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Fast Breeder Test Reactor

12°33′44″N 80°09′52″E / 12.5623504°N 80.1645415°E / 12.5623504; 80.1645415 The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam, Tamil Nadu, India.[1] The Indira Gandhi Center for Atomic Research (IGCAR) and Bhabha Atomic Research Centre (BARC) jointly designed, constructed, and operate the reactor.

Fast Breeder Test Reactor in Kalpakkam

History edit

It first reached criticality in October 1985 (38 years ago) (1985-10),[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 March 7, 2022 it attained the design power level of 40 MWt.[2]

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.[citation needed]

Technical details edit

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.[3]

References edit

  1. ^ . Igcar.ernet.in. 19 October 2005. Archived from the original on 5 November 2009. Retrieved 25 March 2017.
  2. ^ a b "IGCAR: Milistones". Retrieved 19 January 2023.
  3. ^ . Archived from the original on 22 March 2014. Retrieved 22 March 2014.{{cite web}}: CS1 maint: archived copy as title (link)


fast, breeder, test, reactor, this, article, needs, additional, citations, verification, please, help, improve, this, article, adding, citations, reliable, sources, unsourced, material, challenged, removed, find, sources, news, newspapers, books, scholar, jsto. This article needs additional citations for verification Please help improve this article by adding citations to reliable sources Unsourced material may be challenged and removed Find sources Fast Breeder Test Reactor news newspapers books scholar JSTOR March 2017 Learn how and when to remove this template message 12 33 44 N 80 09 52 E 12 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 1 The Indira Gandhi Center for Atomic Research IGCAR and Bhabha Atomic Research Centre BARC jointly designed constructed and operate the reactor Fast Breeder Test Reactor in KalpakkamHistory editIt first reached criticality in October 1985 38 years ago 1985 10 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 March 7 2022 it attained the design power level of 40 MWt 2 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 citation needed Technical details editThe 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 3 References edit A creditable performance at Kalpakkam Igcar ernet in 19 October 2005 Archived from the original on 5 November 2009 Retrieved 25 March 2017 a b IGCAR Milistones Retrieved 19 January 2023 Archived copy Archived from the original on 22 March 2014 Retrieved 22 March 2014 a href Template Cite web html title Template Cite web cite web a CS1 maint archived copy as title link nbsp This article about nuclear power and nuclear reactors for power generation is a stub You can help Wikipedia by expanding it vte This article about an Indian power station is a stub You can help Wikipedia by expanding it vte Retrieved from https en wikipedia org w index php title Fast Breeder Test Reactor amp oldid 1185347057, wikipedia, wiki, book, books, library,

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