The MBIR is a multi-loop research reactor capable of testing lead, lead-bismuth and gas coolants, and run on
MOX fuel
Mixed oxide fuel (MOX fuel) is nuclear fuel that contains more than one oxide of fissile material, usually consisting of plutonium blended with natural uranium, reprocessed uranium, or depleted uranium. MOX fuel is an alternative to the low-enr ...
. MBIR intends to replace the old
BOR-60
The BOR-60 is an operational Russian research sodium-cooled fast reactor designed to test nuclear fuels, structural materials and coolants, as well as scientific experiments under fast neutron irradiation.
History
The BOR-60 reactor was constr ...
experimental
fast reactor
A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons (carrying energies above 1 MeV, on average), as opposed to slow t ...
that started operations at
RIAR's site in 1969. It will have a design life of 50 years.
History
Construction has started in 2015.
MBIR control assembly was installed in 2019.
Reactor vessel was installed in 2023.
Pilot fuel elements were produced in 2024. The MBIR is scheduled to begin operation in 2027.
Estimated commissioning date is 2028.
See also
*
Generation IV reactor
Generation IV (Gen IV) reactors are nuclear reactor design technologies that are envisioned as successors of generation III reactors. The Generation IV International Forum (GIF) – an international organization that coordinates the development of ...
*
BN-800 reactor
The BN-800 reactor (Russian: реактор БН–800) is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. The reactor is designed to generate 880 MW of electrical pow ...
- generation IV
sodium-cooled fast breeder
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. These reactors can be fueled with more-commonly available isotopes of uranium and thorium, such as uranium-238 and thorium-232, as opposed to the rare ...
reactor, operational since 2016
*
BREST-300 - generation IV
lead-cooled fast reactor
The lead-cooled fast reactor is a nuclear reactor design that uses molten lead or lead-bismuth eutectic as its coolant. These materials can be used as the primary coolant because they have low neutron absorption and relatively low melting poi ...
, in construction since 2020
References
External links
Official website
Liquid metal fast reactors
Nuclear power in Russia
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