BREST (reactor)

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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]


The construction of the BREST-300-OD in Seversk (near Tomsk) was approved in August 2016.[3][4]

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 on entry, 340 °C on exit of the steam generator
  • Loop number: 4
  • Core height: 1100 mm
  • Fuel load: 20.6 tons
  • Fuel campaign: 5 years

See also


  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

External links

  • Design Features of BREST Reactors and Experimental Work to Advance the Concept of BREST Reactors
  • Lead-Cooled Fast-Neutron Reactor (BREST), IAEA. 2015
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