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.
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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.
BREST-300
The construction of the BREST-300-OD in Seversk (near Tomsk) was approved in August 2016.
The first BREST-300 will be a demonstration unit, as forerunner to the BREST-1200.
Technical data
References
BREST (reactor) Wikipedia(Text) CC BY-SA