16,952
edits
m
clean up
>Sngineer (→Reactor fleet: Change rowspan structure to improve readability) |
CleanupBot (talk | contribs) m (clean up) |
||
| Line 28: | Line 28: | ||
}} | }} | ||
The '''IPHWR-700''' ('''Indian Pressurized Heavy Water Reactor-700''') is an Indian [[pressurized heavy-water reactor]] designed by the [[Bhabha Atomic Research Centre]].<ref>{{cite web |title=ANU SHAKTI: Atomic Energy In India |url=http://www.barc.gov.in/about/anushakti_phwr.html |publisher=BARC}}</ref> It is a [[Generation III+ reactor]] developed from earlier [[CANDU reactor|CANDU]] based 220 MW and 540 MW designs. It can generate 700 MW of electricity. Currently there are 6 units under construction and 10 more units planned, at a cost of INR 1.05 trillion (US$ 14 billion total or US$2000 per kWe). | The '''IPHWR-700''' ('''Indian Pressurized Heavy Water Reactor-700''') is an Indian [[pressurized heavy-water reactor]] designed by the [[Bhabha Atomic Research Centre]].<ref>{{cite web |title=ANU SHAKTI: Atomic Energy In India |url=http://www.barc.gov.in/about/anushakti_phwr.html |publisher=BARC}}</ref> It is a [[Generation III+ reactor]] developed from earlier [[CANDU reactor|CANDU]] based 220 MW and 540 MW designs. It can generate 700 MW of electricity. Currently there are 6 units under construction and 10 more units planned, at a cost of INR 1.05 trillion (US$14 billion total or US$2000 per kWe). | ||
== Development == | == Development == | ||
| Line 40: | Line 40: | ||
==Design== | ==Design== | ||
[[File:I-PHWR700 Model.png|thumb|I-PHWR700 Model | [[File:I-PHWR700 Model.png|thumb|I-PHWR700 Model installed in GCNEP Office, Haryana]] | ||
Like other [[pressurized heavy-water reactor]]s, IPHWR-700 uses [[heavy water]] (deuterium oxide, D<sub>2</sub>O) as its [[Nuclear reactor coolant|coolant]] and [[neutron moderator]]. The design retains the features of other standardized Indian PHWR units, which include:<ref>{{cite web |title=Status report 105 - Indian 700 MWe PHWR (IPHWR-700) |url=https://aris.iaea.org/PDF/IPHWR-700.pdf |publisher=IAEA}}</ref> | Like other [[pressurized heavy-water reactor]]s, IPHWR-700 uses [[heavy water]] (deuterium oxide, D<sub>2</sub>O) as its [[Nuclear reactor coolant|coolant]] and [[neutron moderator]]. The design retains the features of other standardized Indian PHWR units, which include:<ref>{{cite web |title=Status report 105 - Indian 700 MWe PHWR (IPHWR-700) |url=https://aris.iaea.org/PDF/IPHWR-700.pdf |publisher=IAEA}}</ref> | ||