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A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor .
A cutaway model of the reactor. The core, that is the nuclear fuel at the heart of the reactor has dimensions of 2 meters in height by 0.75 meters in diameter, similar to the BN-800 reactor. [1] The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia.
The BN-1200 reactor is a sodium-cooled fast breeder reactor project, under development by OKBM Afrikantov in Zarechny, Russia. The BN-1200 is based on the earlier BN-600 and especially BN-800, with which it shares a number of features. The reactor's name comes from its electrical output, nominally 1220 MWe.
Sodium has been used as a coolant since the 1950s, but Levesque said the way they are doing it, using sodium-cooled fast reactors, will be safer, more efficient and more economical.
Energy portal; Nuclear technology portal; Russia portal; MBIR - multi-loop research reactor intends to replace BOR-60. In construction since 2015, est. completion in 2027. BN-800 reactor - generation IV sodium-cooled fast breeder reactor, operational since 2016
The reactor will have an output of 1500 MW thermal power and 600 MW electric power. [1] [2] The fuel will be supplied by TVEL, subsidiary of Rosatom, according to the agreement signed in 2019. [4] The CFR-600 is part of the Chinese plan to reach a closed nuclear fuel cycle. Fast neutron reactors are the main future nuclear power technology in ...
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 power.
ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) was a proposal for a 600 MW sodium-cooled fast breeder reactor (Generation IV), proposed by the Commissariat à l'énergie atomique (CEA). It was to be built on the Marcoule Nuclear Site in France.