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Hydrogen Isotopes Retention In Fusion Reactor Plasmafacing Materials: An Abbreviated Review

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Hydrogen and Helium Recycling at Plasma Facing Materials

Part of the book series: NATO Science Series ((NAII,volume 54))

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Abstract

Fusion reactor design requires an understanding of the tritium retention and recycling properties of the plasma-facing materials. After many years of research, a basic understanding of these properties for materials such as beryllium, carbon, and tungsten has been achieved. This report is an abbreviated review of these properties. The most widely accepted values (in the opinion of the authors) for diffusivity, solubility, recombination rate coefficient, and trapping parameters for each of the above materials is given.

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Author information

Authors and Affiliations

  1. Sandia National Laboratories, Livermore, CA, 94550, USA

    Rion A. Causey

  2. Los Alamos National Laboratories, Los Alamos, NM, 87545, USA

    Tom J. Venhaus

Authors
  1. Rion A. Causey
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  2. Tom J. Venhaus
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Editor information

Editors and Affiliations

  1. Argonne National Laboratory, Argonne, Illinois, USA

    Ahmed Hassanein

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© 2002 Springer Science+Business Media Dordrecht

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Causey, R.A., Venhaus, T.J. (2002). Hydrogen Isotopes Retention In Fusion Reactor Plasmafacing Materials: An Abbreviated Review. In: Hassanein, A. (eds) Hydrogen and Helium Recycling at Plasma Facing Materials. NATO Science Series, vol 54. Springer, Dordrecht. https://doi.org/10.1007/978-94-010-0444-2_1

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  • DOI: https://doi.org/10.1007/978-94-010-0444-2_1

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-1-4020-0512-1

  • Online ISBN: 978-94-010-0444-2

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