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The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian
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. Th ...
s designed by the
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 ...
. The baseline 220 MWe design was developed from the
CANDU The CANDU (Canada Deuterium Uranium) is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium oxide ( heavy water) moderator and its use of (originally, natural) uranium fuel. CA ...
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 The CANDU (Canada Deuterium Uranium) is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium oxide ( heavy water) moderator and its use of (originally, natural) uranium fuel. CA ...
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 Atomic Energy of Canada Limited (AECL) is a Canadian federal Crown corporation and Canada's largest nuclear science and technology laboratory. AECL developed the CANDU reactor technology starting in the 1950s, and in October 2011 licensed this ...
, 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 could only be completed by 1981 where some elements of the design were indigenized by
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 ...
in partnership with Indian manufacturers
Larsen & Toubro Larsen & Toubro Ltd, commonly known as L&T, is an Indian multinational conglomerate company, with business interests in engineering, construction, manufacturing, technology, information technology and financial services, headquartered in Mumb ...
and
Bharat Heavy Electricals Limited Bharat Heavy Electricals Limited (BHEL) is an Indian central public sector undertaking. It is under the ownership of Ministry of Heavy Industries, Government of India. It is based in New Delhi, India. Established in 1956, BHEL is Indi ...
. Successively, a totally Indian design of 220 MWe power capacity was designed and two units were built 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 ...
in
Tamil Nadu Tamil Nadu (; , TN) is a state in southern India. It is the tenth largest Indian state by area and the sixth largest by population. Its capital and largest city is Chennai. Tamil Nadu is the home of the Tamil people, whose Tamil languag ...
state christened MAPS-1 and MAPS-2. MAPS-1&2 design was evolved from RAPS-1&2, with modifications carried out to suit the coastal location and also introduction of suppression pool to limit containment peak pressure under
loss of coolant accident A loss-of-coolant accident (LOCA) is a mode of failure for a nuclear reactor; if not managed effectively, the results of a LOCA could result in reactor core damage. Each nuclear plant's emergency core cooling system (ECCS) exists specifically t ...
(LOCA) in lieu of dousing tanks in RAPS-1&2. In addition, MAPS-1&2 have partial double containment. This design was further improved and all subsequent PHWR units in India have double containment. With experience of design and operation of earlier units and indigenous R&D efforts, major modifications were introduced in NAPS-1&2. These units are the basis of standardized Indian PHWR units later designated as IPHWR-220. The design of subsequent units i.e. KGS-1, KGS-2, RAPS-3, RAPS-4, RAPS-5, RAPS-6, KGS-3 and KGS-4 is of standard Indian PHWR design. The major improvements in these designs include valve-less primary heat transport system and a unitized control room concept. In addition, the design of these units included improvements in Control and Instrumentation system and incorporation of computer based systems to match with the advancement in technology.


IPHWR-540

Upon completion of the design of IPHWR-220, a larger 540 MWe design was started around 1984 under the aegis of BARC in partnership with NPCIL. Two reactors of this design were built in
Tarapur, Maharashtra Tarapur is a census town in Palghar district (earlier Palghar was taluka and has recently notified as district) in the Indian state of Maharashtra. It is an industrial town located some 45 km north of Virar, on the Western Railway ...
starting in the year 2000 and the first was commissioned on 12 September 2005.


IPHWR-700

The IPHWR-540 design was later upgraded to a 700 MWe with the main objective to improve fuel efficiency and develop a standardized design to be installed at many locations across India as a fleet-mode effort. The design was also upgraded to incorporate Generation III+ features. The 700 MWe PHWR design includes some features, which are introduced for the first time in Indian PHWRs which include partial boiling at the coolant channel outlet, interleaving of primary heat transport system feeders, passive decay heat removal system, regional over power protection, containment spray system, mobile fuel transfer machine, and a steel liner on the inner containment wall.


Technical specifications


See also

* IPHWR-220, first version of the IPHWR class of recators * IPHWR-700, Generation III+ successor to the IPHWR-220 design *
CANDU The CANDU (Canada Deuterium Uranium) is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium oxide ( heavy water) moderator and its use of (originally, natural) uranium fuel. CA ...
, 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 in 8 nuclear power plants, with a total installed capacity of 7,380 MW. Nuclea ...


References

{{Nuclear fission reactors Nuclear power reactor types Indian inventions Nuclear power in India Pressurized water reactors