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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. 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

  4. Fermi 1 - Wikipedia

    en.wikipedia.org/wiki/Fermi_1

    Fermi 1 was the United States ' only demonstration-scale breeder reactor, built during the 1950s at the Enrico Fermi Nuclear Generating Station on the western shore of Lake Erie south of Detroit, Michigan. It used the sodium-cooled fast reactor cycle, in which liquid sodium metal is used as the primary coolant instead of typical nuclear reactor ...

  5. Monju Nuclear Power Plant - Wikipedia

    en.wikipedia.org/wiki/Monju_Nuclear_Power_Plant

    Monju (もんじゅ) was a Japanese sodium-cooled fast reactor, located near the Tsuruga Nuclear Power Plant, Fukui Prefecture. Its name is a reference to Manjusri. Construction started in 1986 and the reactor achieved criticality for the first time in April 1994. The reactor has been inoperative for most of the time since it was originally built.

  6. Prototype Fast Breeder Reactor - Wikipedia

    en.wikipedia.org/wiki/Prototype_Fast_Breeder_Reactor

    The prototype fast breeder reactor has a negative void coefficient, thus ensuring a high level of passive nuclear safety. This means that when the reactor overheats (below the boiling point of sodium) the speed of the fission chain reaction decreases, lowering the power level and the temperature. [23]

  7. Fast Flux Test Facility - Wikipedia

    en.wikipedia.org/wiki/Fast_Flux_Test_Facility

    The Fast Flux Test Facility with labels. Commemorative photo marking the completion of the FFTF system. The Fast Flux Test Facility (FFTF) is a 400 MW thermal, liquid sodium cooled, nuclear test reactor owned by the U.S. Department of Energy. It does not generate electricity. It is situated in the 400 Area of the Hanford Site, which is located ...

  8. BN-800 reactor - Wikipedia

    en.wikipedia.org/wiki/BN-800_reactor

    Photo from Rosatom. 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. The plant was considered part of the weapons-grade Plutonium Management and ...

  9. BN-1200 reactor - Wikipedia

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

    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.