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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. CFR-600 - Wikipedia

    en.wikipedia.org/wiki/CFR-600

    The CFR-600 (Xiapu fast reactor pilot project) is a sodium-cooled pool-type fast-neutron nuclear reactor under construction in Xiapu County, Fujian province, China, on Changbiao Island. [1] [2] It is a generation IV demonstration project by the China National Nuclear Corporation (CNNC). Construction started in late 2017.

  4. 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.

  5. Company hopes Wyoming's first nuclear power plant will ... - AOL

    www.aol.com/company-hopes-wyomings-first-nuclear...

    Sodium has been used as a coolant since the 1950s, but Levesque said the way they are doing it, using sodium-cooled fast reactors, will be safer, more efficient and more economical.

  6. BOR-60 - Wikipedia

    en.wikipedia.org/wiki/BOR-60

    Construction has started in 1964. Reactor reached first criticality in 1968. [4] Commissioned in 1969. [1] From 1969 to 1981 the BOR-60 used the pellet uranium fuel. [5] Since 1981 BOR-60 has been using the vibropac oxide mixed fuel with the power grade plutonium. [5] BOR-60 is expected to be closed in 2025. Currently constructed MBIR should ...

  7. 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.

  8. Enrico Fermi Nuclear Generating Station - Wikipedia

    en.wikipedia.org/wiki/Enrico_Fermi_Nuclear...

    Fermi 1 was a liquid metal (sodium) cooled fast breeder reactor design. It was capable of producing 200 megawatts thermal (MWt) power or 69 MW electrical power with 26% enriched metallic uranium fuel. The enriched uranium section of the reactor (core) was a 30 inches (76 cm) in diameter cylinder by 30 inches high and contained 92 fuel ...

  9. BN-600 reactor - Wikipedia

    en.wikipedia.org/wiki/BN-600_reactor

    A cutaway model of the reactor. The core, that is the nuclear fuel at the heart of the reactor has dimensions of 2 meters in height by 0.75 meters in diameter, similar to the BN-800 reactor. [1] The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia.