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A breeder reactor is a nuclear reactor that generates more fissile ... In addition to this simple mass difference, the reactor gets two chances to fission the nuclei ...
Experimental Breeder Reactor I (EBR-I) is a decommissioned research reactor and U.S. National Historic Landmark located in the desert about 18 miles (29 km) southeast of Arco, Idaho. It was the world's first breeder reactor . [ 3 ]
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 ...
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 ...
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.
Much of their work culminated with the Molten-Salt Reactor Experiment (MSRE). MSRE was a 7.4 MW th test reactor simulating the neutronic "kernel" of a type of epithermal thorium molten salt breeder reactor called the liquid fluoride thorium reactor (LFTR). The large (expensive) breeding blanket of thorium salt was omitted in favor of neutron ...
Schematic diagram showing the difference between the Pool and Loop designs of a liquid metal fast breeder reactor. The two main design approaches to sodium-cooled reactors are pool type and loop type. In the pool type, the primary coolant is contained in the main reactor vessel, which therefore includes the reactor core and a heat exchanger.
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 ...