Properties of Selected Radioisotopes
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Strontium-90
EPA Facts about Strontium-90 What is strontium-90? The most common isotope of strontium is strontium-90. Radioactive strontium-90 is produced when uranium and plutonium undergo fission. Fission The time required for a radioactive substance to is the process in which the nucleus of a lose 50 percent of its radioactivity by decay is radionuclide breaks into smaller parts. Large known as the half-life. Strontium-90 has a half- amounts of radioactive strontium-90 were life of 29 years and emits beta particles of produced during atmospheric nuclear weapons relatively low energy as it decays. Yttrium-90, its tests conducted in the 1950s and 1960s. As a decay product, has a shorter half-life (64 hours) result of atmospheric testing and radioactive than strontium-90, but it emits beta particles of fallout, this strontium was dispersed and higher energy. deposited on the earth. How are people exposed to strontium- 90? What are the uses of strontium-90? Although external exposure to strontium-90 Strontium-90 is used in medical and agricultural from nuclear testing is of minor concern because studies. It is also used in thermoelectric devices environmental concentrations are low, that are built into small power supplies for use strontium in the environment can become part of the food chain. This pathway of exposure in remote locations, such as navigational beacons, remote weather stations, and space became a concern in the 1950s with the advent vehicles. Additionally, strontium-90 is used in of atmospheric testing of nuclear explosives. electron tubes, radioluminescent markers, as a With the suspension of atmospheric testing of radiation source in industrial thickness gauges, nuclear weapons, dietary intake has steadily and for treatment of eye diseases. -
Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel
University of Tennessee, Knoxville TRACE: Tennessee Research and Creative Exchange Masters Theses Graduate School 5-2004 Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel Jennifer L. Ladd-Lively University of Tennessee - Knoxville Follow this and additional works at: https://trace.tennessee.edu/utk_gradthes Part of the Chemical Engineering Commons Recommended Citation Ladd-Lively, Jennifer L., "Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel. " Master's Thesis, University of Tennessee, 2004. https://trace.tennessee.edu/utk_gradthes/2557 This Thesis is brought to you for free and open access by the Graduate School at TRACE: Tennessee Research and Creative Exchange. It has been accepted for inclusion in Masters Theses by an authorized administrator of TRACE: Tennessee Research and Creative Exchange. For more information, please contact [email protected]. To the Graduate Council: I am submitting herewith a thesis written by Jennifer L. Ladd-Lively entitled "Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel." I have examined the final electronic copy of this thesis for form and content and recommend that it be accepted in partial fulfillment of the equirr ements for the degree of Master of Science, with a major in Chemical Engineering. Robert M. Counce, Major Professor We have read this thesis and recommend its acceptance: Barry B. Spencer, Paul Bienkowski, Fred Weber Accepted for the Council: Carolyn R. Hodges Vice Provost and Dean of the Graduate School (Original signatures are on file with official studentecor r ds.) To the Graduate Council: I am submitting herewith a thesis written by Jennifer L. -
Calcined Bone Provides a Reliable Substrate for Strontium Isotope Ratios As Shown by an Enrichment Experiment
Research Article Received: 8 August 2014 Revised: 15 October 2014 Accepted: 16 October 2014 Published online in Wiley Online Library Rapid Commun. Mass Spectrom. 2015, 29, 107–114 (wileyonlinelibrary.com) DOI: 10.1002/rcm.7078 Calcined bone provides a reliable substrate for strontium isotope ratios as shown by an enrichment experiment Christophe Snoeck1*, Julia Lee-Thorp1,RickSchulting1,JeroendeJong2, Wendy Debouge2 and Nadine Mattielli2 1Research Laboratory for Archaeology and the History of Art, University of Oxford, Dyson Perrins Building, South Parks Rd, Oxford OX1 3QY, UK 2G-Time Laboratory, Université Libre de Bruxelles, CP 160/02, 50, Avenue F.D. Roosevelt, B-1050 Brussels, Belgium RATIONALE: Strontium isotopes (87Sr/86Sr) are used in archaeological and forensic science as markers of residence or mobility because they reflect the local geological substrate. Currently, tooth enamel is considered to be the most reliable tissue, but it rarely survives heating so that in cremations only calcined bone fragments survive. We set out to test the proposition that calcined bone might prove resistant to diagenesis, given its relatively high crystallinity, as the ability to measure in vivo 87Sr/86Sr from calcined bone would greatly extend application to places and periods in which cremation was the dominant mortuary practice, or where unburned bone and enamel do not survive. METHODS: Tooth enamel and calcined bone samples were exposed to a 87Sr-spiked solution for up to 1 year. Samples were removed after various intervals, and attempts were made to remove the contamination using acetic acid washes and ultrasonication. 87Sr/86Sr was measured before and after pre-treatment on a Nu Plasma multi-collector induced coupled plasma mass spectrometer using NBS987 as a standard. -
Ternary Fission and Quasi-Fission of Superheavy Nuclei and Giant Nuclear Systems
June 17, 2010 18:24 Proceedings Trim Size: 9in x 6in zagrebaev_¯ssion_2010b TERNARY FISSION AND QUASI-FISSION OF SUPERHEAVY NUCLEI AND GIANT NUCLEAR SYSTEMS V.I. ZAGREBAEV, A.V. KARPOV Flerov Laboratory of Nuclear Reactions, JINR, Dubna, Moscow Region, Russia WALTER GREINER Frankfurt Institute for Advanced Studies, J.W. Goethe-UniversitÄat,Germany We found that a true ternary ¯ssion with formation of a heavy third fragment (a new kind of radioactivity) is quite possible for superheavy nuclei due to the strong shell e®ects leading to a three-body clusterization with the two doubly magic tin- like cores. The three-body quasi-¯ssion process could be even more pronounced for giant nuclear systems formed in collisions of heavy actinide nuclei. In this case a three-body clusterization might be proved experimentally by detection of two coincident lead-like fragments in low-energy U+U collisions. 1. Introduction Today the term \ternary ¯ssion" is commonly used to denote the process of formation of light charged particle accompanied ¯ssion 1. This is a rare process (less than 1%) relative to binary ¯ssion, see Fig. 1. As can be seen the probability of such a process decreases sharply with increasing mass number of the accompanied third particle. These light particles are emitted almost perpendicularly with respect to the ¯ssion axis (equatorial emission) 1. It is interpreted as an indication that the light ternary particles are emitted from the neck region and are accelerated by the Coulomb ¯elds of both heavy fragments. In contrast to such a process, the term \true ternary ¯ssion" is used for a simultaneous decay of a heavy nucleus into three fragments of not very di®erent mass 1. -
THE NATURAL RADIOACTIVITY of the BIOSPHERE (Prirodnaya Radioaktivnost' Iosfery)
XA04N2887 INIS-XA-N--259 L.A. Pertsov TRANSLATED FROM RUSSIAN Published for the U.S. Atomic Energy Commission and the National Science Foundation, Washington, D.C. by the Israel Program for Scientific Translations L. A. PERTSOV THE NATURAL RADIOACTIVITY OF THE BIOSPHERE (Prirodnaya Radioaktivnost' iosfery) Atomizdat NMoskva 1964 Translated from Russian Israel Program for Scientific Translations Jerusalem 1967 18 02 AEC-tr- 6714 Published Pursuant to an Agreement with THE U. S. ATOMIC ENERGY COMMISSION and THE NATIONAL SCIENCE FOUNDATION, WASHINGTON, D. C. Copyright (D 1967 Israel Program for scientific Translations Ltd. IPST Cat. No. 1802 Translated and Edited by IPST Staff Printed in Jerusalem by S. Monison Available from the U.S. DEPARTMENT OF COMMERCE Clearinghouse for Federal Scientific and Technical Information Springfield, Va. 22151 VI/ Table of Contents Introduction .1..................... Bibliography ...................................... 5 Chapter 1. GENESIS OF THE NATURAL RADIOACTIVITY OF THE BIOSPHERE ......................... 6 § Some historical problems...................... 6 § 2. Formation of natural radioactive isotopes of the earth ..... 7 §3. Radioactive isotope creation by cosmic radiation. ....... 11 §4. Distribution of radioactive isotopes in the earth ........ 12 § 5. The spread of radioactive isotopes over the earth's surface. ................................. 16 § 6. The cycle of natural radioactive isotopes in the biosphere. ................................ 18 Bibliography ................ .................. 22 Chapter 2. PHYSICAL AND BIOCHEMICAL PROPERTIES OF NATURAL RADIOACTIVE ISOTOPES. ........... 24 § 1. The contribution of individual radioactive isotopes to the total radioactivity of the biosphere. ............... 24 § 2. Properties of radioactive isotopes not belonging to radio- active families . ............ I............ 27 § 3. Properties of radioactive isotopes of the radioactive families. ................................ 38 § 4. Properties of radioactive isotopes of rare-earth elements . -
Compilation and Evaluation of Fission Yield Nuclear Data Iaea, Vienna, 2000 Iaea-Tecdoc-1168 Issn 1011–4289
IAEA-TECDOC-1168 Compilation and evaluation of fission yield nuclear data Final report of a co-ordinated research project 1991–1996 December 2000 The originating Section of this publication in the IAEA was: Nuclear Data Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria COMPILATION AND EVALUATION OF FISSION YIELD NUCLEAR DATA IAEA, VIENNA, 2000 IAEA-TECDOC-1168 ISSN 1011–4289 © IAEA, 2000 Printed by the IAEA in Austria December 2000 FOREWORD Fission product yields are required at several stages of the nuclear fuel cycle and are therefore included in all large international data files for reactor calculations and related applications. Such files are maintained and disseminated by the Nuclear Data Section of the IAEA as a member of an international data centres network. Users of these data are from the fields of reactor design and operation, waste management and nuclear materials safeguards, all of which are essential parts of the IAEA programme. In the 1980s, the number of measured fission yields increased so drastically that the manpower available for evaluating them to meet specific user needs was insufficient. To cope with this task, it was concluded in several meetings on fission product nuclear data, some of them convened by the IAEA, that international co-operation was required, and an IAEA co-ordinated research project (CRP) was recommended. This recommendation was endorsed by the International Nuclear Data Committee, an advisory body for the nuclear data programme of the IAEA. As a consequence, the CRP on the Compilation and Evaluation of Fission Yield Nuclear Data was initiated in 1991, after its scope, objectives and tasks had been defined by a preparatory meeting. -
Inis: Terminology Charts
IAEA-INIS-13A(Rev.0) XA0400071 INIS: TERMINOLOGY CHARTS agree INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUGUST 1970 INISs TERMINOLOGY CHARTS TABLE OF CONTENTS FOREWORD ... ......... *.* 1 PREFACE 2 INTRODUCTION ... .... *a ... oo 3 LIST OF SUBJECT FIELDS REPRESENTED BY THE CHARTS ........ 5 GENERAL DESCRIPTOR INDEX ................ 9*999.9o.ooo .... 7 FOREWORD This document is one in a series of publications known as the INIS Reference Series. It is to be used in conjunction with the indexing manual 1) and the thesaurus 2) for the preparation of INIS input by national and regional centrea. The thesaurus and terminology charts in their first edition (Rev.0) were produced as the result of an agreement between the International Atomic Energy Agency (IAEA) and the European Atomic Energy Community (Euratom). Except for minor changesq the terminology and the interrela- tionships btween rms are those of the December 1969 edition of the Euratom Thesaurus 3) In all matters of subject indexing and ontrol, the IAEA followed the recommendations of Euratom for these charts. Credit and responsibility for the present version of these charts must go to Euratom. Suggestions for improvement from all interested parties. particularly those that are contributing to or utilizing the INIS magnetic-tape services are welcomed. These should be addressed to: The Thesaurus Speoialist/INIS Section Division of Scientific and Tohnioal Information International Atomic Energy Agency P.O. Box 590 A-1011 Vienna, Austria International Atomic Energy Agency Division of Sientific and Technical Information INIS Section June 1970 1) IAEA-INIS-12 (INIS: Manual for Indexing) 2) IAEA-INIS-13 (INIS: Thesaurus) 3) EURATOM Thesaurusq, Euratom Nuclear Documentation System. -
Radiological Implications of Plutonium Recycle and the Use of Thorium Fuels in Power Reactor Operations
01 RD/B/N3523 Central Electricity Generating Board Research Department Berkeley Nuclear Laboratories RADIOLOGICAL IMPLICATIONS OF PLUTONIUM RECYCLE AND THE USE OF THORIUM FUELS IN POWER REACTOR OPERATIONS By H. F. Macdonald XJ034 January 1976 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. Radiological Implications of Plutonium Recycle and the Use of Thorium Fuels in Power Reactor Operations “ by - H.F. Macdonald Approved Head of Health Physics Research Section For inclusion in Nuclear Science Abstracts SUMMARY As economically attractive sources of natural uranium are gradually depleted attention will turn to recycling plutonium or the use of thorium fuels. In this study the radiological implications of these fuel cycles in terms of fuel handling and radioactive waste disposal are investigated in 235 relation to a conventional U enriched oxide fuel. It is suggested that a comparative study of this nature may be an important aspect of the overall optimisation of future fuel cycle strategies. It is shown that the use of thorium based fuels has distinct advan tages in terms of neutron dose rates from irradiated fuels and long term a decay heating commitment compared with conventional uranium/plutonium fuels. However, this introduces a y dose rate problem in the fabrication 233 and handling of unirradiated U fuels. For both plutonium and thorium fuels these radiological problems increase during storage of the fuel prior to reactor irradiation. Finally, the novel health physics problems which arise in the handling and processing of thorium fuels are reviewed in an appendix. -
4. CHEMICAL, PHYSICAL, and RADIOLOGICAL INFORMATION
STRONTIUM 189 4. CHEMICAL, PHYSICAL, and RADIOLOGICAL INFORMATION 4.1 CHEMICAL IDENTITY Strontium is an alkaline earth element in Group IIA of the periodic table. Because of its high reactivity, elemental (or metallic) strontium is not found in nature; it exists only as molecular compounds with other elements. The chemical information for elemental strontium and some of its compounds is listed in Table 4-1. Radioactive isotopes of strontium (e.g., 89Sr and 90Sr, see Section 4.2) are the primary cause of concern with regard to human health (see Chapter 3). 4.2 PHYSICAL, CHEMICAL, AND RADIOLOGICAL PROPERTIES The physical properties of strontium metal and selected strontium compounds are listed in Table 4-2. The percent occurrence of strontium isotopes and the radiologic properties of strontium isotopes are listed in Table 4-3. Strontium can exist in two oxidation states: 0 and +2. Under normal environmental conditions, only the +2 oxidation state is stable enough to be of practical importance since it readily reacts with both water and oxygen (Cotton and Wilkenson 1980; Hibbins 1997). There are 26 isotopes of strontium, 4 of which occur naturally. The four stable isotopes, 84Sr, 86Sr, 87Sr, and 88Sr, are sometimes referred to as stable strontium. The most important radioactive isotopes, 89Sr and 90Sr, are formed during nuclear reactor operations and during nuclear explosions by the nuclear fission of 235U, 238U, or 239Pu. For example, 235U is split into smaller atomic mass fragments such as 90Sr by a nuclear chain reaction initiated by high energy neutrons of approximately 1 million electron volts (or 1 MeV). -
Measurement of Cerium in Human Breast Milk and Blood
Measurement of cerium in human breast milk and blood Vera Höllriegl, Montserrat Gonzáles-Estecha*, Elena M. Trasobares*, Augusto Giussani, Uwe Oeh, Miguel Angel Herraiz**, Bernhard Michalkea Institute of Radiation Protection and aInstitute of Ecological Chemistry, Helmholtz Zentrum München, German Research Center for Environmental Health, Ingolstädter Landstrasse 1, 85764 Neuherberg, Germany *Trace Element Unit, Department of Laboratory Medicine and **Department of Obstetrics and Gynaecology, Hospital Clinico Universitario San Carlos, 28040 Madrid, Spain Abstract The aim of this study was to evaluate the relationship between cerium content in human breast milk and blood plasma or serum and the influence due to the environmental exposure. Blood samples and breast milk at various stages of lactation, from 5 days to 51 weeks post partum, were donated by 42 healthy breast-feeding mothers from Munich, Germany and by 26 lactating Spanish mothers from Madrid at 4 weeks post partum. Inductively coupled plasma mass spectrometry was applied for the determination of cerium in the biological samples. Cerium concentration in the digested milk samples from Munich showed low values and the arithmetic mean values ranged between the quantification limit of 5 ng/L up to 65 ng/L. The median value amounted to 13 ng/L. The cerium concentrations in the Spanish breast milk samples amounted to similar low values. The data were about a factor of eight lower than values found in a former study of samples from an eastern German province. All cerium concentrations in the German plasma samples, except for two, were at the quantification limit of 10 ng/L. Interestingly, the serum samples of the Spanish mothers 1 showed cerium values ranging between 21.6 and 70.3 ng/L; these higher data could be explained by an enhanced intake of cerium by humans in Madrid. -
System Studies of Fission-Fusion Hybrid Molten Salt Reactors
University of Tennessee, Knoxville TRACE: Tennessee Research and Creative Exchange Doctoral Dissertations Graduate School 12-2013 SYSTEM STUDIES OF FISSION-FUSION HYBRID MOLTEN SALT REACTORS Robert D. Woolley University of Tennessee - Knoxville, [email protected] Follow this and additional works at: https://trace.tennessee.edu/utk_graddiss Part of the Nuclear Engineering Commons Recommended Citation Woolley, Robert D., "SYSTEM STUDIES OF FISSION-FUSION HYBRID MOLTEN SALT REACTORS. " PhD diss., University of Tennessee, 2013. https://trace.tennessee.edu/utk_graddiss/2628 This Dissertation is brought to you for free and open access by the Graduate School at TRACE: Tennessee Research and Creative Exchange. It has been accepted for inclusion in Doctoral Dissertations by an authorized administrator of TRACE: Tennessee Research and Creative Exchange. For more information, please contact [email protected]. To the Graduate Council: I am submitting herewith a dissertation written by Robert D. Woolley entitled "SYSTEM STUDIES OF FISSION-FUSION HYBRID MOLTEN SALT REACTORS." I have examined the final electronic copy of this dissertation for form and content and recommend that it be accepted in partial fulfillment of the equirr ements for the degree of Doctor of Philosophy, with a major in Nuclear Engineering. Laurence F. Miller, Major Professor We have read this dissertation and recommend its acceptance: Ronald E. Pevey, Arthur E. Ruggles, Robert M. Counce Accepted for the Council: Carolyn R. Hodges Vice Provost and Dean of the Graduate School (Original signatures are on file with official studentecor r ds.) SYSTEM STUDIES OF FISSION-FUSION HYBRID MOLTEN SALT REACTORS A Dissertation Presented for the Doctor of Philosophy Degree The University of Tennessee, Knoxville Robert D. -
RFI) DE-FOA-0002533 on Cleaning up Radioisotope Enventories (CURIE)
U.S. Department of Energy Advanced Research Projects Agency – Energy (ARPA-E) Request for Information (RFI) DE-FOA-0002533 on Cleaning Up RadioIsotope Enventories (CURIE) Introduction The purpose of this RFI is to solicit input for a potential future ARPA-E research program focused on the development of technologies that would enable the effective management of the Nation’s commercial used nuclear fuel (UNF). The goals of this RFI are to (1) solicit information about reactor fuel needs for both the current commercial light-water reactor (LWR) fleet and future advanced reactors, and (2) seek insights into technology gaps and/or cost drivers that may be hindering economical recycling of existing LWR UNF.1 This information is needed to help ARPA-E identify ways in which the Nation’s roughly 86,000 MTU2 inventory of UNF, which has been increasing by approximately 2,000 MTU per year, can best be recycled to support current and advanced reactor fuel needs. Such activities are consistent with ARPA-E’s statutory goals, which include supporting the development of transformative solutions for addressing UNF.3 ARPA-E is interested in information about technologies with the potential to make recycling UNF at least as economical, safe, and secure as the current once-through fuel cycle.4 Such technologies would enable a UNF treatment facility to be economically constructed, managed, and operated; yield an actinide product that is cost-competitive with natural uranium (U) obtained from traditional mining and milling; and generate significantly lower