[en] Presentation about reactor plant parameters, the evolution of engineering solutions, the requirements for new BN reactor designs and the current status of the projects

[en] The paper provides information about the development of the sodium cooled fast reactors in the former USSR (Russian Federation) starting from the 1950s. The evolution of this technology is traced from the small research reactors to large power units. It is shown how power and parameters were changing in reactor plants; how engineering solutions on the layout, reactor core design, main equipment and systems were evolving; and how the most important problem on increasing the fuel burnup was being gradually solved. Mastering of the dense nitride fuel instead of the MOX fuel is mentioned as an important challenge. Given are operational results for the first power units with the BN-350 and BN-600 reactors; the experience obtained is evaluated. Characterized are the challenges to be faced in the new BN-800 and BN-1200 projects, as well as information about the status of these projects. (author)

[en] Review of the general state of nuclear power in Russia as for 1998 is given in brief in the paper. Results of operation of BR-10, BOR-60 and BN-600 fast reactors are presented as well as of scientific and technological escort of the BN-350 reactor. The paper outlines the current status and prospects of South-Urals and Beloyarskaya power unit projects with the BN-800 reactors. The main planned development trends on fast reactors are described concerning both new projects and R and D works. (author)