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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.
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 ]
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 ...
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.
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 ...
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).
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 ...
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 US EBR-2, French Phénix and others used this approach, and it is used by India's Prototype Fast Breeder Reactor and China's CFR-600. In the loop type, the heat exchangers are outside the reactor tank.