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 8 June 2021. [7] [8]
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 ][ citation 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. The first BREST-300 will be a demonstration unit over the next decade. If it is successful, the 1200 MWe (2800 MWt) BREST-1200 will be developed. [9]
In January 2025 the facility for fabrication of nuclear fuel for BREST-OD-300 has started producing prototype fuel assemblies with depleted uranium nitride fuel pellets. It will have around 250 people working in it. [10]
The CANDU is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium oxide moderator and its use of uranium fuel. CANDU reactors were first developed in the late 1950s and 1960s by a partnership between Atomic Energy of Canada Limited (AECL), the Hydro-Electric Power Commission of Ontario, Canadian General Electric, and other companies.
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