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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 ...
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 ...
Fast Breeder Operational 65,000 2010-07-21 Chinese Experimental Fast Reactor (65 MW, 20 MWe, sodium cooled fast-spectrum neutron reactor). Located at CIAE Beijing, construction started May 2000, first criticality July 2010. MNSR-SZ Shenzhen: Mnsr Operational 30 1988-11-01 SPR IAE Beijing: Pool Operational 3,500 1964-12-20
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.
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 ...
The FFTF is not a breeder reactor itself, but rather a sodium-cooled fast neutron reactor, as the name suggests. It is stated on the site dedicated to the FFTF, that it tested "advanced nuclear fuels, materials, components, nuclear power plant operations and maintenance protocols, and reactor safety designs." By 1993, the number of uses to ...
The prototype fast breeder reactor has a negative void coefficient, thus ensuring a high level of passive nuclear safety. This means that when the reactor overheats (below the boiling point of sodium) the speed of the fission chain reaction decreases, lowering the power level and the temperature. [25]
Superphénix was a 1,242 MWe fast breeder reactor with the twin goals of reprocessing nuclear fuel from France's line of conventional nuclear reactors, while also being an economical generator of power on its own. As of 2024, Superphénix remains the largest breeder reactor ever built.