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The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam,
Tamil Nadu Tamil Nadu (; , TN) is the southernmost States and union territories of India, state of India. The List of states and union territories of India by area, tenth largest Indian state by area and the List of states and union territories of Indi ...
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India India, officially the Republic of India, is a country in South Asia. It is the List of countries and dependencies by area, seventh-largest country by area; the List of countries by population (United Nations), most populous country since ...
. The Indira Gandhi Center for Atomic Research ( IGCAR) and Bhabha Atomic Research Centre (BARC) jointly designed, constructed, and operate the reactor.


History

Construction started in 1972 ad it first reached criticality in , making India the seventh nation to have the technology to build and operate a breeder reactor after
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. The reactor was designed to produce 40  MW of thermal power and 13.2 MW of electrical power. The initial nuclear fuel core used in the FBTR consisted of approximately of weapons-grade plutonium. The FBTR has rarely operated at its designed capacity and had to be shut down between 1987 and 1989 due to technical problems. 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. This is considered an important milestone in breeder reactor technology. On 7 March 2022 it attained the design power level of 40 MWt. Using the experience gained from the operation of the FBTR, a 500 MWe Prototype Fast Breeder Reactor (PFBR) is in advanced stage of construction at Kalpakkam.


Technical details

The reactor uses a plutonium-
uranium Uranium is a chemical element; it has chemical symbol, symbol U and atomic number 92. It is a silvery-grey metal in the actinide series of the periodic table. A uranium atom has 92 protons and 92 electrons, of which 6 are valence electrons. Ura ...
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. Some of the uranium is created from the transmutation of thorium bundles that are also placed in the core.


References

Liquid metal fast reactors Nuclear technology in India 1985 establishments in Tamil Nadu {{India-powerstation-stub