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 radioactiv 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 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
References
- ↑ Design completed for prototype fast reactor, World Nuclear News. 2nd September 2014
- ↑ Lead-Cooled Fast-Neutron Reactor (BREST), IAEA. 2015
- ↑ Russia Accelerates Efforts to Build Advanced Nuclear Reactors, Powermag. 1st October 2016
- ↑ Russia notes progress with fast reactor technology, World Nuclear News. 23rd 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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