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Lithium carbide is prospective material for breeder of fusion reactor

  • Materials of Power Engineering and Radiation-Resistant Materials
  • Published:
Inorganic Materials: Applied Research Aims and scope

Abstract

It is shown that lithium carbide is a prospective material for breeder of fusion reactor. The lithium carbide equivalent dose rate reaches a biologically safe level (2.3 × 10−5 Sv/h) one minute after the irradiation with fusion reactor neutrons (with a fluence of 2 × 1023 cm−2) is stopped. The yield of tritium from lithium carbide is 1.5–2.6 times higher than the corresponding yield from such lithium ceramics as Li4SiO4 and Li2TiO3.

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Authors and Affiliations

  1. Vernadsky Institute of Geochemistry and Analytical Chemistry, Russian Academy of Sciences, Moscow, 119991, Russia

    M. V. Alenina & V. P. Kolotov

  2. Baikov Institute of Metallurgy and Materials Science, Russian Academy of Sciences, Moscow, 119991, Russia

    Yu. M. Platov

Authors
  1. M. V. Alenina
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  2. V. P. Kolotov
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  3. Yu. M. Platov
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Correspondence to M. V. Alenina.

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Original Russian Text © M.V. Alenina, V.P. Kolotov, Yu.M. Platov, 2013, published in Perspektivnye Materialy, 2013, No. 7, pp. 44–48.

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Alenina, M.V., Kolotov, V.P. & Platov, Y.M. Lithium carbide is prospective material for breeder of fusion reactor. Inorg. Mater. Appl. Res. 5, 149–153 (2014). https://doi.org/10.1134/S2075113314020026

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  • DOI: https://doi.org/10.1134/S2075113314020026

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