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A fundamental study on testing candidate tritium breeders for fusion reactiors

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Abstract

An apparatus was designed and constructed for investigation of the tritium release rate from neutron-irradiated materials for fusion reactors. The design principles, as well as safe handling of tritium and complete trapping of tritium components released, are described and the tritium release rates obtained with this apparatus are discussed for sintered lithium fluoride pellets.

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Author notes

  1. Y. Sakuma

    Present address: Institute of Plasma Physics, Nagoya University, Nagoya, Japan

Authors and Affiliations

  1. Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, Meguro-Ku, 152, Tokyo, (Japan)

    M. Tabata, Y. Sakuma & M. Okamoto

Authors
  1. M. Tabata
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  2. Y. Sakuma
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  3. M. Okamoto
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Tabata, M., Sakuma, Y. & Okamoto, M. A fundamental study on testing candidate tritium breeders for fusion reactiors. J. Radioanal. Chem. 77, 105–114 (1983). https://doi.org/10.1007/BF02525359

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  • DOI: https://doi.org/10.1007/BF02525359

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