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PFBR
The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe fast breeder nuclear reactor presently being constructed at the Madras Atomic Power Station (MAPS) in Kalpakkam, India. The Indira Gandhi Centre for Atomic Research (IGCAR) is responsible for the design of this reactor. The facility builds on the decades of experience gained from operating the lower power Fast Breeder Test Reactor (FBTR). Originally planned to be commissioned in 2010, the construction of the reactor suffered from multiple delays. As of December 2021, the Prototype Fast Breeder Reactor was at an integrated commissioning stage, with completion targeted for October 2022. Background The Kalpakkam PFBR is designed to use uranium-238 to breed plutonium in a sodium-cooled fast reactor design. The surplus plutonium (or uranium-233 for thorium reactors) from each fast reactor can be used to set up more such reactors and grow the nuclear capacity in tune with India's needs for power. The PFBR is part of the three- ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Madras Atomic Power Station
Madras Atomic Power Station (MAPS) located at Kalpakkam about south of Chennai, India, is a comprehensive nuclear power production, fuel reprocessing, and waste treatment facility that includes plutonium fuel fabrication for fast breeder reactors (FBRs). It is also India's first fully indigenously constructed nuclear power station, with two units each generating 220 MW of electricity. The first and second units of the station went critical in 1983 and 1985, respectively. The station has reactors housed in a reactor building with double shell containment improving protection also in the case of a loss-of-coolant accident. An Interim Storage Facility (ISF) is also located in Kalpakkam. The facility is also home to India's first large scale fast breeder reactor of 500 MWe called the Prototype Fast Breeder Reactor operated by BHAVINI and will also be the site of first two FBR-600 commercial fast breeder reactors. History During its construction, a total of 3.8 lakh (380,00 ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
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 Kalpakkam, 80 km south of Chennai, India. It was established in 1971 as an exclusive centre dedicated to the pursuit of fast reactor science and technology, due to the vision of Dr. Vikram Sarabhai. Originally, it was called as Reactor Research Centre (RRC). It was renamed as Indira Gandhi Centre for Atomic Research (IGCAR) by the then Prime Minister of India, Rajiv Gandhi in December 1985. The centre is engaged in broad-based multidisciplinary programme of scientific research and advanced engineering directed towards the development of Fast Breeder Reactor technology, in India. History The fast reactor related research in India, originated at BARC, Mumbai. Later, RRC was established at Kalpakkam with the same mandate. The Central Works ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Indira Gandhi Centre For Atomic Research
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 Kalpakkam, 80 km south of Chennai, India. It was established in 1971 as an exclusive centre dedicated to the pursuit of fast reactor science and technology, due to the vision of Dr. Vikram Sarabhai. Originally, it was called as Reactor Research Centre (RRC). It was renamed as Indira Gandhi Centre for Atomic Research (IGCAR) by the then Prime Minister of India, Rajiv Gandhi in December 1985. The centre is engaged in broad-based multidisciplinary programme of scientific research and advanced engineering directed towards the development of Fast Breeder Reactor technology, in India. History The fast reactor related research in India, originated at BARC, Mumbai. Later, RRC was established at Kalpakkam with the same mandate. The Central Works ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Bhabha Atomic Research Centre
The Bhabha Atomic Research Centre (BARC) is India's premier nuclear research facility, headquartered in Trombay, Mumbai, Maharashtra, India. It was founded by Homi Jehangir Bhabha as the Atomic Energy Establishment, Trombay (AEET) in January 1954 as a multidisciplinary research program essential for India's nuclear program. It operates under the Department of Atomic Energy (DAE), which is directly overseen by the Prime Minister of India. BARC is a multi-disciplinary research centre with extensive infrastructure for advanced research and development covering the entire spectrum of nuclear science, chemical engineering, material sciences and metallurgy, electronic instrumentation, biology and medicine, supercomputing, high-energy physics and plasma physics and associated research for Indian nuclear programme and related areas. BARC's core mandate is to sustain peaceful applications of nuclear energy. It manages all facets of nuclear power generation, from the theoretical desi ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
India's Three Stage Nuclear Power Programme
India's three-stage nuclear power programme was formulated by Homi Bhabha, the well-known physicist, in the 1950s to secure the country's long term energy independence, through the use of uranium and thorium reserves found in the monazite sands of coastal regions of South India. The ultimate focus of the programme is on enabling the thorium reserves of India to be utilised in meeting the country's energy requirements. Thorium is particularly attractive for India, as India has only around 1–2% of the global uranium reserves, but one of the largest shares of global thorium reserves at about 25% of the world's known thorium reserves. However, thorium is more difficult to use than uranium as a fuel because it requires breeding, and global uranium prices remain low enough that breeding is not cost effective. India published about twice the number of papers on thorium as its nearest competitors, during each of the years from 2002 to 2006. The Indian nuclear establishment estimates t ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
LMFBR Schematics2
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. Breeder reactors achieve this because their neutron economy is high enough to create more fissile fuel than they use, by irradiation of a fertile material, such as uranium-238 or thorium-232, that is loaded into the reactor along with fissile fuel. Breeders were at first found attractive because they made more complete use of uranium fuel than light water reactors, but interest declined after the 1960s as more uranium reserves were found,Helmreich, J.E. ''Gathering Rare Ores: The Diplomacy of Uranium Acquisition, 1943–1954'', Princeton UP, 1986: ch. 10 and new methods of uranium enrichment reduced fuel costs. Fuel efficiency and types of nuclear waste Breeder reactors could, in principle, extract almost all of the energy contained in uranium or thorium, decreasing fuel requirements by a factor of 100 compared to widely used once-through light water reactors, which extract less than ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Breeder Reactor
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. Breeder reactors achieve this because their neutron economy is high enough to create more fissile fuel than they use, by irradiation of a fertile material, such as uranium-238 or thorium-232, that is loaded into the reactor along with fissile fuel. Breeders were at first found attractive because they made more complete use of uranium fuel than light water reactors, but interest declined after the 1960s as more uranium reserves were found,Helmreich, J.E. ''Gathering Rare Ores: The Diplomacy of Uranium Acquisition, 1943–1954'', Princeton UP, 1986: ch. 10 and new methods of uranium enrichment reduced fuel costs. Fuel efficiency and types of nuclear waste Breeder reactors could, in principle, extract almost all of the energy contained in uranium or thorium, decreasing fuel requirements by a factor of 100 compared to widely used once-through light water reactors, which extract less tha ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
AHWR-300
The advanced heavy-water reactor (AHWR) or AHWR-300 is the latest Indian design for a next-generation nuclear reactor that burns thorium in its fuel core. It is slated to form the third stage in India's three-stage fuel-cycle plan. This phase of the fuel cycle plan was supposed to be built starting with a 300MWe prototype in 2016. construction has not started and a firm date has not been set. Background Bhabha Atomic Research Centre (BARC) set up a large infrastructure to facilitate the design and development of these Advanced Heavy Water reactors. Things to be included range from materials technologies, critical components, reactor physics, and safety analysis.Bhabha Atomic Research Centre. (2013). Advanced Heavy Water Reactor (AHWR). Retrieved from http://www.iaea.org/NuclearPower/Downloadable/aris/2013/AHWR.pdf Several facilities have been set up to experiment with these reactors. The AHWR is a pressure tube type of heavy water reactor. The Government of India, Department o ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Pool Type LMFBR
A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor. Several sodium-cooled fast reactors have been built and some are in current operation, particularly in Russia. Others are in planning or under construction. For example in 2022, in the USA, TerraPower (using its Traveling Wave technology) is planning to build its own reactors along with molten salt energy storage in partnership with GEHitachi's PRISM integral fast reactor design, under the ''Natrium'' appellation in Kemmerer, Wyoming. Aside from the Russian experience, Japan, India, China, France and the USA are investing in the technology. Fuel cycle The nuclear fuel cycle employs a full actinide recycle with two major options: One is an intermediate-size (150–600 ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Fast Breeder Test Reactor
The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam, Tamil Nadu, India. The Indira Gandhi Center for Atomic Research (IGCAR) 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, 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- ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Generation IV Reactor
Generation IV reactors (Gen IV) are six nuclear reactor designs recognized by the Generation IV International Forum. The designs target improved safety, sustainability, efficiency, and cost. The most developed Gen IV reactor design is the sodium fast reactor. It has received the greatest share of funding that supports demonstration facilities, as well as two commercial reactors in Russia. One of these has been in commercial operation since 1981. Its principal Gen IV features relates its sustainable closed fuel cycle. Moir and Teller consider the molten-salt reactor, a less developed technology, as potentially having the greatest inherent safety of the six models. The very-high-temperature reactor designs operate at much higher temperatures than prior generations. This allows for high temperature electrolysis or for sulfur–iodine cycle for the efficient production of hydrogen and the synthesis of carbon-neutral fuels. The first commercial plants are not expected before 2040–2 ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Sodium-cooled Fast Reactor
A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor. Several sodium-cooled fast reactors have been built and some are in current operation, particularly in Russia. Others are in planning or under construction. For example in 2022, in the USA, TerraPower (using its Traveling Wave technology) is planning to build its own reactors along with molten salt energy storage in partnership with GEHitachi's PRISM integral fast reactor design, under the ''Natrium'' appellation in Kemmerer, Wyoming. Aside from the Russian experience, Japan, India, China, France and the USA are investing in the technology. Fuel cycle The nuclear fuel cycle employs a full actinide recycle with two major options: One is an intermediate-size (150–600 ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
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