Ayman at 09:34, 11 October 2025

2025-10-11T09:34:25Z

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{{short description|Indian nuclear reactor design}}
{{Infobox nuclear reactor
| name = IPHWR-220 Reactor Class
| image = File:Kaiga Atomic Power Station.jpg
| image_size = 300px
| caption = Kaiga Atomic Power Plant, showing four IPHWR-220 reactors
| concept = [[pressurized heavy-water reactor]]
| generation = [[Generation II reactor]]
| reactor_line= IPHWR
| type_label =
| type =
| design = [[Bhabha Atomic Research Centre]]
| maker = PPED, [[Department of Atomic Energy|DAE]] (now part of [[NPCIL]])
| status = 14 Operational
| fuel_type = NU_SEU_LEU
| fuel_state = Solid
| spectrum = THERMAL
| control = control rods
| coolant = [[Heavy water]]
| moderator = [[Heavy water]]

| electric = 220 MWe
| thermal = 754.5 MWth

| use = Generation of electricity
}}

The '''IPHWR-220''' ('''Indian Pressurized Heavy Water Reactor-220''') 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 |access-date=2021-03-20 |archive-date=2020-06-26 |archive-url=https://web.archive.org/web/20200626114224/http://www.barc.gov.in/about/anushakti_phwr.html |url-status=dead }}</ref> It is a [[Generation II reactor]] developed from earlier [[CANDU reactor|CANDU]] based [[Rajastan Atomic Power Project|RAPS-1]] and [[Rajastan Atomic Power Project|RAPS-2]] reactors built at [[Rawatbhata]], Rajasthan. It can generate 220 MW of electricity. Currently, there are 14 units operational at various locations in India. It is being used as a base for designing the Bharat small modular reactor (BSMR), for captive use by companies.<ref>https://www.world-nuclear-news.org/articles/deadline-extended-to-allow-wider-participation-in-indian-small-reactor-rfp</ref>

The [[IPHWR]] design was later expanded into 540 MW and [[IPHWR-700|700 MW]] designs, as well as the [[advanced heavy-water reactor|AHWR-300]] design.

== Reactor fleet ==
{| class="wikitable"
|+IPHWR-220 Reactor fleet
!Power station
!Location
!Operation start
!Status
|-
|[[Madras Atomic Power Station|MAPS-1]]
| rowspan="2" |[[Kalpakkam]], Tamil Nadu
|27 January 1984
| rowspan="14" |Operational
|-
|[[Madras Atomic Power Station|MAPS-2]]
|21 March 1986
|-
|[[Narora Atomic Power Station|NAPS-1]]
| rowspan="2" |[[Narora]], Uttar Pradesh
|1 January 1991
|-
|[[Narora Atomic Power Station|NAPS-2]]
|1 July 1992
|-
|[[Kakrapar Atomic Power Station|KAPS-1]]
| rowspan="2" |[[Surat|Kakrapar]], Gujarat
|6 May 1993
|-
|[[Kakrapar Atomic Power Station|KAPS-2]]
|1 September 1995
|-
|[[Rajastan Atomic Power Project|RAPS-3]]
| rowspan="4" |[[Rawatbhata]], Rajasthan
|1 June 2000
|-
|[[Rajastan Atomic Power Project|RAPS-4]]
|23 December 2000
|-
|[[Rajastan Atomic Power Project|RAPS-5]]
|4 February 2010
|-
|[[Rajastan Atomic Power Project|RAPS-6]]
|31 March 2010
|-
|[[Kaiga Atomic Power Station|KGS-1]]
| rowspan="4" |[[Kaiga]], Karnataka
|6 November 2000
|-
|[[Kaiga Atomic Power Station|KGS-2]]
|6 May 2000
|-
|[[Kaiga Atomic Power Station|KGS-3]]
|6 May 2007
|-
|[[Kaiga Atomic Power Station|KGS-4]]
|27 November 2010
|}

== Technical specifications ==
{| class="wikitable"
|+
!Specifications
!IPHWR-220<ref>{{Cite news|date=2011-04-04|title=Status report 74 - Indian 220 MWe PHWR (IPHWR-220)|work=International Automic Energy Agency|url=https://aris.iaea.org/PDF/IPHWR-220.pdf|access-date=2021-03-21|archive-date=2022-05-17|archive-url=https://web.archive.org/web/20220517195913/https://aris.iaea.org/PDF/IPHWR-220.pdf|url-status=dead}}</ref>
!IPHWR-540<ref>{{Cite news|last1=Soni|first1=Rakesh|last2=Prasad|first2=PN|others=S. Vijayakumar, A.G. Chhatre, K.P.Dwivedi|title=Fuel technology evolution for Indian PHWRs|work=International Atomic Energy Agency|url=https://inis.iaea.org/collection/NCLCollectionStore/_Public/37/098/37098316.pdf}}</ref><ref>{{Cite journal|last=Muktibodh|first=U.C|date=2011|title=Design, Safety and Operability performances of 220 MWe, 540 MWe and 700 MWe PHWRs in India|journal=Inter-Regional Workshop on Advanced Nuclear Reactor Technology for Near-term Deployment}}</ref><ref>{{Cite journal|last1=Bajaj|first1=S.S|last2=Gore|first2=A.R|date=2006|title=The Indian PHWR|journal=Nuclear Engineering and Design|volume=236|issue=7–8|pages=701–722|doi=10.1016/j.nucengdes.2005.09.028}}</ref><ref>{{Cite journal|last=Singh|first=Baitej|date=July 2006|title=Physics design and Safety assessment of 540 MWe PHWR|url=http://barc.gov.in/publications/nl/2006/200607-2.pdf|journal=BARC Newsletter|volume=270|access-date=2021-03-21|archive-date=2013-05-22|archive-url=https://web.archive.org/web/20130522215947/http://barc.gov.in/publications/nl/2006/200607-2.pdf|url-status=dead}}</ref>
!IPHWR-700<ref>{{Cite news|date=2011-08-01|title=Status report 105 - Indian 700 MWe PHWR (IPHWR-700)|work=International Atomic Energy Agency|url=https://aris.iaea.org/PDF/IPHWR-700.pdf|access-date=2021-03-20|archive-date=2023-04-17|archive-url=https://web.archive.org/web/20230417041219/https://aris.iaea.org/PDF/IPHWR-700.pdf|url-status=dead}}</ref>
|-
|Thermal output, MWth
|754.5
|1730
|2166
|-
|Active power, MWe
|220
|540
|700
|-
|[[Electrical efficiency|Efficiency]], net %
|27.8
|28.08
|29.08
|-
|Coolant temperature, °C:
| colspan="3" |?
|-
|     core coolant inlet
|249
| colspan="2" |266
|-
|     core coolant outlet
|293.4
| colspan="2" |310
|-
|Primary coolant material
| colspan="3" |Heavy Water
|-
|Secondary coolant material
| colspan="3" |Light Water
|-
|Moderator material
| colspan="3" |Heavy Water
|-
|Reactor operating pressure, kg/cm2 (g)
|87
| colspan="2" |100
|-
|Active core height, cm
|508.5
|594
|594
|-
|Equivalent core diameter, cm
|451
| rowspan="3" | -
|638.4
|-
|Average fuel power density
|9.24 KW/KgU
|235 MW/m3
|-
|Average core power density, MW/m3
|10.13
|12.1
|-
|Fuel
| colspan="3" |Sintered Natural UO2 pellets
|-
|Cladding tube material
|Zircaloy-2
| colspan="2" |Zircaloy-4
|-
|Fuel assemblies
|3672
|5096
|4704 fuel bundles in 392 channels
|-
|Number of fuel rods in assembly
|19 elements in 3 rings
|37
|37 elements in 4 rings
|-
|Enrichment of reload fuel
| colspan="3" |0.7% U-235
|-
|Fuel cycle length, Months
|24
| colspan="2" |12
|-
|Average fuel [[burnup]], MW · day / ton
|6700
|7500
|7050
|-
|Control rods
|SS/Co
| colspan="2" |Cadmium/SS
|-
|Neutron absorber
|Boric Anhydride
| colspan="2" |Boron
|-
|[[Residual heat removal system]]
|Active: Shutdown cooling system
Passive: Natural circulation through steam generators
| colspan="2" |Active: Shutdown cooling system
Passive: Natural circulation through steam generators

and Passive Decay heat removal system
|-
|Safety injection system
| colspan="3" |Emergency core cooling system
|}
==See also==
* [[India's three-stage nuclear power programme]]
* [[Nuclear power in India]]

== References ==
{{reflist}}
{{Nuclear power in India}}
{{Nuclear fission reactors}}

[[Category:Nuclear power reactor types]]

IPHWR-220 - Revision history

Ayman at 09:34, 11 October 2025