Helium-3 the Energy Source of Tomorrow?
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Tritium Handling and Safe Storage
NOT MEASUREMENT SENSITIVE DOE-HDBK-1129-2007 March 2007 ____________________ DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1129-2007 This page is intentionally blank. ii DOE-HDBK-1129-2007 TABLE OF CONTENTS SECTION PAGE FOREWORD............................................................................................................................... vii ACRONYMS ................................................................................................................................ ix 1.0 INTRODUCTION ....................................................................................................................1 1.1 Purpose ...............................................................................................................................1 1.2 Scope ..................................................................................................................................1 1.3 Applicability .........................................................................................................................1 1.4 Referenced Material for Further Information .......................................................................2 2.0 TRITIUM .................................................................................................................................3 2.1 Radioactive Properties ........................................................................................................4 -
Tritium and Enriched Uranium Management Plan Through 2060
U.S. DEPARTMENT OF ENERGY Tritium And Enriched Uranium Management Plan Through 2060 Report to Congress October 2015 United States Department of Energy Washington, DC 20585 Message from the Secretary Please find the Department of Energy's plan for management oftritium and enriched uranium 1 inventories through 2060. This report is being provided to the following Members of Congress: • The Honorable Thad Cochran Chairman, Senate Committee on Appropriations • The Honorable Barbara Mikulski Ranking Member, Senate Committee on Appropriations • The Honorable Harold Rogers Chairman, House Committee on Appropriations • The Honorable Nita M. Lowey Ranking Member, House Committee on Appropriations • The Honorable Lamar Alexander Chairman, Subcommittee on Energy and Water Development Senate Committee on Appropriations • The Honorable Dianne Feinstein Ranking Member, Subcommittee on Energy and Water Development Senate Committee on Appropriations • The Honorable Mike Simpson Chairman, Subcommittee on Energy and Water Development House Committee on Appropriations • The Honorable Marcy Kaptur Ranking Member, Subcommittee on Energy and Water Development House Committee on Appropriations If you have any questions or need additional information, please contact me or Mr. Brad Crowell, Assistant Secretary for Congressional and Intergovernmental Affairs, at (202) 586-5450. Sincerely, 1 In response to Title Ill, Division D, Section 311 of the Consolidated Appropriations Act, 2014 (Pub. l. 113-76), and other Congressionalanguage l listed In Appendix B Department of Energy I October 2015 Executive Summary The Department of Energy's National Nuclear Security Administration (DOE/NNSA) is responsible for a number of national missions that require a reliable supply of Enriched Uranium (EU) to meet our defense and non-defense related missions. -
Aspects of Advanced Fuel FRC Fusion Reactors
Aspects of Advanced Fuel FRC Fusion Reactors John F Santarius and Gerald L Kulcinski Fusion Technology Institute Engineering Physics Department CT2016 Irvine, California August 22-24, 2016 [email protected]; 608-692-4128 Laundry List of Fusion Reactor Development Issues • Plasma physics of fusion fuel cycles • Engineering issues unique or more ! Cross sections and Maxwellian reactivity important for DT fuel ! Beta and B-field utilization ! Tritium-breeding blanket design ! Plasma fusion power density ! Neutron damage to materials ! Plasma energy and particle confinement ! Radiological hazard (afterheat and waste disposal) ! Neutron production vs Ti for various fuel ion ratios • Safety • Geometry implications for engineering design • Environment ! Power flows • Licensing ! Direct energy conversion ! Magnet configuration • Economics ! Radiation shielding ! Maintenance in a highly radioactive environment • Nuclear non-proliferation ! Coolant piping accessibility • Non‑electric applications • Plasma‑surface interactions • 3He fuel supply JFS 2016 Fusion Technology Institute, University of Wisconsin 2 UW Developed and/or Participated in 40 MFE & 26 IFE Power Plant and Test Facility Studies in Past 46 years MFE-40 IFE-26 JFS 2016 Fusion Technology Institute, University of Wisconsin 3 Total Fusion Reactivities for Key Fusion Fuels Total Energy Production Rate st 1 generation fuels: MaxwellianTotal Reactivities -19 D + T → n (14.07 MeV) + 4He (3.52 MeV) 10 D + D → n (2.45 MeV) + 3He (0.82 MeV) → p (3.02 MeV) + T (1.01 MeV) -20 {50% each -
OMB Control No.: 3150-0011 UNITED STATES NUCLEAR REGULATORY
OMB Control No.: 3150-0011 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS OFFICE OF NUCLEAR REACTOR REGULATION Washington, D.C. 20555-0001 October 8, 2003 NRC BULLETIN 2003-04: REBASELINING OF DATA IN THE NUCLEAR MATERIALS MANAGEMENT AND SAFEGUARDS SYSTEM Addressees All U.S. Nuclear Regulatory Commission (NRC) licensees, Agreement State licensees, and Certificate Holders (hereafter referred to as licensees) who: (1) Have in their possession, or are licensed to possess, one or more of the following: foreign obligated natural uranium, depleted uranium, or thorium; uranium enriched in the isotope U-235, U-233, plutonium, plutonium-238, or who currently have unreconciled nuclear material balances with the Nuclear Materials Management and Safeguards System (NMMSS). Purpose NRC is issuing this bulletin to: (i) Notify licensees about performance concerns associated with their reporting data to, and the resulting material balances contained in, the NMMSS database; (ii) Request affected licensees to perform a one-time reporting of the quantities of special nuclear material (SNM) and/or foreign obligated source material in their possession, specified as: (a) A quantity of SNM defined by 10 CFR 72.76, 72.78, 74.15, and 150.16, as 1 gram or more of contained uranium-235, uranium-233, plutonium, or 0.1 gram or more plutonium-238 that is greater than 10 percent of the total plutonium by weight; or (b) A quantity of foreign obligated source material (i.e., natural uranium, depleted uranium, or thorium) defined -
EPA Facts About Tritium
. p;RU:,,EPA Facts About V Tritium "~'I4C AD31 /'July 2002 What is Tritium? to the early 1960s. The inventory of tritium in the atmosphere peaked in 1963 and has been decreasing Tritium is a form of hydrogcn that is radioactive. and rapidly since then. Levels of naturally occurring tritium in like hydrogen it reacts with oxygen to form water. the atmosphere produced by cosmic rays arc constant, Tritium is produced naturally in the upper atmosphere and it is projected that levels or manmade tritium will be when cosmic rays strike atmospheric gases. Tritium comparable to natural tritium by 2030. can also be produced by man during nuclear weapon explosions, in reactors intended to produce tritium for Tritium is currently produced by reactors producing nuclear weapons. and by reactors producing electricity. However, releases of tritium from these electricity. facilities are at fractions of the natural background production rates. Other sources of tritium include government plants which have reprocessed reactor fuels. Individuals can also be exposed to tritium broken exit What arc the uses of tritium? signs and luminous dial items that contain tritium. Since tritium reacts similarly to ordinary hydrogen it is Tritium has been produced in large quantities by the incorporated into the body easily in the form of water. nuclear military program. It is also used to make luminous dials and as a source of light for sarety signs. Tritium is Overall, since current world wide levels of tritium in the used as a tracer for biochemical research, animal environment from man-made and natural sources are low, metabolism studies and ground water transport the risk to the average person from tritium is typically not measurements. -
NNSA Should Clarify Long-Term Uranium Enrichment Mission Needs and Improve Technology Cost Estimates
United States Government Accountability Office Report to Congressional Committees February 2018 NUCLEAR WEAPONS NNSA Should Clarify Long-Term Uranium Enrichment Mission Needs and Improve Technology Cost Estimates GAO-18-126 February 2018 NUCLEAR WEAPONS NNSA Should Clarify Long-Term Uranium Enrichment Mission Needs and Improve Technology Cost Highlights of GAO-18-126, a report to Estimates congressional committees Why GAO Did This Study What GAO Found NNSA has several mission needs for The National Nuclear Security Administration (NNSA), a separately organized enriched uranium, including providing agency within the Department of Energy (DOE), is taking or plans to take four LEU to fuel a nuclear reactor that actions to extend inventories of low-enriched uranium (LEU) that is unobligated, produces tritium—a key isotope used or carries no promises or peaceful use to foreign trade partners until about 2038 in nuclear weapons. NNSA has a to 2041. Two of the actions involve preserving supplies of LEU, and the other pressing defense need for unobligated two involve diluting highly enriched uranium (HEU) with lower enriched forms of LEU to fuel this reactor, meaning the uranium to produce LEU. GAO reviewed these actions and found the actual uranium, technology and equipment costs and schedules for those taken to date generally align with estimates. used to produce the LEU, must be U.S. NNSA and GAO have identified risks associated with two of these actions. One in origin. Because the United States of these risks has been resolved; NNSA is taking steps to mitigate another, while lost its only source of unobligated LEU production in 2013, the supply is finite. -
Status of ITER Neutron Diagnostic Development
INSTITUTE OF PHYSICS PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 45 (2005) 1503–1509 doi:10.1088/0029-5515/45/12/005 Status of ITER neutron diagnostic development A.V. Krasilnikov1, M. Sasao2, Yu.A. Kaschuck1, T. Nishitani3, P. Batistoni4, V.S. Zaveryaev5, S. Popovichev6, T. Iguchi7, O.N. Jarvis6,J.Kallne¨ 8, C.L. Fiore9, A.L. Roquemore10, W.W. Heidbrink11, R. Fisher12, G. Gorini13, D.V. Prosvirin1, A.Yu. Tsutskikh1, A.J.H. Donne´14, A.E. Costley15 and C.I. Walker16 1 SRC RF TRINITI, Troitsk, Russian Federation 2 Tohoku University, Sendai, Japan 3 JAERI, Tokai-mura, Japan 4 FERC, Frascati, Italy 5 RRC ‘Kurchatov Institute’, Moscow, Russian Federation 6 Euratom/UKAEA Fusion Association, Culham Science Center, Abingdon, UK 7 Nagoya University, Nagoya, Japan 8 Uppsala University, Uppsala, Sweden 9 PPL, MIT, Cambridge, MA, USA 10 PPPL, Princeton, NJ, USA 11 UC Irvine, Los Angeles, CA, USA 12 GA, San Diego, CA, USA 13 Milan University, Milan, Italy 14 FOM-Rijnhuizen, Netherlands 15 ITER IT, Naka Joint Work Site, Naka, Japan 16 ITER IT, Garching Joint Work Site, Garching, Germany E-mail: [email protected] Received 7 December 2004, accepted for publication 14 September 2005 Published 22 November 2005 Online at stacks.iop.org/NF/45/1503 Abstract Due to the high neutron yield and the large plasma size many ITER plasma parameters such as fusion power, power density, ion temperature, fast ion energy and their spatial distributions in the plasma core can be measured well by various neutron diagnostics. Neutron diagnostic systems under consideration and development for ITER include radial and vertical neutron cameras (RNC and VNC), internal and external neutron flux monitors (NFMs), neutron activation systems and neutron spectrometers. -
An Integrated Model for Materials in a Fusion Power Plant: Transmutation, Gas Production, and Helium Embrittlement Under Neutron Irradiation
Home Search Collections Journals About Contact us My IOPscience An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation This article has been downloaded from IOPscience. Please scroll down to see the full text article. 2012 Nucl. Fusion 52 083019 (http://iopscience.iop.org/0029-5515/52/8/083019) View the table of contents for this issue, or go to the journal homepage for more Download details: IP Address: 193.52.216.130 The article was downloaded on 13/11/2012 at 13:27 Please note that terms and conditions apply. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 52 (2012) 083019 (12pp) doi:10.1088/0029-5515/52/8/083019 An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation M.R. Gilbert, S.L. Dudarev, S. Zheng, L.W. Packer and J.-Ch. Sublet EURATOM/CCFE Fusion Association, Culham Centre for Fusion Energy, Abingdon, Oxfordshire OX14 3DB, UK E-mail: [email protected] Received 16 January 2012, accepted for publication 11 July 2012 Published 1 August 2012 Online at stacks.iop.org/NF/52/083019 Abstract The high-energy, high-intensity neutron fluxes produced by the fusion plasma will have a significant life-limiting impact on reactor components in both experimental and commercial fusion devices. As well as producing defects, the neutrons bombarding the materials initiate nuclear reactions, leading to transmutation of the elemental atoms. Products of many of these reactions are gases, particularly helium, which can cause swelling and embrittlement of materials. -
Formation of Hot, Stable, Long-Lived Field-Reversed Configuration Plasmas on the C-2W Device
IOP Nuclear Fusion International Atomic Energy Agency Nuclear Fusion Nucl. Fusion Nucl. Fusion 59 (2019) 112009 (16pp) https://doi.org/10.1088/1741-4326/ab0be9 59 Formation of hot, stable, long-lived 2019 field-reversed configuration plasmas © 2019 IAEA, Vienna on the C-2W device NUFUAU H. Gota1 , M.W. Binderbauer1 , T. Tajima1, S. Putvinski1, M. Tuszewski1, 1 1 1 1 112009 B.H. Deng , S.A. Dettrick , D.K. Gupta , S. Korepanov , R.M. Magee1 , T. Roche1 , J.A. Romero1 , A. Smirnov1, V. Sokolov1, Y. Song1, L.C. Steinhauer1 , M.C. Thompson1 , E. Trask1 , A.D. Van H. Gota et al Drie1, X. Yang1, P. Yushmanov1, K. Zhai1 , I. Allfrey1, R. Andow1, E. Barraza1, M. Beall1 , N.G. Bolte1 , E. Bomgardner1, F. Ceccherini1, A. Chirumamilla1, R. Clary1, T. DeHaas1, J.D. Douglass1, A.M. DuBois1 , A. Dunaevsky1, D. Fallah1, P. Feng1, C. Finucane1, D.P. Fulton1, L. Galeotti1, K. Galvin1, E.M. Granstedt1 , M.E. Griswold1, U. Guerrero1, S. Gupta1, Printed in the UK K. Hubbard1, I. Isakov1, J.S. Kinley1, A. Korepanov1, S. Krause1, C.K. Lau1 , H. Leinweber1, J. Leuenberger1, D. Lieurance1, M. Madrid1, NF D. Madura1, T. Matsumoto1, V. Matvienko1, M. Meekins1, R. Mendoza1, R. Michel1, Y. Mok1, M. Morehouse1, M. Nations1 , A. Necas1, 1 1 1 1 1 10.1088/1741-4326/ab0be9 M. Onofri , D. Osin , A. Ottaviano , E. Parke , T.M. Schindler , J.H. Schroeder1, L. Sevier1, D. Sheftman1 , A. Sibley1, M. Signorelli1, R.J. Smith1 , M. Slepchenkov1, G. Snitchler1, J.B. Titus1, J. Ufnal1, Paper T. Valentine1, W. Waggoner1, J.K. Walters1, C. -
NIAC 2011 Phase I Tarditti Aneutronic Fusion Spacecraft Architecture Final Report
NASA-NIAC 2001 PHASE I RESEARCH GRANT on “Aneutronic Fusion Spacecraft Architecture” Final Research Activity Report (SEPTEMBER 2012) P.I.: Alfonso G. Tarditi1 Collaborators: John H. Scott2, George H. Miley3 1Dept. of Physics, University of Houston – Clear Lake, Houston, TX 2NASA Johnson Space Center, Houston, TX 3University of Illinois-Urbana-Champaign, Urbana, IL Executive Summary - Motivation This study was developed because the recognized need of defining of a new spacecraft architecture suitable for aneutronic fusion and featuring game-changing space travel capabilities. The core of this architecture is the definition of a new kind of fusion-based space propulsion system. This research is not about exploring a new fusion energy concept, it actually assumes the availability of an aneutronic fusion energy reactor. The focus is on providing the best (most efficient) utilization of fusion energy for propulsion purposes. The rationale is that without a proper architecture design even the utilization of a fusion reactor as a prime energy source for spacecraft propulsion is not going to provide the required performances for achieving a substantial change of current space travel capabilities. - Highlights of Research Results This NIAC Phase I study provided led to several findings that provide the foundation for further research leading to a higher TRL: first a quantitative analysis of the intrinsic limitations of a propulsion system that utilizes aneutronic fusion products directly as the exhaust jet for achieving propulsion was carried on. Then, as a natural continuation, a new beam conditioning process for the fusion products was devised to produce an exhaust jet with the required characteristics (both thrust and specific impulse) for the optimal propulsion performances (in essence, an energy-to-thrust direct conversion). -
Fission and Fusion Can Yield Energy
Nuclear Energy Nuclear energy can also be separated into 2 separate forms: nuclear fission and nuclear fusion. Nuclear fusion is the splitting of large atomic nuclei into smaller elements releasing energy, and nuclear fusion is the joining of two small atomic nuclei into a larger element and in the process releasing energy. The mass of a nucleus is always less than the sum of the individual masses of the protons and neutrons which constitute it. The difference is a measure of the nuclear binding energy which holds the nucleus together (Figure 1). As figures 1 and 2 below show, the energy yield from nuclear fusion is much greater than nuclear fission. Figure 1 2 Nuclear binding energy = ∆mc For the alpha particle ∆m= 0.0304 u which gives a binding energy of 28.3 MeV. (Figure from: http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html ) Fission and fusion can yield energy Figure 2 (Figure from: http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html) Nuclear fission When a neutron is fired at a uranium-235 nucleus, the nucleus captures the neutron. It then splits into two lighter elements and throws off two or three new neutrons (the number of ejected neutrons depends on how the U-235 atom happens to split). The two new atoms then emit gamma radiation as they settle into their new states. (John R. Huizenga, "Nuclear fission", in AccessScience@McGraw-Hill, http://proxy.library.upenn.edu:3725) There are three things about this induced fission process that make it especially interesting: 1) The probability of a U-235 atom capturing a neutron as it passes by is fairly high. -
Neutronic Model of a Fusion Neutron Source
STATIC NEUTRONIC CALCULATION OF A FUSION NEUTRON SOURCE S.V. Chernitskiy1, V.V. Gann1, O. Ågren2 1“Nuclear Fuel Cycle” Science and Technology Establishment NSC KIPT, Kharkov, Ukraine; 2Uppsala University, Ångström Laboratory, Uppsala, Sweden The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellarator- mirror trap. Calculation results for the neutron flux and spectrum inside the first wall are presented. Heat load and irradiation damage on the first wall are calculated. PACS: 52.55.Hc, 52.50.Dg INTRODUCTION made in Ref. [5] indicates that under certain conditions Powerful sources of fusion neutrons from D-T nested magnetic surfaces could be created in a reaction with energies ~ 14 MeV are of particular stellarator-mirror machine. interest to test suitability of materials for use in fusion Some fusion neutrons are generated outside the reactors. Developing materials for fusion reactors has main part near the injection point. There is a need of long been recognized as a problem nearly as difficult protection from these neutrons. and important as plasma confinement, but it has The purpose is to calculate the neutron spectrum received only a fraction of attention. The neutron flux in inside neutron exposing zone of the installation and a fusion reactor is expected to be about 50-100 times compute the radial leakage of neutrons through the higher than in existing pressurized water reactors. shield. Furthermore, the high-energy neutrons will produce Another problem studied in the paper concerns to hydrogen and helium in various nuclear reactions that the determination of the heat load and irradiation tend to form bubbles at grain boundaries of metals and damage of the first wall of the device, where will be a result in swelling, blistering or embrittlement.