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.[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]
BREST-300
[edit]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 8 June 2021.[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. 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.[clarification needed] 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.[clarification needed]
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]
Technical data
[edit]- 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
[edit]References
[edit]- ^ Design completed for prototype fast reactor, World Nuclear News. 2 September 2014
- ^ Ferapontov, Alexey (24 April 2023). "Licensing of new designs: BREST-300, RITM-200 (land deployment)" (PDF). Nuclear Energy Agency.
- ^ Lead-Cooled Fast-Neutron Reactor (BREST), IAEA. 2015
- ^ Russia Accelerates Efforts to Build Advanced Nuclear Reactors, Powermag. 1 October 2016
- ^ Russia notes progress with fast reactor technology, World Nuclear News. 23 August 2016
- ^ Preparatory construction for Brest-300 reactor begins in Russia, Nuclear Engineering International. 22 May 2020
- ^ ""Росатом" начал строительство реактора Брест-300 в Северске". 8 June 2021.
- ^ Proctor, Darrell (8 June 2021). "Nuclear First—Work Starts on Russian Fast Neutron Reactor". POWER Magazine. Retrieved 21 June 2021.
- ^ "Turbine island installation work under way at BREST-OD-300". world-nuclear-news.org. 4 November 2024. Retrieved 4 November 2024.
External links
[edit]- 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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