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Spent Nuclear Fuel Pools in the US
Spent Nuclear Fuel Pools in the U.S.: Reducing the Deadly Risks of Storage front cover WITH SUPPORT FROM: WITH SUPPORT FROM: By Robert Alvarez 1112 16th St. NW, Suite 600, Washington DC 20036 - www.ips-dc.org May 2011 About the Author Robert Alvarez, an Institute for Policy Studies senior scholar, served as a Senior Policy Advisor to the Secre- tary of Energy during the Clinton administration. Institute for Policy Studies (IPS-DC.org) is a community of public scholars and organizers linking peace, justice, and the environment in the U.S. and globally. We work with social movements to promote true democracy and challenge concentrated wealth, corporate influence, and military power. Project On Government Oversight (POGO.org) was founded in 1981 as an independent nonprofit that investigates and exposes corruption and other misconduct in order to achieve a more effective, accountable, open, and ethical federal government. Institute for Policy Studies 1112 16th St. NW, Suite 600 Washington, DC 20036 http://www.ips-dc.org © 2011 Institute for Policy Studies [email protected] For additional copies of this report, see www.ips-dc.org Table of Contents Summary ...............................................................................................................................1 Introduction ..........................................................................................................................4 Figure 1: Explosion Sequence at Reactor No. 3 ........................................................4 Figure 2: Reactor No. 3 -
Breeder Reactors: a Renewable Energy Source Bernard L
Am. J. Phys. 51(1), Jan. 1983 Breeder reactors: A renewable energy source Bernard L. Cohen Department of Physics. University of Pittsburgh, Pittsburgh, Pennsylvania 15260 Since energy sources derived from the sun are called “renew- giving an equilibrium Q = S/8. Assuming that equilibrium has been able,” that adjective apparently means that they will be available in reached, 8–1 = Q/S = (4.6×109 tonne)/ (3.2×104 tonne/yr) = 140 000 undiminished quantity at present costs for as long as the current yr. Since this is such a short time geologically, it is reasonable to relationship between the sun and Earth persists, about 5 billion assume that equilibrium has been reached, and that the value of Q years. It is the purpose of this note to show that breeder reactors at t = 0 is immaterial to the discussion. Moreover, the fact that 8–1 using nuclear fission fulfill this definition of a renewable energy is so much longer than the time for dilution of material through the source, and in fact can supply all the world’s energy needs at world’s oceans, less than 1000 yr,5 means that nonuniformity of present costs for that time period. uranium concentration is not a long-term problem. The world’s uranium resources are sufficient to fuel light-water If we were to withdraw uranium at a rate R, the differential reactors for only a few tens of years, and since uranium is used equation for Q would become about 100 times more efficiently as an energy source in breeder dQ/dt = S – R – 8Q, 8 reactors than in light-water reactors, it is frequently said that the leading to an equilibrium Q = (S – R)/ = Q00(1 – R/S), where Q is amount of uranium available can support the world’s energy needs the present value of Q. -
Table 2.Iii.1. Fissionable Isotopes1
FISSIONABLE ISOTOPES Charles P. Blair Last revised: 2012 “While several isotopes are theoretically fissionable, RANNSAD defines fissionable isotopes as either uranium-233 or 235; plutonium 238, 239, 240, 241, or 242, or Americium-241. See, Ackerman, Asal, Bale, Blair and Rethemeyer, Anatomizing Radiological and Nuclear Non-State Adversaries: Identifying the Adversary, p. 99-101, footnote #10, TABLE 2.III.1. FISSIONABLE ISOTOPES1 Isotope Availability Possible Fission Bare Critical Weapon-types mass2 Uranium-233 MEDIUM: DOE reportedly stores Gun-type or implosion-type 15 kg more than one metric ton of U- 233.3 Uranium-235 HIGH: As of 2007, 1700 metric Gun-type or implosion-type 50 kg tons of HEU existed globally, in both civilian and military stocks.4 Plutonium- HIGH: A separated global stock of Implosion 10 kg 238 plutonium, both civilian and military, of over 500 tons.5 Implosion 10 kg Plutonium- Produced in military and civilian 239 reactor fuels. Typically, reactor Plutonium- grade plutonium (RGP) consists Implosion 40 kg 240 of roughly 60 percent plutonium- Plutonium- 239, 25 percent plutonium-240, Implosion 10-13 kg nine percent plutonium-241, five 241 percent plutonium-242 and one Plutonium- percent plutonium-2386 (these Implosion 89 -100 kg 242 percentages are influenced by how long the fuel is irradiated in the reactor).7 1 This table is drawn, in part, from Charles P. Blair, “Jihadists and Nuclear Weapons,” in Gary A. Ackerman and Jeremy Tamsett, ed., Jihadists and Weapons of Mass Destruction: A Growing Threat (New York: Taylor and Francis, 2009), pp. 196-197. See also, David Albright N 2 “Bare critical mass” refers to the absence of an initiator or a reflector. -
The Nuclear Waste Primer September 2016 What Is Nuclear Waste?
The Nuclear Waste Primer September 2016 What is Nuclear Waste? Nuclear waste is the catch-all term for anything contaminated with radioactive material. Nuclear waste can be broadly divided into three categories: • Low-level waste (LLW), comprised of protective clothing, medical waste, and other lightly-contaminated items • Transuranic waste (TRU), comprised of long-lived isotopes heavier than uranium • High-level waste (HLW), comprised of spent nuclear fuel and other highly-radioactive materials Low-level waste is relatively short-lived and easy to handle. Currently, four locations for LLW disposal exist in the United States. Two of them, Energy Solutions in Clive, Utah and Waste Control Specialists in Andrews, Texas, accept waste from any U.S. state. Transuranic waste is often a byproduct of nuclear weapons production and contains long-lived radioactive elements heavier than uranium, like plutonium and americium. Currently, the U.S. stores TRU waste at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. High-level waste includes spent nuclear fuel and the most radioactive materials produced by nuclear weapons production. Yucca Mountain is the currently designated high-level waste repository for the United States. 1 | What is Spent Nuclear Fuel? Spent nuclear fuel (SNF), alternatively referred to as used nuclear fuel, is the primary byproduct of nuclear reactors. In commercial power reactors in the U.S., fuel begins as uranium oxide clad in a thin layer of zirconium-aluminum cladding. After several years inside of the reactor, around fi ve percent of the uranium has been converted in some way, ranging from short-lived and highly radioactive fi ssion products to long-lived actinides like plutonium, americium, and neptunium. -
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. -
Development of an On-Line Fuel Failure Monitoring System For
DEVELOPMENT OF AN ON-LINE FUEL FAILURE MONITORING SYSTEM FOR CANDU REACTORS DEVELOPPEMENT D'UN SYSTEME DE SURVEILLANCE EN LIGNE POUR DES RUPTURES DE GAINES DES REACTEURS CANDU A Thesis Submitted to the Division of Graduate Studies of the Royal Military College of Canada by Stephen Jason Livingstone, BSc, MSc Sub-Lieutenant In Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy March 2012 ©This thesis may be used within the Department of National Defence but copyright for open publication remains the property of the author. Library and Archives Bibliotheque et Canada Archives Canada Published Heritage Direction du Branch Patrimoine de I'edition 395 Wellington Street 395, rue Wellington Ottawa ON K1A0N4 Ottawa ON K1A 0N4 Canada Canada Your file Votre reference ISBN: 978-0-494-83407-7 Our file Notre reference ISBN: 978-0-494-83407-7 NOTICE: AVIS: The author has granted a non L'auteur a accorde une licence non exclusive exclusive license allowing Library and permettant a la Bibliotheque et Archives Archives Canada to reproduce, Canada de reproduire, publier, archiver, publish, archive, preserve, conserve, sauvegarder, conserver, transmettre au public communicate to the public by par telecommunication ou par Plnternet, preter, telecommunication or on the Internet, distribuer et vendre des theses partout dans le loan, distrbute and sell theses monde, a des fins commerciales ou autres, sur worldwide, for commercial or non support microforme, papier, electronique et/ou commercial purposes, in microform, autres formats. paper, electronic and/or any other formats. The author retains copyright L'auteur conserve la propriete du droit d'auteur ownership and moral rights in this et des droits moraux qui protege cette these. -
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. -
Radiation Hazard Location
Radiation Hazard Location Radiation Detector JS Stanley US Patent 8,399.859 B2 March 19, 2013 Using semi spherical PRESAGE with a lead collimator to detect contaminated Hot Cells Improving the Presage Polymer Radiosensitivity for Hot Cell and Glovebox 3D Characterization Adamovics, John; Farfan, Eduardo B.; Coleman, J. Rusty Health Physics (2013), 104(1), 63-67. RadBall is a novel, passive, radiation detection device that provides 3D mapping of radiation from areas where measurements have not been possible previously due to lack of access or extremely high radiation doses. This kind of technol. is beneficial when decommissioning and decontamination of nuclear facilities occur. The key components of the RadBall technol. include a tungsten outer shell that houses a radiosensitive PRESAGE polymer. The 1.0-cm-thick tungsten shell has a no. of holes that allow photons to reach the polymer, thus generating radiation tracks that are analyzed. Submerged RadBall Deployments in Hanford Site Hot Cells Containing 137CsCl Capsules Farfan, Eduardo B.; Coleman, J. Rusty; Stanley, Steven; Adamovics, John; Oldham, Mark; Thomas, Andrew Health Physics 103:100-106 (2012) The overall objective of this study was to demonstrate that a new technol., known as RadBall, could locate submerged radiol. hazards. RadBall is a novel, passive, radiation detection device that provides a 3-D visualization of radiation from areas where measurements have not been previously possible due to lack of access or extremely high radiation doses. This technol. has been under development during recent years, and all of its previous tests have included dry deployments. This study involved, for the first time, underwater RadBall deployments in hot cells contg. -
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. -
Radiological Basics
Transportation Emergency Preparedness Program MERRTT Radiological Basics INTRODUCTION The reliance upon, and use of, radioactive material in agriculture, notesnotes industry, and medicine continues to increase. As the manufacture, notesnotes use, and disposal of radioactive material has increased, so has the need to transport it. Consequently, the potential for you as a responder to encounter an incident involving some type of radioactive material has increased. Having knowledge of radiological hazards, and the terminology used to describe them, will increase your ability to quickly recognize, safely respond, and accurately relay information during an incident involving radioactive material. PURPOSE Upon completion of this module, you will have a better understanding of the basic structure of an atom and the fundamentals of radiation. MODULE OBJECTIVES Upon completion of this module, you will be able to: 1. Identify the basic components of an atom. 2. Define ionizing radiation, radioactivity, radioactive material, and radioactive contamination. 3. Distinguish between radiation and contamination. 4. Identify some commonly transported sources of radioactive material. 01/05 rev. 3 2-1 Transportation Emergency Preparedness Program MERRTT Radiological Basics BACKGROUND notesnotes Radiation is all around us and has been present since the birth of notesnotes this planet. Today, both man-made and natural radioactive material are part of our daily lives. We use radioactive material for beneficial purposes, such as generating electricity and diagnosing and treating medical conditions. Radiation is used in many ways to improve our health and the quality of our lives. In 1895, while working in his laboratory, Wilhelm Roentgen discovered a previously unknown phenomenon: rays that could penetrate solid objects. -
Study of Macromolecule-Mineral Interactions on Nuclear Related Materials
Study of macromolecule-mineral interactions on nuclear related materials by Lygia Eleftheriou Submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy Supervised by: Prof John Harding Dr Maria Romero-González The University of Sheffield Faculty of Engineering Department of Materials Science and Engineering September 2016 Declaration The work described within this thesis has been completed under the supervision of Prof J. Harding and Dr M. Romero-González at the University of Sheffield between September 2012 and September 2016. This thesis along with the work described here has been completed by the author with some exceptions indicated clearly at the relevant chapters. These include: (1) the construction of ceria models for the computational work that was completed by Dr Colin Freeman and Dr Shaun Hall (described in chapter 5), (2) the purification of peptidoglycan completed by Dr Stephane Mesnage (described in chapter 4) and (3) the electron microscopy analysis completed by Dr Mohamed Merroun (described in chapter 2). Lygia Eleftheriou September 2016 Acknowledgements I would like to express my sincere gratitude to my supervisors Dr Maria Romero González and Prof John Harding for all their support during the past four years. This work would not have been possible without their endless encouragement, guidance and advice. I would also like to thank Dr Colin Freeman, Dr Shaun Hall and Riccardo Innocenti Malini for all the hours they spent trying to make things work and all their help with the computational part of this project. In addition, I would like to thank Dr Simon Thorpe, Dr Stephane Mesnage and Mr Robert Hanson for their help with the analytical methods of this project. -
An Introduction to Nuclear Power – Science, Technology and UK
sustainable development commission The role of nuclear power in a low carbon economy Paper 1: An introduction to nuclear power – science, technology and UK policy context An evidence-based report by the Sustainable Development Commission March 2006 Table of contents 1 INTRODUCTION ................................................................................................................................. 3 2 ELECTRICITY GENERATION ................................................................................................................. 4 2.1 Nuclear electricity generation ................................................................................................. 4 2.2 Fission – how does it work?..................................................................................................... 4 2.3 Moderator ................................................................................................................................. 5 2.4 Coolant...................................................................................................................................... 5 2.5 Radioactivity ............................................................................................................................. 6 3 THE FUEL CYCLE: FRONT END ............................................................................................................ 7 3.1 Mining and milling ................................................................................................................... 7 3.2 Conversion and