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Development of Sodium Coolant Technology for Fast Reactors

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The results of investigations of the composition of sodium impurities and sodium coolant filtrate during prolonged operation of a fast reactor and the methods and means for monitoring impurities and removing them from sodium coolant are presented. Models of mass transfer of dissolved impurities and suspensions of the components of steel in sodium loops are described. The mass transfer of tritium formed in a fast reactor is analyzed.

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Authors and Affiliations

  1. State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI), Obninsk, Russia

    F. A. Kozlov, V. V. Alekseev & A. P. Sorokin

Authors
  1. F. A. Kozlov
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  2. V. V. Alekseev
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  3. A. P. Sorokin
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Translated from Atomnaya Énergiya, Vol. 116, No. 4, pp. 228–234, April, 2014.

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Kozlov, F.A., Alekseev, V.V. & Sorokin, A.P. Development of Sodium Coolant Technology for Fast Reactors. At Energy 116, 278–284 (2014). https://doi.org/10.1007/s10512-014-9854-8

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  • DOI: https://doi.org/10.1007/s10512-014-9854-8

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