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Reprocessing of Spent Nuclear Fuels

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U Uranium

Part of the book series: Gmelin Handbook of Inorganic Chemistry / Gmelin Handbuch der Anorganischen Chemie ((1057,volume U / A-E / A / 4))

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Abstract

Owing to the accumulation of fission products, the depletion of fissile nuclides, and/or changes in the mechanical behavior of the cladding, a nuclear reactor fuel element must be removed from the reactor after a certain period of service, e.g., about 3 years in the case of a LWR. To separate the non-fissioned uranium and the built-up fissile materials such as plutonium and 233U, the irradiated fuel element must be reprocessed after an intermediate “cooling” time to allow for the decay of short-lived radionuclides. Reprocessing of spent fuels strongly depends on the nature of the fuel and on the type of nuclear reactor.

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Authors and Affiliations

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

    G. N. Walton

  2. Institut für Chemische Technologie, Kernforschungsanlage Jülich Jülich, Bundesrepublik Deutschland

    E. Merz

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  1. G. N. Walton
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  1. Gmelin-Institut, Frankfurt am Main, Germany

    Karl-Christian Buschbeck

  2. Kernforschungszentrum Karlsruhe, Schule für Kerntechnik, Frankfurt am Main, Germany

    Cornelius Keller (Supervising scientific coordinator for the Uranium Supplement Volumes) (Supervising scientific coordinator for the Uranium Supplement Volumes)

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Walton, G.N., Merz, E. (1981). Reprocessing of Spent Nuclear Fuels. In: Buschbeck, KC., Keller, C. (eds) U Uranium. Gmelin Handbook of Inorganic Chemistry / Gmelin Handbuch der Anorganischen Chemie, vol U / A-E / A / 4. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-662-06014-8_2

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