Tritium (Hydrogen-3)
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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 -
Chapter 1.2: Transformation Kinetics
Chapter 1: Radioactivity Chapter 1.2: Transformation Kinetics 200 NPRE 441, Principles of Radiation Protection Chapter 1: Radioactivity http://www.world‐nuclear.org/info/inf30.html 201 NPRE 441, Principles of Radiation Protection Chapter 1: Radioactivity Serial Transformation In many situations, the parent nuclides produce one or more radioactive offsprings in a chain. In such cases, it is important to consider the radioactivity from both the parent and the daughter nuclides as a function of time. • Due to their short half lives, 90Kr and 90Rb will be completely transformed, results in a rapid building up of 90Sr. • 90Y has a much shorter half‐life compared to 90Sr. After a certain period of time, the instantaneous amount of 90Sr transformed per unit time will be equal to that of 90Y. •Inthiscase,90Y is said to be in a secular equilibrium. 202 NPRE 441, Principles of Radiation Protection Chapter 1: Radioactivity Exponential DecayTransformation Kinetics • Different isotopes are characterized by their different rate of transformation (decay). • The activity of a pure radionuclide decreases exponentially with time. For a given sample, the number of decays within a unit time window around a given time t is a Poisson random variable, whose expectation is given by t Q Q0e •Thedecayconstant is the probability of a nucleus of the isotope undergoing a decay within a unit period of time. 203 NPRE 441, Principles of Radiation Protection Chapter 1: Radioactivity Why Exponential Decay? The decay rate, A, is given by Separate variables in above equation, we have The decay constant is the probability of a nucleus of the isotope undergoing a decay within a unit period of time. -
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. -
Experimental Γ Ray Spectroscopy and Investigations of Environmental Radioactivity
Experimental γ Ray Spectroscopy and Investigations of Environmental Radioactivity BY RANDOLPH S. PETERSON 216 α Po 84 10.64h. 212 Pb 1- 415 82 0- 239 β- 01- 0 60.6m 212 1+ 1630 Bi 2+ 1513 83 α β- 2+ 787 304ns 0+ 0 212 α Po 84 Experimental γ Ray Spectroscopy and Investigations of Environmental Radioactivity Randolph S. Peterson Physics Department The University of the South Sewanee, Tennessee Published by Spectrum Techniques All Rights Reserved Copyright 1996 TABLE OF CONTENTS Page Introduction ....................................................................................................................4 Basic Gamma Spectroscopy 1. Energy Calibration ................................................................................................... 7 2. Gamma Spectra from Common Commercial Sources ........................................ 10 3. Detector Energy Resolution .................................................................................. 12 Interaction of Radiation with Matter 4. Compton Scattering............................................................................................... 14 5. Pair Production and Annihilation ........................................................................ 17 6. Absorption of Gammas by Materials ..................................................................... 19 7. X Rays ..................................................................................................................... 21 Radioactive Decay 8. Multichannel Scaling and Half-life ..................................................................... -
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 -
Tritium Immobilization and Packaging Using Metal Hydrides
AECL-71S1 ATOMIC ENERGY flPnSy L'ENERGIE ATOMIQUE OF CANADA LIMITED V^^JP DU CANADA LIMITEE TRITIUM IMMOBILIZATION AND PACKAGING USING METAL HYDRIDES Immobilisation et emballage du tritium au moyen d'hydrures de meta! W.J. HOLTSLANDER and J.M. YARASKAVITCH Chalk River Nuclear Laboratories Laboratoires nucl6aires de Chalk River Chalk River, Ontario April 1981 avril ATOMIC ENERGY OF CANADA LIMITED Tritium Immobilization and Packaging Using Metal Hydrides by W.J. Holtslander and J.M. Yaraskavitch Chemical Engineering Branch Chalk River Nuclear Laboratories Chalk River, Ontario KOJ 1J0 1981 April AECL-7151 L'ENERGIE ATOMIQUE DU CANADA, LIMITEE Immo ;ilisation et emballage du tritium au moyen d'hydrures de mëtâT par W.J. Holtslander et J.M. Yaraskavitch Résumé Le tritium provenant des réacteurs CANDU â eau lourde devra être emballé et stocké de façon sûre. Il sera récupéré sous la forme élémentaire T2. Les tritiures de métal sont des composants efficaces pour immobiliser le tritium comme solide non réactif stable et ils peuvent en contenir beaucoup. La technologie nécessaire pour préparer les hydrures des métaux appropriés, comme le titane et le zirconium,a été développée et les propriétés des matériaux préparés ont été évaluées. La conception des emballages devant contenir les tritiures de métal, lors du transport et durant le stockage à long terme, est terminée et les premiers essais ont commencé. Département de génie chimique Laboratoires nucléaires de Chalk River Chalk River, Ontario KOJ 1J0 Avril 1981 AECL-7151 ATOMIC ENERGY OF CANADA LIMITED Tritium Immobilization and Packaging Using Metal Hydrides by W.J. Holtslander and J.M. -
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. -
Nuclide Safety Data Sheet Iron-59
59 Nuclide Safety Data Sheet 59 Iron-59 Fe www.nchps.org Fe I. PHYSICAL DATA 1 Gammas/X-rays: 192 keV (3% abundance); 1099 keV (56%), 1292 keV (44%) Radiation: 1 Betas: 131 keV (1%), 273 keV (46%), 466 keV (53%) 2 Gamma Constant: 0.703 mR/hr per mCi @ 1.0 meter [1.789E-4 mSv/hr per MBq @ 1.0 meter] 1 Half-Life [T½] : Physical T½: 44.5 day 3 Biological T½: ~1.7 days (ingestion) ; much longer for small fraction Effective T½: ~1.7 days (varies; also small fraction retained much longer) Specific Activity: 4.97E5 Ci/g [1.84E15 Bq/g] max.1 II. RADIOLOGICAL DATA Radiotoxicity4: 1.8E-9 Sv/Bq (67 mrem/uCi) of 59Fe ingested [CEDE] 4.0E-9 Sv/Bq (150 mrem/uCi) of 59Fe inhaled [CEDE] Critical Organ: Spleen1, [blood] Intake Routes: Ingestion, inhalation, puncture, wound, skin contamination (absorption); Radiological Hazard: Internal Exposure; Contamination III. SHIELDING Half Value Layer [HVL] Tenth Value Layer [TVL] Lead [Pb] 15 mm (0.59 inches) 45 mm (1.8 inches) Steel 35 mm (1.4 inches) 91 mm (3.6 inches) The accessible dose rate should be background but must be < 2 mR/hr IV. DOSIMETRY MONITORING - Always wear radiation dosimetry monitoring badges [body & ring] whenever handling 59Fe V. DETECTION & MEASUREMENT Portable Survey Meters: Geiger-Mueller [e.g. PGM] to assess shielding effectiveness & contamination Wipe Test: Liquid Scintillation Counter, Gamma Counter VI. SPECIAL PRECAUTIONS • Avoid skin contamination [absorption], ingestion, inhalation, & injection [all routes of intake] • Use shielding (lead) to minimize exposure while handling of 59Fe • Use tools (e.g. -
Hydrogen Is a Friend, Or an Enemy, of the Environment?
Energy Research Journal Original Research Paper Hydrogen is a Friend, or an Enemy, of the Environment? 1Relly Victoria Virgil Petrescu, 2Raffaella Aversa, 3Taher M. Abu-Lebdeh, 2 1 Antonio Apicella and Florian Ion Tiberiu Petrescu 1ARoTMM-IFToMM, Bucharest Polytechnic University, Bucharest, (CE), Romania 2Advanced Material Lab, Department of Architecture and Industrial Design, Second University of Naples, 81031 Aversa (CE), Italy 3North Carolina A and T State University, USA Article history Abstract: Hydrogen is the best friend of man and the environment. Received: 08-02-2018 Actually, it is the core element from that can extract energy, at infinity, Revised: 15-03-2018 in various forms. Until now has not been sufficiently exploited, but Accepted: 17-03-2018 once with the evolution of the human species is the time to start to pool all types of energy which the hydrogen and its isotopes may donate Corresponding Author: Florian Ion Tiberiu Petrescu them to us. Obviously the most abundant are nuclear energies which ARoTMM-IFToMM, Bucharest may be extracted from the hydrogen, either by well-known reaction of Polytechnic University, fission or through the much-desired fusion. In the reaction of a merger Bucharest, (CE), Romania Deuterium-Tritium, for example, the energy required to overcome the E-mail: [email protected] Coulomb barrier is 0.1 MeV. Conversion between the energy and the [email protected] temperature shows that the barrier of 0.1 MeV would be exceeded at a temperature of over 1.2 billion Kelvin degrees. According to the static calculations required a temperature of fusion to warm temperature is about 4 billion degrees. -
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. -
Tritium, Carbon-14 and Krypton-85
Tritium, carbon-14 and krypton-85 Jan Willem Storm van Leeuwen Independent consultant member of the Nuclear Consulting Group August 2019 [email protected] Note In this document the references are coded by Q-numbers (e.g. Q6). Each reference has a unique number in this coding system, which is consistently used throughout all publications by the author. In the list at the back of the document the references are sorted by Q-number. The resulting sequence is not necessarily the same order in which the references appear in the text. m42H3C14Kr85-20190828 1 Contents 1 Introduction 2 Tritium 3H Hydrogen isotopes Anthropogenic tritium production Chemical properties DNA incorporation Health hazards Removal and disposal of tritium 3 Carbon-14 Carbon isotopes Anthropogenic carbon-14 production Chemical properties DNA incorporation Suess effect Health hazards Removal and disposal of carbon-14 4 Krypton-85 Anthropogenic kry[ton-85 production Chemical properties Biological properties Health hazards Removal and disposal of krypton-85 References TABLES Table 1 Neutron reactions producing tritium and precursors Table 2 Calculated production and discharge rates of tritium Table 3 Neutron reactions producing carbon-14 and precursors Table 4 Calculated production and discharge rates of carbon-14 Table 5 Calculated production and discharge rates of krypton-85 FIGURES Figure 1 Pathways of tritium and carbon-14 into human metabolism m42H3C14Kr85-20190828 2 1 Introduction The three radionuclides tritium (3H), carbon-14 (14C) and krypton-85 (85Kr) are routinely released into the human environment by nominally operating nuclear power plants. According to the classical dose-risk paradigm these discharges would have negligible public health effects and so were and still are permitted.