Calculations Related to Nuclear Fission-Product Yields
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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. -
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. -
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. -
ESTIMATION of FISSION-PRODUCT GAS PRESSURE in URANIUM DIOXIDE CERAMIC FUEL ELEMENTS by Wuzter A
NASA TECHNICAL NOTE NASA TN D-4823 - - .- j (2. -1 "-0 -5 M 0-- N t+=$j oo w- P LOAN COPY: RET rm 3 d z c 4 c/) 4 z ESTIMATION OF FISSION-PRODUCT GAS PRESSURE IN URANIUM DIOXIDE CERAMIC FUEL ELEMENTS by WuZter A. PuuZson una Roy H. Springborn Lewis Reseurcb Center Clevelund, Ohio NATIONAL AERONAUTICS AND SPACE ADMINISTRATION WASHINGTON, D. C. NOVEMBER 1968 i 1 TECH LIBRARY KAFB, NM I 111111 lllll IllH llll lilll1111111111111 Ill1 01317Lb NASA TN D-4823 ESTIMATION OF FISSION-PRODUCT GAS PRESSURE IN URANIUM DIOXIDE CERAMIC FUEL ELEMENTS By Walter A. Paulson and Roy H. Springborn Lewis Research Center Cleveland, Ohio NATIONAL AERONAUTICS AND SPACE ADMINISTRATION For sale by the Clearinghouse for Federal Scientific and Technical Information Springfield, Virginia 22151 - CFSTl price $3.00 ABSTRACl Fission-product gas pressure in macroscopic voids was calculated over the tempera- ture range of 1000 to 2500 K for clad uranium dioxide fuel elements operating in a fast neutron spectrum. The calculated fission-product yields for uranium-233 and uranium- 235 used in the pressure calculations were based on experimental data compiled from various sources. The contributions of cesium, rubidium, and other condensible fission products are included with those of the gases xenon and krypton. At low temperatures, xenon and krypton are the major contributors to the total pressure. At high tempera- tures, however, cesium and rubidium can make a considerable contribution to the total pressure. ii ESTIMATION OF FISSION-PRODUCT GAS PRESSURE IN URANIUM DIOXIDE CERAMIC FUEL ELEMENTS by Walter A. Paulson and Roy H. -
Models of the Atomic Nucleus
Models of the Atomic Nucleus Second Edition Norman D. Cook Models of the Atomic Nucleus Unification Through a Lattice of Nucleons Second Edition 123 Prof. Norman D. Cook Kansai University Dept. Informatics 569 Takatsuki, Osaka Japan [email protected] Additional material to this book can be downloaded from http://extras.springer.com. ISBN 978-3-642-14736-4 e-ISBN 978-3-642-14737-1 DOI 10.1007/978-3-642-14737-1 Springer Heidelberg Dordrecht London New York Library of Congress Control Number: 2010936431 © Springer-Verlag Berlin Heidelberg 2006, 2010 This work is subject to copyright. All rights are reserved, whether the whole or part of the material is concerned, specifically the rights of translation, reprinting, reuse of illustrations, recitation, broadcasting, reproduction on microfilm or in any other way, and storage in data banks. Duplication of this publication or parts thereof is permitted only under the provisions of the German Copyright Law of September 9, 1965, in its current version, and permission for use must always be obtained from Springer. Violations are liable to prosecution under the German Copyright Law. The use of general descriptive names, registered names, trademarks, etc. in this publication does not imply, even in the absence of a specific statement, that such names are exempt from the relevant protective laws and regulations and therefore free for general use. Cover design: WMXDesign GmbH, Heidelberg Printed on acid-free paper Springer is part of Springer Science+Business Media (www.springer.com) Preface to the Second Edition Already by the 1970s, some theorists had declared that nuclear structure physics was a “closed chapter” in science, but since then it has repeatedly been found necessary to re-open this closed chapter to address old problems and to explain new phenom- ena. -
Re-Examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix
Re-examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix T. E. G. Nicholasa,∗, T. P. Davisb, F. Federicia, J. E. Lelandc, B. S. Patela, C. Vincentd, S. H. Warda a York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, UK b Department of Materials, University of Oxford, Parks Road, Oxford, OX1 3PH c Department of Electrical Engineering and Electronics, University of Liverpool, Liverpool, L69 3GJ, UK d Centre for Advanced Instrumentation, Department of Physics, Durham University, Durham DH1 3LS, UK Abstract Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineer- ing and materials science will still impose significant constraints on the char- acteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the sig- nificant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fu- sion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation. -
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. -
Relative Fission Product Yield Determination in the Usgs
RELATIVE FISSION PRODUCT YIELD DETERMINATION IN THE USGS TRIGA MARK I REACTOR by Michael A. Koehl © Copyright by Michael A. Koehl, 2016 All Rights Reserved A thesis submitted to the Faculty and the Board of Trustees of the Colorado School of Mines in partial fulfillment of the requirements for the degree of Doctor of Philosophy (Nuclear Engineering). Golden, Colorado Date: ____________________ Signed: ________________________ Michael A. Koehl Signed: ________________________ Dr. Jenifer C. Braley Thesis Advisor Golden, Colorado Date: ____________________ Signed: ________________________ Dr. Mark P. Jensen Professor and Director Nuclear Science and Engineering Program ii ABSTRACT Fission product yield data sets are one of the most important and fundamental compilations of basic information in the nuclear industry. This data has a wide range of applications which include nuclear fuel burnup and nonproliferation safeguards. Relative fission yields constitute a major fraction of the reported yield data and reduce the number of required absolute measurements. Radiochemical separations of fission products reduce interferences, facilitate the measurement of low level radionuclides, and are instrumental in the analysis of low-yielding symmetrical fission products. It is especially useful in the measurement of the valley nuclides and those on the extreme wings of the mass yield curve, including lanthanides, where absolute yields have high errors. This overall project was conducted in three stages: characterization of the neutron flux in irradiation positions within the U.S. Geological Survey TRIGA Mark I Reactor (GSTR), determining the mass attenuation coefficients of precipitates used in radiochemical separations, and measuring the relative fission products in the GSTR. Using the Westcott convention, the Westcott flux, ; modified spectral index, ; neutron temperature, ; and gold-based cadmium ratiosφ were determined for various sampling√⁄ positions in the USGS TRIGA Mark I reactor. -
Ornl-Tm-1853
OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the U.S. ATOMIC ENERGY COMMISSION ORNL- TM-1853 COPY NO. - 0-C kc+- DATE -6-6-67 CFSTI RpICZiS CHEMICAL RESEARCHAND DEVELOPMENTFOR MOLTEN- SALT BREEDERREACTORS W. R. Grimes ABSTRACT kq Results of the 15-year program of chemical research and develop- .; ment for molten salt reactors are summarized in this document. These c results indicate that 7LiF-BeFz-LJFb mixtures are feasible fuels for thermal breeder reactors. Such mixtures show satisfactory phase be- havior, they are compatible with Hastelloy N and moderator graphite, and they appear to resist radiation and tolerate fission product ac- cumulation. Mixtures of 7LiF-BeF2-ThF4 similarly appear suitable as blankets for such machines. Several possible secondary coolant mix- tures are available; NaF-NaBF3 systems seem, at present, to be the most likely possibility. Gaps in the technology are presented along with the accomplish- ments, and an attempt is made to define the information (and the research and development program) needed before a Molten Salt Thermal Breeder can be operated with confidence. NOTICE This document contains information of a preliminary nature and was prepared primarily for internal use at the Oak Ridge National Loboratory. It is subject to revision or correction and therefore does not represent a final report. The information is not to be abstracted, reprinted or otherwise given public dis- 4 .”: semination without the approval of the ORNL potent branch, Legal and Infor- mation Control Department. ’ y a I LEGAL NOTICE This report was prepored as an occount of Government sponsored work. Neither the United States, nw the Commission, nor ony person octing un beholf of the Commission: A. -
Uranium (Nuclear)
Uranium (Nuclear) Uranium at a Glance, 2016 Classification: Major Uses: What Is Uranium? nonrenewable electricity Uranium is a naturally occurring radioactive element, that is very hard U.S. Energy Consumption: U.S. Energy Production: and heavy and is classified as a metal. It is also one of the few elements 8.427 Q 8.427 Q that is easily fissioned. It is the fuel used by nuclear power plants. 8.65% 10.01% Uranium was formed when the Earth was created and is found in rocks all over the world. Rocks that contain a lot of uranium are called uranium Lighter Atom Splits Element ore, or pitch-blende. Uranium, although abundant, is a nonrenewable energy source. Neutron Uranium Three isotopes of uranium are found in nature, uranium-234, 235 + Energy FISSION Neutron uranium-235, and uranium-238. These numbers refer to the number of Neutron neutrons and protons in each atom. Uranium-235 is the form commonly Lighter used for energy production because, unlike the other isotopes, the Element nucleus splits easily when bombarded by a neutron. During fission, the uranium-235 atom absorbs a bombarding neutron, causing its nucleus to split apart into two atoms of lighter mass. The first nuclear power plant came online in Shippingport, PA in 1957. At the same time, the fission reaction releases thermal and radiant Since then, the industry has experienced dramatic shifts in fortune. energy, as well as releasing more neutrons. The newly released neutrons Through the mid 1960s, government and industry experimented with go on to bombard other uranium atoms, and the process repeats itself demonstration and small commercial plants. -
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.