enow.com Web Search

Search results

  1. Results from the WOW.Com Content Network
  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. Experimental Breeder Reactor II - Wikipedia

    en.wikipedia.org/.../Experimental_Breeder_Reactor_II

    The Experimental Breeder Reactor II. Experimental Breeder Reactor-II (EBR-II) was a sodium-cooled fast reactor designed, built and operated by Argonne National Laboratory at the National Reactor Testing Station in Idaho. It was shut down in 1994. Custody of the reactor was transferred to Idaho National Laboratory after its founding in 2005.

  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. Prototype Fast Breeder Reactor - Wikipedia

    en.wikipedia.org/wiki/Prototype_Fast_Breeder_Reactor

    The Kalpakkam PFBR is designed to use uranium-238 to breed plutonium in a sodium-cooled fast reactor design. The use of thorium-232, which in itself is not a fissile material, as a blanket is also envisaged in this stage. By transmutation, thorium will create fissile uranium-233 which will be used as fuel in the third stage.

  7. SEFOR - Wikipedia

    en.wikipedia.org/wiki/SEFOR

    The design concept of using thermal expansion to stabilize a reactor core has since been featured in other reactor designs, notably in the pebble bed reactor, which is however neither a fast neutron reactor nor a breeder reactor, and in subsequent Fast breeder reactors.

  8. 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.

  9. PRISM (reactor) - Wikipedia

    en.wikipedia.org/wiki/PRISM_(reactor)

    The integral fast reactor was developed at the West Campus of the Argonne National Laboratory in Idaho Falls, Idaho and was an extension (inc fuel reprocessing) to the Experimental Breeder Reactor II, which achieved first criticality in 1965 and ran for 30 years. The Integral Fast Reactor project (and EBR II) was shut down by the U.S. Congress ...