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IPHWR
The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre. The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata, Rajasthan. The design was later expanded into 540 MW and 700 MW designs. Currently there are 17 units of various types operational at various locations in India. IPHWR-220 The first PHWR units built in India (RAPS-1 and RAPS-2) are of Canadian CANDU design similar to the first full-scale Canadian reactor built at Douglas point, Ontario. The reactors were set up in collaboration with Government of Canada. Starting in 1963, 100 MWe RAPS-1 was mostly built with equipment and technology supplied by AECL, Canada. RAPS-1 was commissioned in 1973 but the cessation of Canadian cooperation in light of successful development of nuclear weapons by India as part of Operation Smiling Buddha the RAPS-2 commissioning ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Nuclear Power In India
Nuclear power is the fifth-largest source of electricity in India after coal, gas, hydroelectricity and wind power. , India has 22 nuclear reactors in operation in 8 nuclear power plants, with a total installed capacity of 7,380 MW. Nuclear power produced a total of 43 TWh in 2020-21, contributing 3.11% of total power generation in India (1,382 TWh). 10 more reactors are under construction with a combined generation capacity of 8,000 MW. In October 2010, India drew up a plan to reach a nuclear power capacity of 63 GW in 2032. However, following the 2011 Fukushima nuclear disaster there have been numerous anti-nuclear protests at proposed nuclear power plant sites. There have been mass protests against the Jaitapur Nuclear Power Project in Maharashtra and the Kudankulam Nuclear Power Plant in Tamil Nadu, and a proposed large nuclear power plant near Haripur was refused permission by the Government of West Bengal. A Public Interest Litigation (PIL) has also been filed against t ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
IPHWR-220
The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre. It is a Generation II reactor developed from earlier CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata, Rajasthan. The design was later expanded into 540 MW and 700 MW designs. It can generate 220 MW of electricity. Currently there are 14 units operational at various locations in India. Reactor fleet Technical specifications See also * IPHWR, class of Indian PHWRs * IPHWR-700, Generation III+ successor to the IPHWR-220 design * CANDU, predecessor to Indian PHWR designs * AHWR-300, thorium fuelled PHWR design for the Indian Three stage nuclear power programme * India's three-stage nuclear power programme * Nuclear power in India Nuclear power is the fifth-largest source of electricity in India after coal, gas, hydroelectricity and wind power. , India has 22 nuclear reactors in operation i ... [...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 estima ... [...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 de ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Rajastan Atomic Power Project
The Rajasthan Atomic Power Station (RAPS; also ''Rajasthan Atomic Power Project'' - RAPP) is located at Rawatbhata in the state of Rajasthan, India. History The construction of the Douglas Point Nuclear Generating Station Canada began in 1961 with a CANDU (Canada Deuterium Uranium) pressurised heavy water reactor (PHWR) capable of producing 220 MW of electricity. Two years after the construction of the Rajasthan Power Project (RAPP) commenced, two similar reactors were built in the state of Rajasthan. Ten years later, in 1973 RAPS-1 was put into service. In 1974 after India conducted Smiling Buddha, its first nuclear weapons test Canada stopped its support of the project, delaying the commissioning of RAPS-2 until 1981. In the context of the Indian atomic program, two more PHWR with an output of 220 MW each were built. They cost around 570 million dollars. RAPS-3 became critical on 24 December 1999, RAPS-4 became critical on 3 November 2000. Commercial ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Rajasthan Atomic Power Station
The Rajasthan Atomic Power Station (RAPS; also ''Rajasthan Atomic Power Project'' - RAPP) is located at Rawatbhata in the state of Rajasthan, India. History The construction of the Douglas Point Nuclear Generating Station Canada began in 1961 with a CANDU (Canada Deuterium Uranium) pressurised heavy water reactor (PHWR) capable of producing 220 MW of electricity. Two years after the construction of the Rajasthan Power Project (RAPP) commenced, two similar reactors were built in the state of Rajasthan. Ten years later, in 1973 RAPS-1 was put into service. In 1974 after India conducted Smiling Buddha, its first nuclear weapons test Canada stopped its support of the project, delaying the commissioning of RAPS-2 until 1981. In the context of the Indian atomic program, two more PHWR with an output of 220 MW each were built. They cost around 570 million dollars. RAPS-3 became critical on 24 December 1999, RAPS-4 became critical on 3 November 2000. Commercial ope ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Tarapur Atomic Power Station
Tarapur Atomic Power Station (T.A.P.S.) is located in Tarapur, Palghar, India. It was the first commercial nuclear power station built in India. History Tarapur Atomic Power Station was constructed initially with two boiling water reactor (BWR) units under the 1963 123 Agreement between India, the United States, and the International Atomic Energy Agency (IAEA). It was built for the Department of Atomic Energy by GE and Bechtel. Units 1 and 2 were brought online for commercial operation on 28 October 1969 with an initial power of 210 MW of electricity. Later on this was reduced to 160 MW due to technical difficulties. These were the first of their kind in Asia. More recently, an additional two pressurised heavy water reactor (PHWR) units of 540 MW each were constructed by BHEL, L&T and Gammon India, seven months ahead of schedule and well within the original cost estimates. Unit 3 was brought online for commercial operation on 18 August 2006, and unit 4 ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Narora Atomic Power Station
Narora Atomic Power Station (NAPS) is a nuclear power plant located in Narora, Dibai Tehsil, Bulandshahar District in Uttar Pradesh, India. Reactors The plant houses two reactors, each a pressurized heavy-water reactor (PHWR) capable of producing 220 MW of electricity. Commercial operation of NAPS-1 began on 1 January 1991, NAPS-2 on 1 July 1992. The reactors were not originally under IAEA safeguards. but subsequent to the signing of the 1-2-3 agreement, they have been placed under IAEA monitoring with effect from 2014 Units Incidents 31 May 1993 after months of operation two steam turbine blades in NAPS-1 malfunctioned causing a major fire. This in combination with problems in the reactor's cabling system nearly led to a nuclear meltdown A nuclear meltdown (core meltdown, core melt accident, meltdown or partial core melt) is a severe nuclear reactor accident that results in core damage from overheating. The term ''nuclear meltdown'' is not offic ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
PHWR Under Construction At Kakrapar Gujarat India
A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water ( deuterium oxide D2O) as its coolant and neutron moderator. PHWRs frequently use natural uranium as fuel, but sometimes also use very low enriched uranium. The heavy water coolant is kept under pressure to avoid boiling, allowing it to reach higher temperature (mostly) without forming steam bubbles, exactly as for pressurized water reactor. While heavy water is very expensive to isolate from ordinary water (often referred to as ''light water'' in contrast to ''heavy water''), its low absorption of neutrons greatly increases the neutron economy of the reactor, avoiding the need for enriched fuel. The high cost of the heavy water is offset by the lowered cost of using natural uranium and/or alternative fuel cycles. As of the beginning of 2001, 31 PHWRs were in operation, having a total capacity of 16.5 GW(e), representing roughly 7.76% by number and 4.7% by generating capacity of all current o ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Pressurized Heavy-water Reactor
A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water ( deuterium oxide D2O) as its coolant and neutron moderator. PHWRs frequently use natural uranium as fuel, but sometimes also use very low enriched uranium. The heavy water coolant is kept under pressure to avoid boiling, allowing it to reach higher temperature (mostly) without forming steam bubbles, exactly as for pressurized water reactor. While heavy water is very expensive to isolate from ordinary water (often referred to as ''light water'' in contrast to ''heavy water''), its low absorption of neutrons greatly increases the neutron economy of the reactor, avoiding the need for enriched fuel. The high cost of the heavy water is offset by the lowered cost of using natural uranium and/or alternative fuel cycles. As of the beginning of 2001, 31 PHWRs were in operation, having a total capacity of 16.5 GW(e), representing roughly 7.76% by number and 4.7% by generating capacity of all current op ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Douglas Point Nuclear Generating Station
The Douglas Point Nuclear Generating Station was Canada’s first full-scale nuclear power plant and the second CANDU (CANada Deuterium Uranium) pressurised heavy water reactor. Its success was a major milestone and marked Canada's entry into the global nuclear power scene. The same site was later used for the Bruce Nuclear Generating Station, which was built just to the south of Douglas Point. Douglas Point was built and owned by Atomic Energy of Canada Limited (AECL) but operated by Ontario Hydro. It was in service from 26 September 1968 to 5 May 1984. The plant served as a teaching tool for the emerging Canadian nuclear industry, and the experience gained was applied to the later CANDU power plants. Design The first CANDU was a demonstration unit, the Nuclear Power Demonstrator (NPD). In 1958, before NPD was complete, AECL formed the Nuclear Power Plant Division at Ontario Hydro’s A.W. Manby Service Centre in Toronto to manage the construction of a full-scale prototype for fu ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Generation III Reactor
Generation III reactors, or Gen III reactors, are a class of nuclear reactors designed to succeed Generation II reactors, incorporating evolutionary improvements in design. These include improved fuel technology, higher thermal efficiency, significantly enhanced safety systems (including passive nuclear safety), and standardized designs intended to reduce maintenance and capital costs. They are promoted by the Generation IV International Forum (GIF). The first Generation III reactors to begin operation were Kashiwazaki 6 and 7 advanced boiling water reactors (ABWRs) in 1996 and 1997. Since 2012, both have been shut down due to security concerns. Due to the prolonged period of stagnation in the construction of new reactors and the continued (albeit declining) popularity of Generation II/II+ designs in new construction, relatively few third generation reactors have been built. Overview The older Gen II reactors comprise the vast majority of current nuclear reactors. Gen III r ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
