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U Uranium

Behavior of Uranium Fuels in Nuclear Reactors. Reprocessing of Spent Nuclear Fuels

  • Book
  • © 1981

Overview

Part of the book series: Gmelin Handbook of Inorganic and Organometallic Chemistry - 8th edition (GMELIN, volume U / A-E / A / 4)

Part of the book sub series: U. Uran. Uranium (System-Nr. 55) (1057)

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Table of contents (2 chapters)

Keywords

About this book

The present volume A4 of the "Uranium" series of the Gmelin Handbook deals with two very important technological aspects of the nuclear fuel cycle: - the behavior of fuel elements during burnup in a nuclear reactor, and - the reprocessing of spent fuel to recover the non-fissioned uranium and newly created materials. The usefullifetime of a fuel element in a nuclear reactor depends strongly on the change of its chemical and physical properties during irradiation. Properties like thermal conductivity, swelling, creep, and oxygen-to-metal ratio are strongly affected by the intense neutron field and the energetic fission products. Furthermore, the high temperature gradient in a fuel element also produces alterations of the initial fuel. such as densification or U: Pu segregation. All of these effects are thoroughly discussed for the different kinds of fuels to be used in modern nuclear reactors today or in the future. The vast amount of very often Contradietory results in sometimes difficultly obtainable Iiterature has been summarized to create a compendium in this field with the two sections, on oxide and on carbide and nitride fuels, respectively. The chapters on reprocessing of spent fuels deal only with fuel elements of the uranium­ 235 thorium fuel cycle and with those containing fuel highly enriched in U. The treatment of U0 2 and (U,Pu)0 has already been given in the transuranic element series.

Authors, Editors and Affiliations

  • Gmelin-Institut, Frankfurt am Main, Germany

    Karl-Christian Buschbeck

  • Kernforschungszentrum Karlsruhe, Schule für Kerntechnik, Frankfurt am Main, Germany

    Cornelius Keller

  • Kraftwerk Union AG, Erlangen, Germany

    Helmut Aßmann, Heinz Stehle

  • Kernforschungsanlage, Jülich, Germany

    Erich Merz, Aristides Naoumidis, Hubertus Nickel

  • Department of Chemical Engineering and Chemical Technology, Imperial College, London University, London, UK

    Gilbert N. Walton

Bibliographic Information

  • Book Title: U Uranium

  • Book Subtitle: Behavior of Uranium Fuels in Nuclear Reactors. Reprocessing of Spent Nuclear Fuels

  • Authors: Helmut Aßmann, Erich Merz, Aristides Naoumidis, Hubertus Nickel, Heinz Stehle, Gilbert N. Walton

  • Editors: Karl-Christian Buschbeck, Cornelius Keller

  • Series Title: Gmelin Handbook of Inorganic and Organometallic Chemistry - 8th edition

  • DOI: https://doi.org/10.1007/978-3-662-06014-8

  • Publisher: Springer Berlin, Heidelberg

  • eBook Packages: Springer Book Archive

  • Copyright Information: Springer-Verlag Berlin Heidelberg 1981

  • eBook ISBN: 978-3-662-06014-8Published: 11 November 2013

  • Edition Number: 8

  • Number of Pages: V, 359

  • Number of Illustrations: 23 b/w illustrations

  • Topics: Chemistry/Food Science, general, Inorganic Chemistry

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