The BREST reactor is a Russian conceptual design for a lead-cooled fast reactor based on a generation IV reactor. Two designs are planned, the BREST-300 (300 MWe) and the BREST-1200 (1200 MWe). The 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.[2] Lead is chosen as a coolant for being high-boiling, radiation-resistant, low-activated and at atmospheric pressure.[3]
The construction of the BREST-300-OD in Seversk (near Tomsk) was approved in August 2016.[4] [5] The preparatory construction work commenced in May 2020.[6] Construction started in .[7] [8]
The first BREST-300 will be a demonstration unit, as forerunner to the BREST-1200.
The combination of a heat-conducting nitride fuel and the properties of the lead coolant allow for complete plutonium breeding inside the core. This results in a small operating reactivity margin and enables power operation without prompt neutron reactor power excursions. In simpler terms, the uranium 238 in the core is converted to plutonium, which itself will undergo an effective fission in the fast spectrum. In doing so, a substantial number of neutrons is required for breeding.
By the end of 2024 the cooling tower has been built, the walls of the reactor containment building have been erected, the reactor shaft has been installed. In November 2024 installation work has begun for the condenser in the turbine hall. Installation of the turbine and generator is planned to start in 2025. The target for starting operation is 2026.[9]