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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.
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 ...
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 ...
From a big-picture perspective, NuScale Power is just a good idea right now. It has created a new nuclear reactor design that it is trying to get through the strict regulatory approval process.
A sample of thorium. Thorium-based nuclear power generation is fueled primarily by the nuclear fission of the isotope uranium-233 produced from the fertile element thorium.A thorium fuel cycle can offer several potential advantages over a uranium fuel cycle [Note 1] —including the much greater abundance of thorium found on Earth, superior physical and nuclear fuel properties, and reduced ...
In this file image shows the outside of the Unit 3 reactor containment building at Plant Vogtle in Waynesboro. Unit 3 reached “initial criticality” earlier this week, a key step in generating ...
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 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 ...