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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. Breeder reactor - Wikipedia

    en.wikipedia.org/wiki/Breeder_reactor

    Assembly of the core of Experimental Breeder Reactor I in Idaho, United States, 1951. A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. [ 1 ] 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 uranium ...

  4. Prototype Fast Breeder Reactor - Wikipedia

    en.wikipedia.org/wiki/Prototype_Fast_Breeder_Reactor

    The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe sodium-cooled, fast breeder reactor that is being constructed at Kokkilamedu, near Kalpakkam, in Tamil Nadu state, India. [4] The Indira Gandhi Centre for Atomic Research (IGCAR) is responsible for the design of this reactor, the Advanced Fuel Fabrication Facility at the Bhabha Atomic ...

  5. 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 ...

  6. Integral fast reactor - Wikipedia

    en.wikipedia.org/wiki/Integral_fast_reactor

    The integral fast reactor (IFR), originally the advanced liquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron moderator (a "fast" reactor). IFRs can breed more fuel and are distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.

  7. 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 ...

  8. Fast Breeder Test Reactor - Wikipedia

    en.wikipedia.org/wiki/Fast_Breeder_Test_Reactor

    From 1989 to 1992, the reactor operated at 1 MW. In 1993, the reactor's power level was raised to 10.5 MW. In September 2002, fuel burn-up in the FBTR for the first time reached the 100,000 megawatt-days per metric ton uranium (MWd/MTU) mark. [citation needed] This is considered an important milestone in breeder reactor technology. On 7 March ...

  9. SEFOR - Wikipedia

    en.wikipedia.org/wiki/SEFOR

    SEFOR (Southwest Experimental Fast Oxide Reactor) was an experimental fast breeder reactor located in Cove Creek Township, Washington County, near Strickler, in northwest Arkansas (20 miles southwest of Fayetteville, Arkansas). The site consisted of a 20-Megawatt (thermal), Sodium-Cooled Test Reactor, a Shop Building, an Operations Building, a ...