Partitioning and Transmutation Current Developments – 2004 a Report from the Swedish Reference Group on P&T-Research
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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. -
Nuclear Transmutation Strategies for Management of Long-Lived Fission
PRAMANA c Indian Academy of Sciences Vol. 85, No. 3 — journal of September 2015 physics pp. 517–523 Nuclear transmutation strategies for management of long-lived fission products S KAILAS1,2,∗, M HEMALATHA2 and A SAXENA1 1Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai 400 085, India 2UM–DAE Centre for Excellence in Basic Sciences, Mumbai 400 098, India ∗Corresponding author. E-mail: [email protected] DOI: 10.1007/s12043-015-1063-z; ePublication: 27 August 2015 Abstract. Management of long-lived nuclear waste produced in a reactor is essential for long- term sustenance of nuclear energy programme. A number of strategies are being explored for the effective transmutation of long-lived nuclear waste in general, and long-lived fission products (LLFP), in particular. Some of the options available for the transmutation of LLFP are discussed. Keywords. Nuclear transmutation; long-lived fission products; (n, γ ) cross-section; EMPIRE. PACS Nos 28.41.Kw; 25.40.Fq; 24.60.Dr 1. Introduction It is recognized that for long-term energy security, nuclear energy is an inevitable option [1]. For a sustainable nuclear energy programme, the management of long-lived nuclear waste is very critical. Radioactive nuclei like Pu, minor actinides like Np, Am and Cm and long-lived fission products like 79Se, 93Zr, 99Tc, 107Pd, 126Sn, 129I and 135Cs constitute the main waste burden from a power reactor. In this paper, we shall discuss the management strategies for nuclear waste in general, and long-lived fission products, in particular. 2. Management of nuclear waste The radioactive nuclei which are produced in a power reactor and which remain in the spent fuel of the reactor form a major portion of nuclear waste. -
Plasma–Material Interactions in Current Tokamaks and Their Implications for Next Step Fusion Reactors
Plasma–material interactions in current tokamaks and their implications for next step fusion reactors G. Federicia ITER Garching Joint Work Site, Garching, Germany C.H. Skinnerb Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey, USA J.N. Brooksc Argonne National Laboratory, Argonne, Illinois, USA J.P. Coad JET Joint Undertaking, Abingdon, United Kingdom C. Grisolia Tore Supra, CEA Cadarache, St.-Paul-lez-Durance, France A.A. Haaszd University of Toronto, Institute for Aerospace Studies, Toronto, Ontario, Canada A. Hassaneine Argonne National Laboratory, Argonne, Illinois, USA V. Philipps Institut f¨ur Plasmaphysik, Forschungzentrum J¨ulich, J¨ulich, Germany C.S. Pitcherf MIT Plasma Science and Fusion Center, Cambridge, Massachusetts, USA J. Roth Max-Planck-Institut f¨ur Plasmaphysik, Garching, Germany W.R. Wamplerg Sandia National Laboratories, Albuquerque, New Mexico, USA D.G. Whyteh University of California, San Diego, La Jolla, California, USA Nuclear Fusion, Vol. 41, No. 12R c 2001, IAEA, Vienna 1967 Contents 1. Introduction/background ........................................................................1968 1.1. Introduction....................................................................................1968 1.2. Plasma edge parameters and plasma–material interactions . 1969 1.3. History of plasma facing materials . 1973 2. Plasma edge and plasma–material interaction issues in next step tokamaks . 1977 2.1. Introduction....................................................................................1977 2.2. Progress towards a next step fusion device. .1977 2.3. Most prominent plasma–material interaction issues for a next step fusion device . 1980 2.4. Selection criteria for plasma facing materials. .1995 2.5. Overview of design features of plasma facing components for next step tokamaks. .1998 3. Review of physical processes and underlying theory ..........................................2002 3.1. Introduction....................................................................................2002 3.2. -
Security of Supply of Medical Radioisotopes - a Clinical View Dr Beverley Ellis Consultant Radiopharmacist
Security of Supply of Medical Radioisotopes - a clinical view Dr Beverley Ellis Consultant Radiopharmacist Nuclear Medicine Centre Manchester University NHS Foundation Trust Nuclear Medicine § Approx 35 million clinical radionuclide imaging procedures worldwide § Globally 2nd most common imaging technique after CT (higher than MR) 20 million in USA 9 million in Europe 3 million in Japan 3 million in rest of the world Approx 700, 000 nuclear medicine procedures per year in UK Myocardial Perfusion - Ischaemia Stress Stress SA Rest Stress VLA Rest Stress HLA Rest Rest Tc-99m Bone Scans Normal Metastases Mo-99/Tc-99m Generator Supply Tc-99m Radiopharmaceutical Production Mo-99 Shortages Design of Clinical Services to Reduce Tc-99m Use § Optimisation of generator management – Efficiency savings – Delivery and extraction schedules – Patient scheduling § Improved communication – Customers – Suppliers § Improved software – gamma cameras – Produce comparable quality images using less radioactivity Global Situation § OECD/Nuclear Energy Agency (NEA) – Set up High Level Group (HLG-MR) in 2009 – Security of supply of Mo-99 and Tc-99m – Established 6 principles e.g. full cost recovery and outage reserve capacity – Issued a series of publications Global Situation § AIPES (Association of Imaging Producers & Equipment supplies) (Now called Nuclear Medicine Europe) – Support coordination of research reactor schedules Global Situation § Increased Mo-99 Production Capacity – Mo-99 suppliers – acquire additional capacity to cover shortfalls (Outage -
The Supply of Medical Isotopes
The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS This work is published under the responsibility of the Secretary-General of the OECD. The opinions expressed and arguments employed herein do not necessarily reflect the official views of OECD member countries. This document, as well as any data and any map included herein, are without prejudice to the status of or sovereignty over any territory, to the delimitation of international frontiers and boundaries and to the name of any territory, city or area. Please cite this publication as: OECD/NEA (2019), The Supply of Medical Isotopes: An Economic Diagnosis and Possible Solutions, OECD Publishing, Paris, https://doi.org/10.1787/9b326195-en. ISBN 978-92-64-94550-0 (print) ISBN 978-92-64-62509-9 (pdf) The statistical data for Israel are supplied by and under the responsibility of the relevant Israeli authorities. The use of such data by the OECD is without prejudice to the status of the Golan Heights, East Jerusalem and Israeli settlements in the West Bank under the terms of international law. Photo credits: Cover © Yok_onepiece/Shutterstock.com. Corrigenda to OECD publications may be found on line at: www.oecd.org/about/publishing/corrigenda.htm. © OECD 2019 You can copy, download or print OECD content for your own use, and you can include excerpts from OECD publications, databases and multimedia products in your own documents, presentations, blogs, websites and teaching materials, provided that suitable acknowledgement of OECD as source and copyright owner is given. -
Rational Ligand Design for U(VI) and Pu(IV)* by Géza Szigethy BA
Rational Ligand Design for U(VI) and Pu(IV)* by Géza Szigethy B.A. (Princeton University), 2004 A dissertation submitted in partial satisfaction of the requirements for the degree of Doctor of Philosophy in Chemistry in the Graduate Division of the University of California, Berkeley Committee in charge: Professor Kenneth N. Raymond, Chair Professor Richard A. Andersen Professor Garrison Sposito Fall 2009 * This research and the ALS are supported by the Director, Office of Science, Office of Basic Energy Sciences (OBES), and the OBES Division of Chemical Sciences, Geosciences, and Biosciences of the U.S. Department of Energy at LBNL under Contract No. DE-AC02- 05CH11231. Rational Ligand Design for U(VI) and Pu(IV) by Géza Szigethy B.A. (Princeton University), 2004 A dissertation submitted in partial satisfaction of the requirements for the degree of Doctor of Philosophy in Chemistry in the Graduate Division of the University of California, Berkeley Committee in charge: Professor Kenneth N. Raymond, Chair Professor Richard A. Andersen Professor Garrison Sposito Fall 2009 Rational Ligand Design for U(VI) and Pu(IV) Copyright © 2009 Géza Szigethy Abstract Rational Ligand Design for U(VI) and Pu(IV) by Géza Szigethy Doctor of Philosophy in Chemistry University of California, Berkeley Professor Kenneth N. Raymond, Chair Nuclear power is an attractive alternative to hydrocarbon-based energy production at a time when moving away from carbon-producing processes is widely accepted as a significant developmental need. Hence, the radioactive actinide power sources for this industry are necessarily becoming more widespread, which is accompanied by the increased risk of exposure to both biological and environmental systems. -
Radioisotope Power: a Key Technology for Deep Space Exploration
20 Radioisotope Power: A Key Technology for Deep Space Exploration George R. Schmidt1, Thomas J. Sutliff1 and Leonard A. Dudzinski2 1NASA Glenn Research Center, 2NASA Headquarters USA 1. Introduction Radioisotope Power Systems (RPS) generate electrical power by converting heat released from the nuclear decay of radioactive isotopes into electricity. Because all the units that have flown in space have employed thermoelectrics, a static process for heat-to-electrical energy conversion that employs no moving parts, the term, Radioisotope Thermoelectric Generator (RTG), has been more popularly associated with these devices. However, the advent of new generators based on dynamic energy conversion and alternative static conversion processes favors use of “RPS” as a more accurate term for this power technology. RPS were first used in space by the U.S. in 1961. Since that time, the U.S. has flown 41 RTGs, as a power source for 26 space systems on 25 missions. These applications have included Earth- orbital weather and communication satellites, scientific stations on the Moon, robotic explorer spacecraft on Mars, and highly sophisticated deep space interplanetary missions to Jupiter, Saturn and beyond. The New Horizons mission to Pluto, which was launched in January 2006, represents the most recent use of an RTG. The former U.S.S.R. also employed RTGs on several of its early space missions. In addition to electrical power generation, the U.S. and former U.S.S.R. have used radioisotopes extensively for heating components and instrumentation. RPS have consistently demonstrated unique capabilities over other types of space power systems. A comparison between RPS and other forms of space power is shown in Fig. -
Space Isotopic Power Systems
Space isotopiC power systems With the technology sound and growing, and units already built for missions ranging from 120 days to 5 years, the designer can and should plan appropriate space application of isotopic systems BY CAPT. R. T. CARPENTER, USAF U.S. Atomic Energy Commission A new space power system technology technology, and aerospace nuclear Concurrently, the terrestrial appli -isotopic power-has developed to safety technology contributed by the cations-the Snap-7 programs-sus the point where it can and should be program and used as a foundation for tained the isotopic power development considered by the space-vehicle de follow-on space isotopic power-system program and promoted the fission signer for use in many types of mis developments. product separations and processing sions. Because of this sound technical capability that exists within the Com The' Atomic Energy Commission's basis, the Commission's space-oriented mission today! The interest among isotopic space power program dates isotopic power development program terrestrial power users-the Navy, back to several years before Sputnik has made a steady, although some Weather Bureau, and Coast Guard I, but the program suffered a severe times slow, comeback through a series was sufficiently strong to sup:port this setback in 1959 when the Snap-1A of events since 1959, so that today a . fuels production program, whe:r:eas the generator development program was program technically comparable to interest in Snap-1A had been inade cancelled.' This pioneer program was Snap-1A could once more be under quate. At the same time, significant not completed because it may have taken with a high probability of suc quantities of the long-lived alpha been tt;lO ambitious for its day. -
Chelation of Actinides
UC Berkeley UC Berkeley Previously Published Works Title Chelation of Actinides Permalink https://escholarship.org/uc/item/4b57t174 Author Abergel, RJ Publication Date 2017 DOI 10.1039/9781782623892-00183 Peer reviewed eScholarship.org Powered by the California Digital Library University of California Chapter 6 Chelation of Actinides rebecca J. abergela aChemical Sciences Division, lawrence berkeley National laboratory, One Cyclotron road, berkeley, Ca 94720, USa *e-mail: [email protected] 6.1 The Medical and Public Health Relevance of Actinide Chelation the use of actinides in the civilian industry and defense sectors over the past 60 years has resulted in persistent environmental and health issues, since a large inventory of radionuclides, including actinides such as thorium (th), uranium (U), neptunium (Np), plutonium (pu), americium (am) and curium 1 Downloaded by Lawrence Berkeley National Laboratory on 22/06/2018 20:28:11. (Cm), are generated and released during these activities. Controlled process- Published on 18 October 2016 http://pubs.rsc.org | doi:10.1039/9781782623892-00183 ing and disposal of wastes from the nuclear fuel cycle are the main source of actinide dissemination. however, significant quantities of these radionu- clides have also been dispersed as a consequence of nuclear weapons testing, nuclear power plant accidents, and compromised storage of nuclear materi- als.1 In addition, events of the last fifteen years have heightened public con- cern that actinides may be released as the result of the potential terrorist use of radiological dispersal devices or after a natural disaster affecting nuclear power plants or nuclear material storage sites.2,3 all isotopes of the 15 ele- ments of the actinide series (atomic numbers 89 through 103, Figure 6.1) are radioactive and have the potential to be harmful; the heaviest members, however, are too unstable to be isolated in quantities larger than a few atoms at a time,4 and those elements cited above (U, Np, pu, am, Cm) are the most RSC Metallobiology Series No. -
CURIUM Element Symbol: Cm Atomic Number: 96
CURIUM Element Symbol: Cm Atomic Number: 96 An initiative of IYC 2011 brought to you by the RACI ROBYN SILK www.raci.org.au CURIUM Element symbol: Cm Atomic number: 96 Curium is a radioactive metallic element of the actinide series, and named after Marie Skłodowska-Curie and her husband Pierre, who are noted for the discovery of Radium. Curium was the first element to be named after a historical person. Curium is a synthetic chemical element, first synthesized in 1944 by Glenn T. Seaborg, Ralph A. James, and Albert Ghiorso at the University of California, Berkeley, and then formally identified by the same research tea at the wartime Metallurgical Laboratory (now Argonne National Laboratory) at the University of Chicago. The discovery of Curium was closely related to the Manhattan Project, and thus results were kept confidential until after the end of World War II. Seaborg finally announced the discovery of Curium (and Americium) in November 1945 on ‘The Quiz Kids!’, a children’s radio show, five days before an official presentation at an American Chemical Society meeting. The first radioactive isotope of Curium discovered was Curium-242, which was made by bombarding alpha particles onto a Plutonium-239 target in a 60-inch cyclotron (University of California, Berkeley). Nineteen radioactive isotopes of Curium have now been characterized, ranging in atomic mass from 233 to 252. The most stable radioactive isotopes are Curium- 247 with a half-life of 15.6 million years, Curium-248 (half-life 340,000 years), Curium-250 (half-life of 9000 years), and Curium-245 (half-life of 8500 years). -
Curium Is the First North American Manufacturer Offering Exclusively 100% LEU Generators
FOR IMMEDIATE RELEASE January 16, 2018 Curium Is the First North American Manufacturer Offering Exclusively 100% LEU Generators (St. Louis - January 16, 2018) — Curium, a leading nuclear medicine solutions provider, announced today that the company is the first North American manufacturer to meet the deadline established by the American Medical Isotopes Production Act of 2012. This legislation effectively mandates the full conversion away from highly enriched uranium (HEU) as soon as possible and no later than January 2020. Curium’s multi-year project to transition its molybdenum-99 (Mo-99) processing facility from HEU to low enriched uranium (LEU) was completed in late-2017. This project makes Curium the only North American Technetium Tc 99m Generator manufacturer able to supply its customers exclusively with 100 percent LEU Tc 99m generators. Mo-99 is the parent isotope of Tc 99m, which is used in 30 to 40 million nuclear medicine procedures worldwide every year1. Curium is the world’s largest supplier of Tc 99m generators and the largest user of Mo- 99 in the world. “This milestone helps satisfy the goals set forth by the Department of Energy’s (DOE) National Nuclear Security Administration (NNSA) and confirms our support for the NNSA project to eliminate the use of weapons-grade uranium in the production of medical isotopes. We are eager to see others follow our lead and comply with the government’s call for full conversion as soon possible” says Curium North American CEO, Dan Brague. This project is the culmination of more than seven years of work, requiring close collaboration with Curium’s irradiation partners: the Dutch High Flux Reactor, the Polish MARIA reactor, and BR2 in Belgium, as well as, the DOE and NNSA. -
Episode 527: Nuclear Transmutation
9/28/2018 Episode 527: Nuclear transmutation Institute of Physics Search Home Electricity Mechanics Vibrations and waves Fields Atoms and nuclei Energy Astronomy You are here > Atoms and nuclei > Nuclear fission > Episode 527: Nuclear transmutation Nuclear fission Episode 527: Nuclear transmutation Episode 526: Preparation for nuclear fission topic Students need to move beyond the idea that nuclear changes are represented solely by alpha, beta and gamma decay. There are other decay processes, and there are other events that occur when a nucleus absorbs a particle and becomes unstable. Episode 527: Nuclear transmutation Episode 528: Controlling fission Summary Discussion: Transmutation of elements (15 minutes) Student questions: Balancing equations (30 minutes) Discussion: Induced fission (10 minutes) Demonstration: The nucleus as a liquid drop (10 minutes) Discussion: Fission products and radioactive waste (10 minutes) Worked example: A fission reaction (10 minutes) Discussion and demonstrations: Controlled chain reactions (15 minutes) Discussion: The possibility of fission (10 minutes) Student questions: Fission calculations (20 minutes) Discussion: Transmutation of elements Start by rehearsing some assumed knowledge. What is the nucleus made of? (Protons and neutrons, collectively know as nucleons.) What two natural processes change one element into another? (a and b decay). This is transmutation. Using a Periodic Table, explain that a decay moves two places down the periodic table. What about b- decay? (Moves one place up the periodic table.) Introduce the idea of b+ decay. (Moves one place down the periodic table.) Write general equations for these processes. There is another way in which an element may be transmuted; for example, the production of radioactive 14C used in radio- carbon dating in the atmosphere by the neutrons in cosmic rays.