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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

    The nuclear fuel cycle employs a full actinide recycle with two major options: One is an intermediate-size (150–600 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel, supported by a fuel cycle based on pyrometallurgical reprocessing in facilities integrated with the reactor. The second is a medium to ...

  4. 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 ...

  5. Outline of nuclear power - Wikipedia

    en.wikipedia.org/wiki/Outline_of_nuclear_power

    Fast neutron reactor; Gas-cooled fast reactor; Generation IV reactor; Integral Fast Reactor; ... Archived from the original (PDF) on 1 December 2007.

  6. Prototype Fast Breeder Reactor - Wikipedia

    en.wikipedia.org/wiki/Prototype_Fast_Breeder_Reactor

    Schematic diagram showing the difference between the loop and pool designs of a liquid metal fast breeder reactor. The pool-type has greater thermal inertia to changes in temperature, which therefore gives more time to shut down/SCRAM during a loss of coolant accident situation. The reactor is a pool type LMFBR with

  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. Clementine (nuclear reactor) - Wikipedia

    en.wikipedia.org/wiki/Clementine_(nuclear_reactor)

    Clementine was the code name for the world's first fast-neutron reactor, also known as the Los Alamos fast plutonium reactor. It was an experimental-scale reactor. The maximum output was 25 kW and was fueled by plutonium and cooled by liquid mercury. Clementine was located at Los Alamos National Laboratory in Los Alamos, New Mexico.

  9. Category:Fast-neutron reactors - Wikipedia

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

    Download as PDF; Printable version; In other projects Wikimedia Commons; ... Fast-neutron reactor; A. Aurora nuclear reactor; C. CFR-600; Clinch River Breeder Reactor ...