The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at

Kalpakkam Kalpakkam is a township in Tamil Nadu, India, situated on the Coromandel Coast 70 kilometres south of Chennai. A conglomerate of two villages (Puduppattinam and Sadurangappatinam) and a DAE township, it is about from Thiruvanmiyur and fro ...

, Tamil Nadu, India. The Indira Gandhi Center for Atomic Research (

IGCAR Indira Gandhi Centre for Atomic Research (IGCAR) is one of India's premier nuclear research centres. It is the second largest establishment of the Department of Atomic Energy (DAE), next to Bhabha Atomic Research Centre (BARC), located at Kal ...

) and Bhabha Atomic Research Centre (BARC) jointly designed, constructed, and operate the reactor.

History

It first reached criticality in , making India the seventh nation to have the technology to build and operate a breeder reactor after United States, UK, France,

Japan Japan ( ja, 日本, or , and formally , ''Nihonkoku'') is an island country in East Asia. It is situated in the northwest Pacific Ocean, and is bordered on the west by the Sea of Japan, while extending from the Sea of Okhotsk in the north ...

, 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 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 March 7, 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 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