The BREST reactor is a Russian concept of lead-cooled fast reactor aiming to the standards of a generation IV reactor. Two designs are planned, the BREST-300 (300 MWe) and the BREST-1200 (1200 MWe). Main characteristics of the BREST reactor are passive safety and a closed fuel cycle.
The reactor uses nitride uranium-plutonium fuel, is a breeder reactor and can burn long-term radioactive waste. Lead is chosen as a coolant for being high-boiling, radiation-resistant, low-activated and at atmospheric pressure.
The first BREST-300 will be a demonstration unit, as forerunner to the BREST-1200.
- Thermal power: 700 MW
- Electrical power 300 MW
- Average lead coolant temperature: 505 °C (941 °F) on entry, 340 °C (644 °F) on exit of the steam generator
- Loop number: 4
- Core height: 1,100 millimetres (43 in)
- Fuel load: 20.6 short tons (18.7 t)
- Fuel campaign: 5 years
- Design completed for prototype fast reactor, World Nuclear News. 2 September 2014
- Lead-Cooled Fast-Neutron Reactor (BREST), IAEA. 2015
- Russia Accelerates Efforts to Build Advanced Nuclear Reactors, Powermag. 1 October 2016
- Russia notes progress with fast reactor technology, World Nuclear News. 23 August 2016