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  2. Breeder reactor - Wikipedia

    en.wikipedia.org/wiki/Breeder_reactor

    India has been trying to develop fast breeder reactors for decades but suffered repeated delays. [72] By December 2024 the Prototype Fast Breeder Reactor is due to be completed and commissioned. [73] [74] [75] The program is intended to use fertile thorium-232 to breed fissile uranium-233. India is also pursuing thorium thermal breeder reactor ...

  3. Thorium-based nuclear power - Wikipedia

    en.wikipedia.org/wiki/Thorium-based_nuclear_power

    Learn about the history, benefits and challenges of thorium-based nuclear power generation, which uses uranium-233 produced from thorium as fuel. Find out how thorium reactors can offer advantages over uranium reactors, such as lower weaponization potential, reduced waste production and higher efficiency.

  4. 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.

  5. Clinch River Breeder Reactor Project - Wikipedia

    en.wikipedia.org/wiki/Clinch_River_Breeder...

    The Clinch River Breeder Reactor Project was a nuclear reactor project that aimed to build the USA's first large-scale demonstration breeder reactor plant. [2] It was led by the U.S. Atomic Energy Commission (and a successor agency, the U.S. Energy Research and Development Administration (ERDA), and subsequently the U.S. Department of Energy).

  6. Thorium fuel cycle - Wikipedia

    en.wikipedia.org/wiki/Thorium_fuel_cycle

    The primary physical advantage of thorium fuel is that it uniquely makes possible a breeder reactor that runs with slow neutrons, otherwise known as a thermal breeder reactor. [6] These reactors are often considered simpler than the more traditional fast-neutron breeders. Although the thermal neutron fission cross section (σ f) of the ...

  7. Reactor Overview. Small, sealed, transportable, autonomous reactor (SSTAR) is a proposed lead-cooled nuclear reactor being primarily researched and developed in the United States by Lawrence Livermore National Laboratory. It is designed as a fast breeder reactor that is passively safe.

  8. Fermi 1 - Wikipedia

    en.wikipedia.org/wiki/Fermi_1

    The plutonium created could be used to fuel the breeder core, with enough left over to run other reactors. A breeder potentially generates not only electricity, but also income through fuel sales. The first power-producing reactor was a breeder, the Experimental Breeder Reactor I (EBR-I) at what became the Idaho National Laboratory. On December ...

  9. 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.