Abstract
The main stages of the development of sodium-cooled fast reactors in Russia are described. The statistical information on the deviations from the normal regime of functioning that occur in BOR-60 and BN-600 operation is presented. The important role of BN-600 at the Beloyarskaya nuclear power plant in the validation of sodium-cooled fast reactors is shown. A conclusion is drawn on the basis of a review of the operating experience about the level of mastery of sodium-cooled fast reactors in Russia and the prospects for further development of such reactors are analyzed taking account of this experience.
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