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  2. Sodium-cooled fast reactor - Wikipedia

    en.wikipedia.org/wiki/Sodium-cooled_fast_reactor

    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 .

  3. BN-1200 reactor - Wikipedia

    en.wikipedia.org/wiki/BN-1200_reactor

    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.

  4. Fast-neutron reactor - Wikipedia

    en.wikipedia.org/wiki/Fast-neutron_reactor

    Since liquid metals other than lithium and beryllium have low moderating ability, the primary interaction of neutrons with fast reactor coolant is the (n,gamma) reaction, which induces radioactivity in the coolant. Sodium-24 (24 Na) is created in the reactor loop of the sodium cooled fast reactor, from natural sodium-23 by neutron bombardment.

  5. BOR-60 - Wikipedia

    en.wikipedia.org/wiki/BOR-60

    The reactor is a sodium-cooled fast reactor, which uses liquid sodium as the coolant. [4] It uses two separate sodium loops, and these are connected to a main water-cooled loop which feeds the steam generators and turbines for producing electricity. [7] The sodium coolant is pressurized to 5.5 MPa, and is heated to over 500 °C in the reactor. [6]

  6. BN-800 reactor - Wikipedia

    en.wikipedia.org/wiki/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 power.

  7. CFR-600 - Wikipedia

    en.wikipedia.org/wiki/CFR-600

    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 ...

  8. Toshiba 4S - Wikipedia

    en.wikipedia.org/wiki/Toshiba_4S

    The actual reactor would be located in a sealed, cylindrical vault 30 m (98 ft) underground, while the building above ground would be 22×16×11 m (72×52.5×36 ft) in size. This power plant is designed to provide 10 megawatts of electrical power with a 50 MW version available in the future. [3] The 4S is a fast neutron sodium reactor

  9. BN-600 reactor - Wikipedia

    en.wikipedia.org/wiki/BN-600_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.