Beneficial Uses of Depleted Uranium
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FT/P3-20 Physics and Engineering Basis of Multi-Functional Compact Tokamak Reactor Concept R.M.O
FT/P3-20 Physics and Engineering Basis of Multi-functional Compact Tokamak Reactor Concept R.M.O. Galvão1, G.O. Ludwig2, E. Del Bosco2, M.C.R. Andrade2, Jiangang Li3, Yuanxi Wan3 Yican Wu3, B. McNamara4, P. Edmonds, M. Gryaznevich5, R. Khairutdinov6, V. Lukash6, A. Danilov7, A. Dnestrovskij7 1CBPF/IFUSP, Rio de Janeiro, Brazil, 2Associated Plasma Laboratory, National Space Research Institute, São José dos Campos, SP, Brazil, 3Institute of Plasma Physics, CAS, Hefei, 230031, P.R. China, 4Leabrook Computing, Bournemouth, UK, 5EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK, 6TRINITI, Troitsk, RF, 7RRC “Kurchatov Institute”, Moscow, RF [email protected] Abstract An important milestone on the Fast Track path to Fusion Power is to demonstrate reliable commercial application of Fusion as soon as possible. Many applications of fusion, other than electricity production, have already been studied in some depth for ITER class facilities. We show that these applications might be usefully realized on a small scale, in a Multi-Functional Compact Tokamak Reactor based on a Spherical Tokamak with similar size, but higher fields and currents than the present experiments NSTX and MAST, where performance has already exceeded expectations. The small power outputs, 20-40MW, permit existing materials and technologies to be used. The analysis of the performance of the compact reactor is based on the solution of the global power balance using empirical scaling laws considering requirements for the minimum necessary fusion power (which is determined by the optimized efficiency of the blanket design), positive power gain and constraints on the wall load. In addition, ASTRA and DINA simulations have been performed for the range of the design parameters. -
小型飛翔体/海外 [Format 2] Technical Catalog Category
小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
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. -
Radiation Quick Reference Guide Recommend Contacting Your State Fusion Center
Domestic Nuclear Detection Office If you encounter something suspicious follow your specific local protocols. Radiation Quick Reference Guide Recommend contacting your state fusion center. DNDO is available 24/7 to assist at 1-877-DNDO-JAC / 1-877-363-6522 JAC Information Line 202-254-7179 Email: [email protected] Nuclear Concerns/ Threats 1. Nuclear Weapon - a device that releases nuclear energy in an ex- Isotopes of Concern for use in RDDs - with common uses plosive manner. Uses Highly Enriched Uranium (HEU) and/or 1. Cobalt-60 – cancer treatment, level/ Plutonium. density gauge, teletherapy, radiography, 2. Improvised Nuclear Device (IND) - a nuclear weapon fabricated food sterilization/irradiation, by a terrorist organization or rogue nation. brachytherapy 2. Iridium-192 – Radiography/non- destructive testing, flaw detection, brachy- therapy “cancer seed”, skin cancer Cobalt 60 sources Uranium “superficial” brachytherapy Plutonium 3. Uranium a. Uranium exists naturally in the earth’s crust. Of the different “isotopes” of uranium, U-235 is the one required to produce a Iridium sentinel and nuclear weapon. gamma camera b. Natural uranium contains a small amount of U-235 (<1%) which Cesium Seeds must be separated in complex extraction processes to create HEU. The predominant uranium isotope is U-238. 3. Cesium-137 - Gauge/level gauge, industrial radiography, brachyther- c. Highly Enriched Uranium (HEU) refers to uranium usable in weap- apy/teletherapy, well logging/density gauges ons due to its enrichment in U-235. 4. Strontium-90 – Radioisotope thermoelectric generator (RTG), fis- d. Approximately 25 kg of HEU is required for a nuclear weapon. sion product, industrial gauges, medical treatment e. -
Depleted Uranium: a DOE Management Challenge
Depleted Uranium: A DOE Management Challenge October 1995 U.S. Department of Energy Office of Environmental Management Office of Technology Development This report has been reproduced direcdy from die best available copy. Available to DOE and DOE Contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; prices available from (615) 576-8401. Available to die pubfic from die U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161, (703) 487-4650. Printed with soy ink on recycled paper 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. Images are produced from the best available original document. DOE/EM-0262 Depleted Uranium: A DOE Management Challenge October 1995 JSW O.STR.BUT.ON OF TH,S DOCUMENT » UNUM'TSD T U.S. -
High-Density Concrete with Ceramic Aggregate Based on Depleted Uranium Dioxide
HIGH-DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DIOXIDE S.G. Ermichev, V.I. Shapovalov, N.V.Sviridov (RFNC-VNIIEF, Sarov, Russia) V.K. Orlov, V.M. Sergeev, A. G. Semyenov, A.M. Visik, A.A. Maslov, A. V. Demin, D.D. Petrov, V.V. Noskov, V. I. Sorokin, O. I. Uferov (VNIINM, Moscow, Russia) L. Dole (ORNL, Oak Ridge, USA) Abstract - Russia is researching the production and testing of concretes with ceramic aggregate based on depleted uranium dioxide (UO2). These DU concretes are to be used as structural and radiation-shielded material for casks for A-plant spent nuclear fuel transportation and storage. This paper presents the results of studies aimed at selection of ceramics and concrete composition, justification of their production technology, investigation of mechanical properties, and chemical stability. This Project is being carried out at the A.A. Bochvar All-Russian Scientific-Research Institute of inorganic materials (VNIINM, Russia) and Russian Federal Nuclear Center – All-Russia Scientific Research Institute of Experimental Physics (RFNC-VNIIEF, Russia). This Project #2691 is financed by the International Science and Technology Center (ISTC) under collaboration of the Oak- Ridge National Laboratory (USA) I. INTRODUCTION The current practice of ensuring the required gamma conduction, thermo-, radiation and corrosion resistance, shielding and strength of metal-concrete casks is based on service life and water resistance. concrete density. For this purpose high-density rocks Specific characteristics of UO2’s chemical activity (magnetite, iron glance, barium sulfate, etc.) as well as because of its small size of particles and thus great specific scrap, scale, broken metal chips and others are introduced surface area prevent the use of traditional methods of UO2 into concrete as coarse aggregates. -
Disposal of Radioisotope Thermoelectric Generators; Problems, and How to Solve Them
DISPOSAL OF RADIOISOTOPE THERMOELECTRIC GENERATORS; PROBLEMS, AND HOW TO SOLVE THEM N.R. Kuzelev, Ye.N. Kroschkin, A.G. Kataschov - FSUE “VNIITFA”. 1. The work carried out at “VNIITFA” in 2007 The following work for disposal of RTGs was carried out at “VNIITFA” in 2007: USA - For the money allocated by the US we completed the work on developing of the database of all the RTGs located on the territory of the Russian Federation. 21 RTGs were tested in the Far East and in Kamchatka. Besides, the US coordinated the work financed by the Canadian side on decommissioning of 10 RTGs from the Tiksi Bay, as well as installation of 9 alternative power sources in the Strait of Yugorsky Schar. Canada - in accordance with the Executive Agreement with the Ministry of Foreign Affairs and International Trade of Canada 17 transportation containers for transporting RHSes were fabricated, as well as 16 sets of secure containers for transporting RTGs. The above equipment is currently being used to transport RTGs and RHSes for disposal. Norway - removal of RTGs from the coast of the Barents Sea continued with the technical assistance of Norway. Totally 21 RTGs were removed and disassembled due to the money of Norway. Currently there are no RTGs on the Kola Peninsula. Russia - for the money of the Russian Federation the work was carried out to eliminate radiation accident with the RTG at Navarin lighthouse, as well as 3 RTGs from the Baltic region were disposed of with a certain preliminary work. Inspection of 10 RTGs was carried out in Yakutia (Peleduy). -
Depleted Uranium in Bosnia and Herzegovina Revised Edition: May 2003
First published in Switzerland in 2003 by the United Nations Environment Programme. Copyright © 2003, United Nations Environment Programme. ISBN 92-1-158619-4 This publication may be reproduced in whole or in part and in any form for educational or non-profit purposes without special permission from the copyright holder, provided acknowledgement of the source is made. UNEP would appreciate receiving a copy of any publication that uses this publication as a source. No use of this publication may be made for resale or for any other commercial purpose whatsoever without prior permission in writing from the United Nations Environment Programme. United Nations Environment Programme PO Box 30552 This report by the United Nations Environment Programme was made possible Nairobi by the generous contributions of the Governments of Italy and Switzerland. Kenya Tel: +254 2 621234 Fax: +254 2 624489/90 E-mail: [email protected] Web: http://www.unep.org Further information DISCLAIMER Copies of this report may be ordered from: This revised edition includes three chapters translated into the local language. SMI (Distribution Services) Limited The contents of this volume do not necessarily reflect the views of UNEP, or contributory organizations. The P. O . B o x 1 1 9 designations employed and the presentations do not imply the expressions of any opinion whatsoever on the Stevenage part of UNEP or contributory organizations concerning the legal status of any country, territory, city or area or Hertfordshire SG1 4TP, UK its authority, or concerning the -
The Tokamak As a Neutron Source
PREPARED FOR THE U.S. DEPARTMENT OF ENERGY, UNDER CONTRACT DE-AC02-76-CHO-3073 PPPL-2656 PPPL-2656 UC-420 THE TOKAMAK AS A NEUTRON SOURCE BY H.W. HENDEL AND D.L JASSBY November 1989 PMNCITON PLASMA PHYSICS LASOffATORY PRINCETON UNIVERSITY, PRINCETON, NEW JERSEY NOTICE Available from: National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road Springfield. Virginia 22161 703-487-4650 Use the following price codes when ordering: Price: Printed Copy A04 Microfiche A01 THE TOKAMAK AS A NEUTRON SOURCE by H.W. Hendel and D.L. Jassby PPPL—2656 DE90 001821 Princeton Plasma Physics Laboratory Princeton University Princeton, N.J. 08543 ABSTRACT This paper describes the tokamak in its role as a neutron source, with emphasis on experimental results for D-D neutron production. The sections summarize tokamak operation, sources of fusion and non-fusion neutrons, principal nsutron detection methods and their calibration, neutron energy spectra and fluxes outside the tokamak plasma chamber, history of neutron production in tokamaks, neutron emission and fusion power gain from JET and TFTR (the largest present-day tokamaks), and D-T neutron production from burnup of D-D tritons. This paper also discusses the prospects for future tokamak neutron production and potential applications of tokamak neutron sources. DISCLAIMER This report was prepared as JH account or 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 for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or repre^r-s that its use would not infringe privately owned rights. -
Highly Enriched Uranium: Striking a Balance
OFFICIAL USE ONLY - DRAFT GLOSSARY OF TERMS APPENDIX F GLOSSARY OF TERMS Accountability: That part of the safeguards and security program that encompasses the measurement and inventory verification systems, records, and reports to account for nuclear materials. Assay: Measurement that establishes the total quantity of the isotope of an element and the total quantity of that element. Atom: The basic component of all matter. Atoms are the smallest part of an element that have all of the chemical properties of that element. Atoms consist of a nucleus of protons and neutrons surrounded by electrons. Atomic energy: All forms of energy released in the course of nuclear fission or nuclear transformation. Atomic weapon: Any device utilizing atomic energy, exclusive of the means for transportation or propelling the device (where such means is a separable and divisible part of the device), the principal purpose of which is for use as, or for development of, a weapon, a weapon prototype, or a weapon test device. Blending: The intentional mixing of two different assays of the same material in order to achieve a desired third assay. Book inventory: The quantity of nuclear material present at a given time as reflected by accounting records. Burnup: A measure of consumption of fissionable material in reactor fuel. Burnup can be expressed as (a) the percentage of fissionable atoms that have undergone fission or capture, or (b) the amount of energy produced per unit weight of fuel in the reactor. Chain reaction: A self-sustaining series of nuclear fission reactions. Neutrons produced by fission cause more fission. Chain reactions are essential to the functioning of nuclear reactors and weapons. -
A New Hydrogen Processing Demonstration System
A New Hydrogen Processing Demonstration System James (Jim) Klein Anita Poore Xin (Steve) Xiao Dave Babineau 35th Tritium Focus Group (TFG) Meeting Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ May 5-6, 2015 SRNL‐L2100‐2015‐00033 Overview: Compare and Contrast Tritium Process Systems Background • D (Deuterium) – Discovered in 1931 • T (Tritium) – Discovered in 1934 • Various uses for tritium • D-T Fusion Reaction – D + T = He + n + 17.59 MeV 2 Beginning Research US Cold War Defense Programs • D + T = He + n + 17.59 MeV • 1940’s during WWII – US Manhattan Project • US Nuclear Deterrent Fusion Energy • D + T = He + n + 17.59 MeV • 1950’s – US Atoms for Peace • Electric Power Generation 3 Tritium Fuel Cycle: Similar for All Uses Emissions Process Tritium Inputs Process Tritium Tritium Supply Evacuation Tritium Tritium Clean‐up Storage (impurity removal) Tritium Isotope Detritiation Separation Confinement Processing 4 Compare and Contrast Tritium Process Systems/Fuel Cycles Emissions Tritium Fuel Cycle: Similar for All Uses Process Tritium Inputs Process Tritium Tritium Supply Evacuation Tritium Tritium Clean‐up Storage (impurity removal) Tritium Isotope Detritiation Separation Confinement Processing 5 Tritium Fuel Cycle: Tritium Process • Defense Programs • EXIT Signs • ITER – Components – Glass Tubes – Tokamak Emissions Process Tritium Inputs The Illusion Process Tritium Tritium “Once the Tritium Process has been defined, all Supply Evacuation that is left to debate is what processes and Tritium Tritium Clean‐up equipment to use -
Properties of Depleted Uranium
Properties of Depleted Uranium Presentation by Thomas B. Cochran Natural Resources Defense Council At the Symposium on the Health Effects of Depleted Uranium Munitions New York June 14, 2003 Density of Selected Materials Material Density _______ __(g/cc)__ Water 1 Steel 7.8 UO2 10.96 Lead 11.35 DU 18.95 Tungsten 19.3 Uranium is Pyrophoric As it penetrates armor DU flakes off particles, i.e., powder and aerosols, that ignite spontaneously (oxidize) when sufficient oxygen is present. Oxides of DU include UO2, UO3, and U3O8. Isotopic Abundance of Uranium (weight percent) Isotope Uranium____ Natural Depleted U-238 99.2836 99.98 U-235 0.711 0.2-0.3 U-234 0.0054 0.001-0.002 Radioactive Decay 238 235 92U 92U , , 4.468 billion years 704 million years 234 231 90Th 90Th , , 24.10 days 1.0633 days 234 231 91Pa 91Pa , , 6.70 hours 32,760 years 234 92U decay chain , continues 245,400 years 230 90Th U: uranium , Th: thorium 80,000 years Pa: protactinium decay chain Subscript: protons continues Superscript: protons+neutrons Uranium Radioactivity Isotope Half-life Specific Activity (Ci/g) U-238 4.5 billion years , 0.000000336 U-235 704 million years , 0.00000216 U-234 245 400 years , 0.00622 At equilibrium (Ci/g U) Th-231 25.52 hours , same as U-235 Th-234 24.10 days , same as U-238 Pa-234 6.70 hours , same as U-238 Campared to: Cs-137 30 years , 87.0 Ci/g Ba-137m same , same as Cs-137 Radiation from Depleted Uranium (0.3 wt.% U-235) Activity (disintegrations/sec-kg) 89.4 % due to U-238 (including Th-234 and Pa-234) 1.2 % due to U-235