DOCSLIB.ORG

Department of Energy 3-RMA-BOP-40- 20120327.1

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Department of Energy 3-RMA-BOP-40- 20120327.1 Department of Energy Portsmouth/Paducah Project Office 1017 Majestrc Drive, Suite 200 Lexington, Kentucky 4051 3 (85s) 219-4000 MAR 21 \An Ms. Maria Galanti PPPO-03- t426732-12 Ohio Environmental Protection Agency Southeast District Office 2195 Front Street Logan, Ohio 43138 Dear Ms. Galanti: FINAL ACTION MEMORANDUM FOR TFIB PLANT SUPPORT BUILDINGS AND S'TRUCTURES AT THE PORTSMOUTI{ GASBOUS DIFFUSION PLANT, PIKETON' OHIO References: l. Letter from V. Adams to M. Galanti, "Draft Action Memorandum for the Plant Sr"rpport Buildings and Structnres at the Portsmouth Gaseotts Diffusion Plant, Piketon, Ohio, (PPPO-03-141 6007-1 2)," dated February 29, 2012 2, Letter from M. Galanti to J. Bradburne and K. Wiehle, "Ohio EPA Concurrence with the Draft Action Memorandum for the Plant Support Buildings and Draft Structures at the Portsmouth Gaseous Diffusion Plant," dated March 8,2012 al Enclosecl, please fi¡d the Action Mentorctnchrnt Jbr the Plunl Sup¡torÍ Builtlings ancl Struclt'tres the Port;;ltouth Gaseous Dffision Plctnt, Pikelon, Ohio (DOE/PPPO/O3-0230eDÐ' Tlie Ohio Environmental Protection Agency (Ohio EPA) was provided with the draft Action Menrorandum, which Ohio EPA concurred on in the letter dated March 8,2012. This culrent Action Memorandum is the fi¡al version and has been signed by Mr' William E. Murphie, Manager of the ports¡routh/Paducah Project Office. This document was prepared in accordance wjthihe Aprit 13,2010 Director's Fincti Findings ctnd orcler,s.for Rentoval Action and Rentedictl lhe Investigaüàn ctncl Feasibiliry Stndy anrJ Rentediul Design ctncl lì.entediul Action, including September 12, 201I Modificcttion thereto. This transmittal includes: P ort sntouth Gaseon5 Dffi s ion Pl ant, P ike t on, Ohi o (DOE/PPPO/03-0230&D4); (DOE/PPPO/03- Structures ctt the Þorrsntoith Gct:;eous Di//Ltsion Plttnt, PikeÍon, Ohio 0207&D4),wliich the Ohio EPA reviewed and concurred on in a letter dated March S, 2012; and Ms. Galanli PPPO-03-1426732-t2 Þ Attacllreut 2: Responsiveness Sumrnary for Public Comnents Receivecl on the Engineering Ettcrluctl iott/Cost Annlysi,s.fòr lhe Pltrnl Suppotl Builtlings and Structures ¿tt lhe Porlsntouth Gaseou,; Di.llusion Pl.cutt, Piketon, Ohio, which inchrdes Appendix A: Tlansclipt of the Public Availability Session. Ohio EPA's engagenenl and participation in eally discussior, ar.rd dlaft docunent leviews was a tremendous ber.reht to the ploject and DOE appreciates yout cooperatìon. Ilyou l.rave auy questions ol lequile aclditional infor-mation, please coutacl me at (740) 8()7-2759 or I(risti Wielile o1'my staff a1 (740) 897-5020. Sincercly, // ". 1¿ -\ Y,ô ) Portsr.r]outh Site Dil ector Portsmouth/Paducah Ploj ect Olfi ce Enclosule: FtnaI Aclion. Mentorandum .fitr the Plctnt Sultporl Builtlings ond Stntt'tures ¿tt the Pù.tsmoutl't Gaseous Di/fùsion Plant, Piketon, Ollio cc w/ enclosule: lìachel.Bh"[email protected]. gov. PPPO/ORO [email protected]. gov, PPPO/POlìT'S Belt. [email protected]. gov, PPPO/LEX [email protected], PPPO/POR'l'S [email protected]. gov, PPPO/I-EX [email protected]. gov, PPPO/LEX I(Listi, [email protected]. gov, PPPO/POR'l-S Jìm. S1èr'[email protected],oh. us, Ohio EPA/Logan .Tamie. Jar.neson(-!fbports.corr, FBP/POR'lS Dennis.Carr@lbpo1 ts.col't't, FBP/PORTS [email protected], FBP/POR'f S Malc.Jervelt@lbpolts, com, FtlP/POR f S M ike. [email protected], gor,. IìSVPORTS [email protected],gov. RSI/POlìTS PPPO. DIrlì[email protected]. gov U.S. Department of Energy Portsmouth/Paducah Project Office This document has been approved for public release: Henry Thomas (signature on file) 3/14/2012 Classification & Information Officer Date Action Memorandum for the Plant Support Buildings and Structures at the Portsmouth Gaseous Diffusion Plant, Piketon, Ohio (DOE/PPPO/03-0230&D4) 1.0 PURPOSE The purpose of this Action Memorandum (AM) is to document the selection of the non-time-critical removal action for the decontamination and decommissioning (D&D) of 46 process support buildings/structures located at the Portsmouth Gaseous Diffusion Plant (PORTS), including associated materials or equipment anywhere within or adjacent to the buildings or structures. The removal action recommended in the Engineering Evaluation/Cost Analysis for the Plant Support Buildings and Structures at the Portsmouth Gaseous Diffusion Plant, Piketon, Ohio (EE/CA) (U.S. Department of Energy [DOE] 2011) is selected in this AM. The EE/CA is provided in Attachment 1, which is incorporated by reference into this AM as if it is fully set forth herein. 2.0 SITE DESCRIPTION AND CONTAMINANTS The plant support buildings and structures addressed in this AM are identified in Table 1 and shown on Figure 2 of the EE/CA. Table 1. PORTS Process Support Buildings Building Number Building Name DFF&O Groupa X-100 Administration Building 2 X-100B Air Conditioner Equipment Building 2 X-101 Dispensary 2 X-102 Cafeteria 2 X-104 Guard Headquarters 2 X-106 Tactical Response Building 1 X-106C New Fire Training Building 1 X-108H Pike Avenue Portal 1 X-109A Personnel Monitoring Station 1 X-109B Personnel Monitoring Station 1 X-109C Personnel Monitoring Station 1 X-343 Feed Vaporization and Sampling Building 4 X-530A High Voltage Switchyard 2 X-530B Switch House 2 X-530C Test and Repair Building 2 X-530D Oil House 2 X-530E Valve House 2 X-530F Valve House 2 X-600 Steam Plant 3 X-600B Steam Plant Shop Building 3 X-600C Ash Wash Treatment Building 3 X-611 Water Treatment Plant 2 X-611C Filter Building 1 X-611D Recarbonization Instrumentation Building 1 X-611E Clear Well and Chlorine Building 1 X-612 Elevated Storage Tank 1 X-614A Sewage Pumping Station 1 X-614B Sewage Pumping Station 1 1 U.S. Department of Energy Portsmouth/Paducah Project Office Table 1. PORTS Process Support Buildings (Continued) Building Number Building Name DFF&O Groupa X-618 North Holding Pond Storage Building 1 X-621 Coal Pile Treatment Facility 3 X-624-1 Decontamination Pad 2 X-640-1 Fire Water Pump House 1 X-640-2 Elevated Storage Tank 1 X-735A Landfill Utility Building 1 X-743 Lumber Storage Facility 1 X-744B Salt Storage Building 1 X-744G Bulk Storage Building 2 X-744H Bulk Storage Building 1 X-744J Bulk Storage Building 1 X-744L Stores and Maintenance Warehouse 1 X-744S Warehouse S Non-UEA 1 X-744W Surplus and Salvage Warehouse 1 X-750 Mobile Equipment Maintenance Shop 2 X-750A Garage Storage Building 1 X-752 Warehouse 1 X-752AT 1-4 Trailer Complex 1 aGroup 1 – Low Risk/Low Complexity, Group 2 – Industrial/Medium Complexity, Group 3 – Chemical/Medium Complexity, Group 4 – Radiological/High Complexity DFF&O = The April 13, 2010 Director’s Final Findings and Orders for Removal Action and Remedial Investigation and Feasibility Study and Remedial Design and Remedial Action, including the September 12, 2011 Modification thereto Based on previous reports (DOE 1993 and Theta Pro2Serve Management Company [TPMC] 2006), materials of construction, process knowledge, and the nature and extent of potential contamination, the most common contaminants of potential concern (COPCs) have been identified and presented along with the building descriptions in the EE/CA. The most common COPCs, which are substances that have the potential to adversely affect human health and the environment because of their concentrations, distribution, and toxicity, include asbestos, lead, radionuclides (primarily uranium), mercury, and polychlorinated biphenyls (PCBs). Some individual facilities also have the potential for volatile organic compounds, semivolatile organic compounds, heavy metals, corrosives, and biological hazards contaminants to be present. The process knowledge inquiry included examination of available records and photographs about building use and history, interviews, and walkdowns of the buildings and structures. The walkdowns provided information about chemicals used in the buildings, materials used in building construction and their current condition, and radiologically controlled areas that resulted from existing radiological surveys. Knowledge of materials or chemicals used in the buildings was the basis for identifying additional COPCs and for the information in the building descriptions provided in Appendix A of the EE/CA. The presence of older insulation or tiled floors indicates that asbestos is a COPC; older painted surfaces may contain lead and PCBs. DOE has evaluated potential reuse of the proposed buildings consistent with existing policies on disposition of buildings, DOE Order 458.1, and applicable segments of DOE Order 5400. Due to the presence of contamination, the aging condition of the buildings, and anticipated cost of maintenance, no future use has been identified at this time for these buildings. Inclusion of a building on this list does not preclude its future reuse, if a need should be identified. Buildings that are shown to be free of contamination according to DOE Order 458.1 and applicable segments of DOE Order 5400, either under current conditions or after decontamination for the purpose of reusing the building, can U.S. Department of Energy Portsmouth/Paducah Project Office be removed from this decision through a decision modification pursuant to agreement between DOE and the Ohio Environmental Protection Agency (Ohio EPA) and in accordance with The April 13, 2010 Director’s Final Findings and Orders for Removal Action and Remedial Investigation and Feasibility Study and Remedial Design and Remedial Action, including the September 12, 2011 Modification thereto (DFF&O) (Ohio EPA 2011) and the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The set of buildings addressed in the EE/CA and this AM includes a subset of buildings presented in Attachment G of the DFF&O, as well as the X-530A facility, which has been recently added to Attachment G.
Load more

Recommended publications
  • 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
    [Show full text]
  • 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 &paratian 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.
    [Show full text]
  • 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).
    [Show full text]
  • 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
    [Show full text]
  • 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.
    [Show full text]
  • The Gaseous Diffusion Process
    The Gaseous Diffusion Process The Portsmouth Gaseous Diffusion Plant, built in 1953-1954, produces enriched uranium hexafluoride (UF6) for commercial power reactors. In the past highly enriched uranium hexafluoride 235 was produced for the U.S. Navy. Enriched UF6 is material that contains the isotope U in assays (concentrations) greater than 0.711 weight percent. Commercial power plants currently use uranium enriched to the 3 to 5 percent range. The plant is capable of producing a range of U235 assays from 0.2% to over 97%. In late 1991, the equipment that produced high assay uranium was taken off line and placed in long term shutdown. High assay material that was declared excess by the US Navy and Department of Energy was fed into the cascade and blended down to the assays used by commercial power plants. This refeed project was completed in July 1998. It is possible that other high assay material will be declared excess in the future and would possibly be blended down at PORTS. It is also possible that high assay production could be resumed in the future. The plant's certification under the Nuclear Regulatory Commission (NRC) limits the maximum assay to 10%. Enrichment is accomplished using gaseous diffusion technology as the name implies. The gaseous diffusion cascade consists of many stages of equipment connected in series, i.e., in a cascade arrangement. Each stage consists of an electric motor, a compressor, and a converter which contains 235 a porous membrane through which the lighter U F6 diffuses at a slightly faster rate than the heavier 238 U F6.
    [Show full text]
  • Actinide Series
    20-Mar-20 Lecture 6-8 ACTINIDE SERIES (5f- elements) 4th year (Micro/Chem- Botany/Chem and Biochemistry) 18 Occurrence and Preparation of the Elements • Ac, Th, Pa, U are naturally occur • All known isotopes of all actinide metals are radioactive. • Thorium (Th) occurs in monazite sands, which are up to 20% ThO2. • Chemically it can be prepared from thermal decomposition of the iodide (de Boer process): ThI4 → Th + 2I2 • Uranium (U) occurs (at about 0.1%) in uraninite ores as U3O8, and carnotite as K2(UO2)2(VO4)2·3H2O. 19 1 20-Mar-20 Occurrence and Preparation of the Elements • The transuranic elements must all be prepared artificially. • About 1200 tonnes of plutonium (Pu) have been produced worldwide in reactors! 20 Actinide Metals Preparation • Reduction of AnF3 or AnF4 with vapors of Li, Mg, Ca or Ba at 1100 - 1400°C • Chlorides and oxides can be similarly reduced. Example: • Am can be Chemically prepared by reduction of AmF3 with Ba: 3Ba(g) + 2AmF3 → 3BaF2 + 2Am • Or by reduction of americium oxide with lanthanum (La) at 1200oC: Am2O3 + 2La → La2O3 + 2Am 21 2 20-Mar-20 Chemical reactivity of Actinides • Actinides are Highly reactive metals, especially when finely divided. • Typically react with: • air → tarnishing • boiling water or dilute acid → releasing Hydrogen • most non-metals in direct combination • Alkalies have no effect. 22 Oxides and hydroxides • Some actinides can exists in several oxide forms such as An2O3, AnO2, An2O5 and AnO3. • For all actinides, oxides AnO3 are amphoteric and An2O3, AnO2 and An2O5 are basic, they easily react with water, forming bases: An2O3 + 3 H2O → 2 An(OH)3.
    [Show full text]
  • Portsmouth Gaseous Diffusion Plant Spill Report 9-1 Underground Storage Tanks (Usts) 9-1
    ES/ESH-50 POEF-3050 PORTSMOUTH GASEOUS DIFFUSION PLANT ANNUAL SITE ENVIRONMENTAL REPORT FOR 1993 Project director F. C. Kornegay Project coordinator D. C. West Technical coordinator S. C. Newman Coordinating editor C. M. Horak Date Published: November 1994 Prepared by Environmental, Safety, and Health Compliance and Environmental Management staffs MARTIN MARIETTA ENERGY SYSTEMS, INC. P.O. Box 2008 Oak Ridge, Tennessee 37831-6285 and the Environmental Control Department Portsmouth Gaseous Diffusion Plant MARTIN MARIETTA ENERGY SYSTEMS, INC. P.O. Box 628 P^OMo 45661 |„ftT, U.S. DEPARTMENT OF ENERGY If i§ Ofm under contract No. DE-AC05-84OR21400 «t?3ff" & %M M ^ ^ and MARTIN MARIETTA UTILITY SERVICES, INC. for the UNITED STATES ENRICHMENT CORPORATION under contract No. DE-AC05-76OR00001 ^-^a*11^-'^ 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, make any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. DISCLAIMER Portions of this document may be illegible in electronic image products.
    [Show full text]
  • Mining, Milling, Conversion, and Enrichment of Uranium Ores
    MINING, MILLING, CONVERSION, AND ENRICHMENT OF URANIUM ORES Presented by Lisa Loden Export Control Implementation Global Nuclear Security Technology Division Oak Ridge National Laboratory Oak Ridge, TN 37830 Based on the slides of the late Dr. Clarence J. Hardy Past President Pacific Nuclear Council Secretary, Australian Nuclear Association Managing Director, Nuclear Fuel Australia Ltd July 19, 2011 Uranium Background Key points over 150 years •1789 – Uranium was discovered by Klaproth in Germany and named after the planet Uranus recently discovered by Herschel. •1896 – Professor Becquerel in Paris discovered radioactivity in uranium minerals; radium was then discovered by Mme. Curie in Paris. •1910 – Dr. Soddy in Cambridge, UK, proposed “isotopes” for atoms with different atomic weights but identical chemical properties. •1913 – Professor Thomson at Cambridge showed neon had “isotopes,” and, therefore, other elements were likely to have them, too. •1932 – Dr. Chadwick at Cambridge discovered the neutron. •1935 – Dr. Dempster in Chicago showed uranium contained 0.7% of uranium-235 and the rest was uranium-238. Uranium structure was shown to be 92 p and 146 n in U-238; 92 p and 143 n in U-235. Background to the Nuclear Fuel Cycle •1939 – Discovery of fission of uranium by Hahn and Strassman in Germany with extra neutrons released gave rise to the possibility of a chain reaction. •1939–1942 – Concept of an atomic bomb was developed in UK, U.S., and Germany. •1942 – Start of the Manhattan Project and the need for the nuclear fuel cycle with uranium ore processing, uranium enrichment, plutonium production, etc. •1942 – Chemical and physical separation processes became very important for the production of large amounts of uranium-235 and plutonium.
    [Show full text]
  • An Atomic History Chapter 2
    An Atomic History 0-3 8/11/02 7:31 AM Page 18 Chapter Two 19 THE FERMI-SZILARD PILE AND URANIUM RESEARCH The first government funding for nuclear research was allocated to purchase graphite and uranium oxide for the chain reaction experiments being organized by Fermi and World War II and the Manhattan Project Szilard at Columbia University in February 1940.2 This work, which began in New York 2 City, soon spread to Princeton, the University of Chicago, and research institutions in California.3 Even at this stage, the scientists knew that a chain reaction would need three major components in the right combination: fuel, moderator, and coolant. The fuel would contain the fissile material needed to support the fission process. The neutrons generated by the fission process had to be slowed by the moderator so that they could initiate addi- tional fission reactions. The heat that resulted from this process had to be removed by the coolant. Fermi’s initial research explored the possibility of a chain reaction with natural urani- The 1930s were a time of rapid progress in the development of nuclear physics. um. It was quickly determined that high-purity graphite served as the best neutron moder- Research accelerated in the early years of the Second World War, when new developments ator out of the materials then available.4 After extensive tests throughout 1940 and early were conceived and implemented in the midst of increasing wartime urgency. American 1941, Fermi and Szilard set up the first blocks of graphite at Columbia University in government interest in these developments was limited at first, but increased as the war September 1941.
    [Show full text]
  • Agenda November 14, 2012 Page 2  Dr
    ORANGE WATER AND SEWER AUTHORITY A public, non-profit agency providing water, sewer and reclaimed water services to the Carrboro-Chapel Hill community. MEMORANDUM TO: Natural Resources/Technical Systems Committee Terri Buckner (Chair) Dana Stidham Stephen Dear Michael Hughes Will Raymond Amy Witsil Alan Rimer (ex officio) THROUGH: Ed Kerwin FROM: Mason Crum DATE: November 14, 2012 SUBJECT: December 4, 2012 Natural Resources/Technical Systems (NRTS) Committee Meeting The NRTS Committee will meet December 4, 2012 at 4:00 PM in the OWASA Community Room. The Committee will discuss the two petitions received from the public on August 23rd and September 27th requesting that OWASA discontinue its current practice of adding fluoride to drinking water as part of the treatment process at the Jones Ferry Road Water Treatment Plant. The Committee Chair, Ms. Terri Buckner, and the OWASA staff have contacted Dr. Rebecca King, Section Chief of the NC Oral Health Section and Mr. Allen Spalt, co-founder of Toxic Free North Carolina and previous Carrboro Alderman, and they will participate in the Committee’s discussions. We will invite to the meeting the two petitioners and all OWASA customers (approximately 25) that have asked questions about our fluoridation practices since 1998. Please note that the NRTS Committee will not receive comments from the public at this Committee meeting. However, the public is welcome to present comments or petition the OWASA Board at any of its regularly scheduled Board meetings. Attached are statements from the following individuals/organizations stating their support for fluoridation of drinking water: Dr. L. Herald, State Health Director Dr.
    [Show full text]
  • Uranium Enrichment Processes Directed Self-Study Course! This Is the Fifth of Seven Modules Available in This Self-Study Course
    MODULE 5.0: ELECTROMAGNETIC SEPARATION (CALUTRON) AND THERMAL DIFFUSION Introduction Welcome to Module 5.0 of the Uranium Enrichment Processes Directed Self-Study Course! This is the fifth of seven modules available in this self-study course. The purpose of this module is to assist the trainee in describing the general principles of the electromagnetic separation (calutron) and thermal diffusion technologies and general facility and component layouts, identifying the uses of the calutron and thermal diffusion processes in industry and the production amounts of enriched uranium, and identifying the hazards and safety concerns for each process, including major incidents. This self-study module is designed to assist you in accomplishing the learning objectives listed at the beginning of the module. There are eight sections in this module. The module has self-check questions to help you assess your understanding of the concepts presented in the module. Before you Begin It is recommended that you have access to the following materials: 9 Trainee Guide Complete the following prerequisite: 9 Module 1.0 Introduction to Uranium Enrichment 1. Review the learning objectives. 2. Read each section within the module in sequential order. How to Complete 3. Complete the self-check questions and activities within this This Module module. 4. Check off the tracking form as you complete the self-check questions and/or activity within the module. 5. Contact your administrator as prompted for a progress review meeting. 6. Contact your administrator as prompted for any additional materials and/or specific assignments. 7. Complete all assignments related to this module. If no other materials or assignments are given to you by your administrator, you have completed this module.
    [Show full text]