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The results of the development of technology for using sodium as coolant for fast-neutron reactors
Authors: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
Affiliation:(1) State Scientific Center of the Russian Federation, The Leipunskii Institute of Energy Physics (FEI), pl. Bondarenko 1, Obninsk, Kaluzhskaya oblast, 249033, Russia
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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