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The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam, India. The Indira Gandhi Center for Atomic Research (IGCAR) and Bhabha Atomic Research Centre (BARC) jointly designed, constructed, and operate the reactor. The reactor was designed to produce 40 MW of thermal power and 13.2 MW of electrical power.
The Dhruva reactor is India's largest nuclear research reactor.It was the first nuclear reactor in Asia proper. [1] Located in the Mumbai suburb of Trombay at the Bhabha Atomic Research Centre (BARC), it is India's primary generator of weapons-grade plutonium-bearing spent fuel for its nuclear weapons program.
The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre. [1] It is a Generation II reactor developed from earlier CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata, Rajasthan. It can generate 220 MW of electricity.
The proposed design of the AHWR is that of a heavy-water-moderated nuclear power reactor that will be the next generation of the PHWR type. It is being developed at Bhabha Atomic Research Centre (BARC), in Mumbai, India and aims to meet the objectives of using thorium fuel cycles for commercial power generation. The AHWR is a vertical pressure ...
In August 1956, the one-megawatt "swimming-pool" research reactor APSARA was commissioned, making India the first Asian country besides the Soviet Union to have a nuclear reactor. Running on enriched natural uranium fuel supplied by the United Kingdom Atomic Energy Commission and thorium, APSARA represented the first stage of Bhabha's plan: it ...
The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre. [1] The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata, Rajasthan.
CIRUS (Canada India Reactor Utility Services) [1] [2] [3] was a research reactor at the Bhabha Atomic Research Center (BARC) in Trombay near Mumbai, India. CIRUS was supplied by Canada in 1954, but used heavy water (deuterium oxide) supplied by the United States. It was the second nuclear reactor to be built in India.
After Canada withdrew from the project, research, design and development work in the Bhabha Atomic Research Centre and Nuclear Power Corporation of India (NPCIL) enabled India to proceed without assistance. India took help of Soviet Union whose VVER(Pressurised Water Reactor type) technology was used as a design for indigenization. Some ...