride Vac Back Air UO for the production of UF . electrolyte. 3 4 Secondary Meeting World Demands Advanced Technology Water Glycol Hydrator Heating & Cooling UO2 Transfer AHF Primary The Springfields Hex facilities are capable of Both plants demonstrate proven and state- To Scrubbers Hopper To Scrubbers H2 Transport Rotary Off-Gas Cylinder producing up to 5,500 tU of (UF6) annually, of-the-art technology. -
The Challenge of Developing of a High Speed Rotor Assembly by Mr R.K
The Challenge of Developing a High Speed Rotor Assembly - How It Was Met Shri R.K. Garg, FNAE Preamble The development of a high speed rotating machine commonly known as ‘Gas Centrifuge’ and used in enrichment of Uranium is considered a difficult and guarded technology, but strategic for the nuclear energy programme. This was achieved in the Bhabha Atomic Research Centre (BARC) during the period 1980–1990 by entirely indigenous R&D efforts. For me, as a leading participant in this development, right from conception to the final stage, it was both, a challenge and unique opportunity which not many engineers get throughout their professional career. I take pride in sharing with fellow engineers and scientists my experience and my belief that for a dedicated team, no task is impossible if the right working environment is provided. Being a multi- disciplinary project, the R&D team comprised of about twenty engineers and scientists in the disciplines of chemical, mechanical, electrical, electronics and instrumentation engineering, metallurgy, physics and chemistry. One unique feature of this team was that except two of us, all others had joined directly from the Training School run by BARC to work on this project. The credit for the success of this project goes to all of them who worked with dedication and team spirit and employed several innovative ideas. Glimpses of some of the materials, components and systems needed for this programme and the technological and managerial approaches that were adopted for this development, leading to the setting up of a demonstration facility, are provided in this article. -
\.J ,. John an Mccone/ , ,I;' I Chai7;>Man ' Genei'm A, R
REDACTED COpy Conglreu of the United Statea Joint Committ&:t, on Atomic Ener,>gy Full Committee -=- ,....-'".~_. Meeting No" Time; 10:00 a.tIl> pu.,ce: Room FQ88.• the Capitol Date: Auguat 30. 1960 PURPOSE WITNESSES. AEC \.J ,. , ,I;' John An McCone/i Chai7;>man ' GeneI'M A, R. ~edecke, Gene>l>'al 1'.![anagel' Geol>' ge F. Quinn, DiX'ectOl:'. Div. 0% Plfoduetion Charle.lI L.Marllhall. Dil"?edol:', Di,'" of Clsasification D1:. :?aul McDaniel, pUector, Div, of Relleal:'ch I:lJ:'. (;. L. Rogolla, Oiv.l')f Re8eOlS.d~ Ino ¢eorge A, Kolatlld, Chief, PIWF1.ell and Mathematics Blranch; Div. of Rel!iIlall',ch , ., , I / S&ate 0!:Ral:t.m'!~ / Chul!lll Sullivan /) EXECUTIVE SESSION MEETING NO. 86-2-49 TUESDAY, AUGUST JO, 1960 Joint Committee on Atomic Energy Congress of the United States Washington, D. C. The Joint Committee on Atomic Energy met, pursuant to call, at 10:15 p.m., in the Committee Room, the Capitol, Honorable Clinton p. Anderson (Chairman) presiding. Present were: Senators Clinton p. Anderson (presiding), John O. Pastore, Albert Gore, Bourke B. Hickenlooper and Wallace Bennett; Representatives Chet Holifield, Melvin Price, James E. Van Zandt, Craig Hosmer and William Bates. Committee Consultants present: Captain Edward J. Bauser, USN, and Lt. Colonel Richard T. Lunger. Committee staff present: James T. Ramey, Executive Director, John T. Conway, David R. Toll, Carey Brewer, George T. Murphy, Jr., and Kenneth MacAlpine. Representatives of the Atomic Energy Commission: Honorable John A. McCone, Chairman, Honorable Robert E. Wilson and Hooorable Loren Olson, Commissioners, General A. R. Luedecke, General Manager, George F. -
Medical Effects of Internal Contamination with Uranium Asaf Durakoviæ Department of Nuclear Medicine, Georgetown University School of Medicine, Washington D.C., USA
COMMENT THIS ARTICLE SEE COMMENTS ON THIS ARTICLE CONTACT AUTHOR March 1999 (Volume 40, Number 1) Medical Effects of Internal Contamination with Uranium Asaf Durakoviæ Department of Nuclear Medicine, Georgetown University School of Medicine, Washington D.C., USA The purpose of this work is to present an outline of the metabolic pathways of uranium isotopes and compounds, medical consequences of uranium poisoning, and an evaluation of the therapeutic alternatives in uranium internal contamination. The chemical toxicity of uranium has been recognized for more than two centuries. Animal experiments and human studies are conclusive about metabolic adverse affects and nephro- toxicity of uranium compounds. Radiation toxicity of uranium isotopes has been recognized since the beginning of the nuclear era, with well documented evidence of reproductive and developmental toxicity, as well as mutagenic and carcinogenic consequences of uranium internal contamination. Natural uranium (238U), an alpha emitter with a half-life of 4.5x109 years, is one of the primordial substances of the universe. It is found in the earth's crust, combined with 235U and 234U, alpha, beta, and gamma emitters with respective half-lives of 7.1x108 and 2.5x105 years. A special emphasis of this paper concerns depleted uranium. The legacy of radioactive waste, environmental and health hazards in the nuclear industry, and, more recently, the military use of depleted uranium in the tactical battlefield necessitates further insight into the toxicology of depleted uranium. The present controversy over the radiological and chemical toxicity of depleted uranium used in the Gulf War warrants further experimental and clinical investigations of its effects on the biosphere and human organisms. -
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.