Operating experience and prospects for future development of sodium-cooled fast reactors

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 sodiumcooled 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.The present article is devoted to an analysis of the operating experience gained with sodium-cooled fast reactors from the standpoint of developing and mastering such reactor technology as well as the prospects for its subsequent development. Sodium-cooled fast reactors were mastered on the basis of R&D work and taking account of operating experience. In turn, the performance indicators attained attest to the quality of the development and level of mastery of this reactor technology as a whole.Stages of Assimilation of Sodium-Cooled Fast Reactors. The work on sodium-cooled fast reactors began in our country in the second half of the 20th century. The results were as follows:• the research fast reactor BR-5/10 (