Abstract
The main results obtained from research activities on the technology of sodium coolant as applied to nuclear power installations built around fast-neutron reactors are briefly described. Abnormal situations involving considerable contamination of sodium coolant that were observed in fast-neutron reactors are considered. Further investigations in this field are aimed at extending the service life of the BN-600 nuclear power installation and developing advanced nuclear power plants on the basis of fast-neutron reactors with increased parameters. Problems that have to be urgently solved for further development of the sodium usage technology are formulated.
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Original Russian Text © F.A. Kozlov, V.V. Alekseev, Yu.I. Zagorul’ko, G.P. Sergeev, L.G. Volchkov, P.S. Kozub, Yu.P. Kovalev, T.A. Vorob’eva, A.N. Volov, 2007, published in Teploenergetika.
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Kozlov, F.A., Alekseev, V.V., Zagorul’ko, Y.I. et al. The results of the development of technology for using sodium as coolant for fast-neutron reactors. Therm. Eng. 54, 942–954 (2007). https://doi.org/10.1134/S0040601507120026
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DOI: https://doi.org/10.1134/S0040601507120026