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  2. Fast-neutron reactor - Wikipedia

    en.wikipedia.org/wiki/Fast-neutron_reactor

    The BN-350 fast-neutron reactor at Aktau, Kazakhstan.It operated between 1973 and 1994. 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 thermal neutrons used in thermal-neutron reactors.

  3. 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 .

  4. Category:Fast-neutron reactors - Wikipedia

    en.wikipedia.org/wiki/Category:Fast-neutron_reactors

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  5. BN-350 reactor - Wikipedia

    en.wikipedia.org/wiki/BN-350_reactor

    Construction of the BN-350 fast breeder reactor began in 1964, [2]: 785 and the plant first produced electricity in 1973. [3] In addition to providing power for the city (350 MW e ), BN-350 was also used for producing plutonium and for desalination to supply 120,000 m³ of fresh water per day to the city.

  6. Beloyarsk Nuclear Power Station - Wikipedia

    en.wikipedia.org/wiki/Beloyarsk_Nuclear_Power...

    The BN-800 is the largest fast neutron power reactor in service in the world. Three turbines are connected to the BN-600 reactor. The BN-600 reactor core is 1.03 metres (41 in) tall and has a diameter of 2.05 metres (81 in). It has 369 fuel assemblies, each consisting of 127 fuel rods with an enrichment of 17–26% 235 U.

  7. 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.

  8. Gas-cooled fast reactor - Wikipedia

    en.wikipedia.org/wiki/Gas-cooled_fast_reactor

    Classed as a Generation IV reactor, it features a fast-neutron spectrum and closed fuel cycle for efficient conversion of fertile uranium and management of actinides. The reference reactor design is a helium - cooled system operating with an outlet temperature of 850 °C (1,560 °F) using a direct Brayton closed-cycle gas turbine for high ...

  9. 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.