BREST (reactor)

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.[1]

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.[2]

BREST-300

The construction of the BREST-300-OD in Seversk (near Tomsk) was approved in August 2016.[3][4]. The preparatory construction work commenced in May 2020. [5]

The first BREST-300 will be a demonstration unit, as forerunner to the BREST-1200.

Technical data
  • 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
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See also

References
  1. Design completed for prototype fast reactor, World Nuclear News. 2 September 2014
  2. Lead-Cooled Fast-Neutron Reactor (BREST), IAEA. 2015
  3. Russia Accelerates Efforts to Build Advanced Nuclear Reactors, Powermag. 1 October 2016
  4. Russia notes progress with fast reactor technology, World Nuclear News. 23 August 2016
  5. Preparatory construction for Brest-300 reactor begins in Russia, Nuclear Engineering International. 22 May 2020
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