https://indianpedia.org/index.php?action=history&feed=atom&title=Fast_Breeder_Test_ReactorFast Breeder Test Reactor - Revision history2026-07-30T20:06:51ZRevision history for this page on the wikiMediaWiki 1.45.4https://indianpedia.org/index.php?title=Fast_Breeder_Test_Reactor&diff=59815&oldid=prev>BrownHairedGirl at 01:51, 26 March 20212021-03-26T01:51:23Z<p></p>
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The '''Fast Breeder Test Reactor''' ('''FBTR''') is a [[breeder reactor]] located at [[Kalpakkam]], [[India]].<ref>{{cite web |url=http://www.igcar.ernet.in/press_releases/press15.htm |title=A creditable performance at Kalpakkam |website=Igcar.ernet.in |date=2005-10-19 |access-date=2017-03-25 |archive-url=https://web.archive.org/web/20091105165909/http://www.igcar.ernet.in/press_releases/press15.htm |archive-date=5 November 2009 |url-status=dead }}</ref> The Indira Gandhi Center for Atomic Research ([[IGCAR]]) and [[Bhabha Atomic Research Centre]] (BARC) jointly designed, constructed, and operate the reactor.<br />
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==History==<br />
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It first reached criticality in October 1985, 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&nbsp;[[Megawatt|MW]] of thermal power and 13.2&nbsp;MW of electrical power. The initial nuclear fuel core used in the FBTR consisted of approximately 50&nbsp;kg of weapons-grade [[plutonium]]. <br />
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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&nbsp;MW. <br />
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In 1993, the reactor's power level was raised to 10.5&nbsp;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. <br />
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Using the experience gained from the operation of the FBTR, a 500&nbsp;MWe [[Prototype Fast Breeder Reactor]] ([[PFBR]]) is in advanced stage of construction at Kalpakkam.<br />
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==Technical details==<br />
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 Atomic Power Station|Tarapur]].<br />
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Some of the uranium is created from the transmutation of thorium bundles that are also placed in the core.<ref>{{cite web |url=http://dst.gov.in/whats_new/press-release13/pib_27-02-2013_4.htm |title=Archived copy |access-date=2014-03-22 |url-status=dead |archive-url=https://web.archive.org/web/20140322030151/http://dst.gov.in/whats_new/press-release13/pib_27-02-2013_4.htm |archive-date=2014-03-22 }}</ref><br />
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==References==<br />
{{Reflist}}<br />
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{{Nuclear power in India}}<br />
{{nuclear fission reactors}}<br />
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[[Category:Liquid metal fast reactors]]<br />
[[Category:Nuclear technology in India]]<br />
[[Category:1985 establishments in Tamil Nadu]]<br />
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