In today's world, Fast Breeder Test Reactor is a topic of great relevance and interest to a wide spectrum of the population. Its impact extends to different aspects of daily life, from science and technology to politics and culture. In this article, the various facets of Fast Breeder Test Reactor will be explored, analyzing its historical importance, its evolution over time and its influence on contemporary society. Through a multidisciplinary approach, we seek to offer a complete and detailed vision of Fast Breeder Test Reactor, allowing the reader to understand its relevance and implications in today's world.
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12°33′44″N 80°09′52″E / 12.5623504°N 80.1645415°E The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam, Tamil Nadu, India.[1] The Indira Gandhi Center for Atomic Research (IGCAR) and Bhabha Atomic Research Centre (BARC) jointly designed, constructed, and operate the reactor.
Construction started in 1972 ad it first reached criticality in October 1985,[2] making India the seventh nation to have the technology to build and operate a breeder reactor after United States, UK, France, Japan, Germany, and Russia. 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 50 kg (110 lb) 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.[citation needed] This is considered an important milestone in breeder reactor technology. On 7 March 2022 it attained the design power level of 40 MWt.[2]
Using the experience gained from the operation of the FBTR and KAMINI a 500 MWe Prototype Fast Breeder Reactor (PFBR) is in advanced stage of construction at Kalpakkam.[3]
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.
Some of the uranium is created from the transmutation of thorium bundles that are also placed in the core.[4]