The results of the development of technology for using sodium as coolant for fast-neutron reactors

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.