• Source: BREST (reactor)

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.
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 preparatory construction work commenced in May 2020. Construction started in 8 June 2021.
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. This is in contrast to other fast reactor designs, where an outside blanket of uranium is required; placing too much uranium in the core section would lead to subcritical operation.
In doing so, a substantial number of neutrons is required for breeding. This implies in turn, that in the reactor operation, there are "just enough" neutrons to operate, and no excess is present.
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.




Technical data


Thermal power: 700 MW
Electrical power 300 MW
Average lead coolant temperature: 540 °C (1,004 °F) on entry in the steam generator; 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




See also


Fast breeder reactor
Fast neutron reactor
Generation IV reactor
Siberian Chemical Combine




References






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

Kata Kunci Pencarian:

• OKB Gidropress
• Reaktor modular kecil
• BREST (reactor)
• Brest
• Lead-cooled fast reactor
• Generation IV reactor
• List of Russian small nuclear reactors
• Breeder reactor
• Small modular reactor
• Fast-neutron reactor
• BOR-60
• List of small modular reactor designs