Considerable Russian experience has been built up from operation of a number of experimental and prototype fast reactors including BR-10, BOR-60, BN-350 and BN-600 (IAEA-TECDOC-1289, 2002). BN-600 has operated reliably at Belojarskl in Russia (IAEA-TECDOC-1083, 1999). BN-600 has a nominal power output of 600 MWe and has been in operation in 1980 with an average load factor of 70% (IAEA-TECDOC — 1289, 2002).

The major emphasis in the Russian Federation is in continued design improvement and improved economics. The main applications are seen to be for energy production and the conversion of plutonium and minor actinides. The design of BN-800 has been completed and a site licence issued for the construction of a BN-800 at Yuzno-Uralskya and Beloyarskaya in Russia (IAEA-TECDOC-1289, 2002).

BN-800 is based on a three circuit flow system incorporating three primary loops, three secondary loops and three steam generators. The reactor core and radial blanket are built up with assemblies in a hexagonal lattice. The fuel is MOX sintered pellets. Compared with BN-600, there are a number of design improvements.

These include improved economic and operational performance, enhanced reliability of components and simplification of systems (e. g. single steam turbine compared with three in BN-600). Improved safety is included with the introduction of a passive emergency protection system and improved safety system redundancy and diversity.