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Burnup is an important factor in determining the types and abundances of isotopes produced by a fission reactor. Breeder reactors by design have high burnup compared to a conventional reactor, as breeder reactors produce more of their waste in the form of fission products, while most or all of the actinides are meant to be fissioned and destroyed.
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 ]
PFBR – 500MWe Sodium cooled fast breeder nuclear reactor, under construction. Expected completion 2015. Expected completion 2015. FBTR – 40 MW Fast Breeder Test Reactor, uses mixed (plutonium and uranium) carbide fuel
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.
Of all the reactors in the U.S., N Reactor was the most similar to the ill-fated No. 4 Reactor at the Chernobyl Nuclear Power Plant, in that it was graphite-moderated, although N Reactor used pressurized water rather than boiling water as a coolant. Like all the Hanford Site's reactors, it had no containment vessel and would never have passed ...
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 ...
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.
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. The U.S. Department of ...