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  2. Breeder reactor - Wikipedia

    en.wikipedia.org/wiki/Breeder_reactor

    The doubling time is the amount of time it would take for a breeder reactor to produce enough new fissile material to replace the original fuel and additionally produce an equivalent amount of fuel for another nuclear reactor. This was considered an important measure of breeder performance in early years, when uranium was thought to be scarce.

  3. Fast Breeder Test Reactor - Wikipedia

    en.wikipedia.org/wiki/Fast_Breeder_Test_Reactor

    From 1989 to 1992, the reactor operated at 1 MW. In 1993, the reactor's power level was raised to 10.5 MW. In September 2002, fuel burn-up in the FBTR for the first time reached the 100,000 megawatt-days per metric ton uranium (MWd/MTU) mark. [citation needed] This is considered an important milestone in breeder reactor technology. On 7 March ...

  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. 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.

  6. ASTRID (reactor) - Wikipedia

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

    ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) was a proposal for a 600 MW sodium-cooled fast breeder reactor (Generation IV), proposed by the Commissariat à l'énergie atomique (CEA). It was to be built on the Marcoule Nuclear Site in France.

  7. Prototype Fast Breeder Reactor - Wikipedia

    en.wikipedia.org/wiki/Prototype_Fast_Breeder_Reactor

    At first, the reactor's construction was supposed to be completed in September 2010, but there were several delays. The Prototype Fast Breeder Reactor is scheduled to be put into service in December 2024, [7] which is more than 20 years after construction began and 14 years after the original commissioning date, as of December 2023. The project ...

  8. RAPID-L - Wikipedia

    en.wikipedia.org/wiki/RAPID-L

    The RAPID-L, RAPID-L AT (L: Lunar base, A: Automatic,T: Thermoelectric) is a micro nuclear reactor concept conceived as a powerhouse for colonies on the Moon and Mars.It is based on the RAPID-series (Refueling by All Pins Integrated Design) fast breeder reactor using a liquid lithium-6 design.

  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.