The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe sodium-cooled, fast breeder reactor that is being constructed at Kokkilamedu, near Kalpakkam, in...

5623504°N 80.1645415°E / 12.5623504; 80.1645415 The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam, Tamil Nadu, India. The Indira...

A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. These reactors can be fueled with more-commonly available...

reactor (LMR) is a type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first adapted for breeder reactor...

A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is...

The BN-800 reactor (Russian: реактор БН–800) is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk...

The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. It has...

reactor types Generation II reactor Generation III reactor Integral fast reactor Stable salt reactor Liquid fluoride thorium reactor Breeder reactor Small...

sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals...

gas-cooled fast reactor (GFR) system is a nuclear reactor design which is currently in development. Classed as a Generation IV reactor, it features a fast-neutron...

and Instrumentation Lab were constructed. The center houses a Fast Breeder Test Reactor (FBTR), which attained its first criticality in October 1985....

5 years Fast breeder reactor Fast neutron reactor Generation IV reactor Siberian Chemical Combine Design completed for prototype fast reactor, World Nuclear...

of the Integral Fast Reactor developed by Argonne National Laboratory between 1984 and 1994. It is a sodium-cooled fast breeder reactor, based on the Experimental...

development of civil fast breeder reactors, and the Vulcan Naval Reactor Test Establishment (NRTE), a military submarine reactor testing facility. Both these...

high-temperature reactors) and still have a solid fuel. Molten salt reactors, as a class, include both burners and breeders in fast or thermal spectra...

The Fast Flux Test Facility (FFTF) is a 400 MW thermal, liquid sodium cooled, nuclear test reactor owned by the U.S. Department of Energy. It does not...

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...

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)...

The IFR was a sodium-cooled fast reactor (SFR) is its closest surviving fast breeder reactor, a type of Generation IV reactor. The U.S. Department of Energy...

design. Fast breeder reactor Fast neutron reactor Gas-cooled fast reactor Generation IV reactor Integral fast reactor Sodium-cooled fast reactor Reistad...

utilise Uranium-233 produced in the fast-breeder reactors being developed by IGCAR. The Indian molten salt breeder reactor (IMSBR) is the platform to burn...

fast breeder reactor that is passively safe. It has a self-contained fuel source of uranium-235 and uranium-238 which will be partly consumed by fast-neutron...

characteristics of a fast neutron reactor, thereby combining the established and proven technology of light water reactors with the desired features of fast neutron...

the detonation of India's first nuclear explosion in 1974. India's fast breeder reactor (FBR) program is a crucial part of the nation's strategy to expand...

power plant using a thorium fuel cycle in a breeder reactor. Increased research into Generation IV reactor designs renewed interest in the 21st century...

natural nuclear fission reactor is a uranium deposit where self-sustaining nuclear chain reactions occur. The idea of a nuclear reactor existing in situ within...

Aqueous homogeneous reactors (AHR) is a two (2) chamber reactor consisting of an interior reactor chamber and an outside cooling and moderating jacket...

Cooling is provided by molten lead in a separate loop. It is a fast breeder reactor, and can use both uranium and thorium to breed fissile material,...

239 Pu is more likely to absorb a fast neutron than 235 U. Fast reactors can be breeder reactors. These reactors release enough neutrons to transmute...

A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D2O) as its coolant and neutron moderator. PHWRs...