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Clementine was the code name for the world's first fast-neutron reactor, also known as the Los Alamos fast plutonium reactor. It was an experimental-scale reactor. The maximum output was 25 kW and was fueled by plutonium and cooled by liquid mercury. Clementine was located at Los Alamos National Laboratory in Los Alamos, New Mexico.
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 Oblast, Russia. The reactor is designed to generate 880 MW of electrical power.
The BN-350 fast-neutron reactor at Aktau, Kazakhstan.It operated between 1973 and 1994. 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 sustained by fast neutrons (carrying energies above 1 MeV, on average), as opposed to slow thermal neutrons used in thermal-neutron reactors.
It was the B Reactor that produced the first plutonium in the United States. The first supply of plutonium was delivered to the Army on February 2, 1945, just four months after the reactor began ...
, fast reactors could use all of them for fuel. All actinides can undergo neutron induced fission with unmoderated or fast neutrons. A fast reactor is therefore more efficient than a thermal reactor for using plutonium and higher actinides as fuel. These fast reactors are better suited for the transmutation of other actinides than thermal ...
PUREX (plutonium uranium reduction extraction) is a chemical method used to purify fuel for nuclear reactors or nuclear weapons. [7] PUREX is the de facto standard aqueous nuclear reprocessing method for the recovery of uranium and plutonium from used nuclear fuel ( spent nuclear fuel , or irradiated nuclear fuel).
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's cost has doubled from ₹3,500 crore to ₹7,700 crore due to the multiple delays.
The reactor uses a plutonium-uranium mixed carbide fuel and liquid sodium as a coolant. The fuel is an indigenous mix of 70 percent plutonium carbide and 30 percent uranium carbide. Plutonium for the fuel is extracted from irradiated fuel in the Madras power reactors and reprocessed in Tarapur.