Jump to content
 







Main menu
   


Navigation  



Main page
Contents
Current events
Random article
About Wikipedia
Contact us
Donate
 




Contribute  



Help
Learn to edit
Community portal
Recent changes
Upload file
 








Search  

































Create account

Log in
 









Create account
 Log in
 




Pages for logged out editors learn more  



Contributions
Talk
 



















Contents

   



(Top)
 


1 Reactor fleet  





2 Technical specifications  





3 See also  





4 References  














IPHWR-220






Українська
 

Edit links
 









Article
Talk
 

















Read
Edit
View history
 








Tools
   


Actions  



Read
Edit
View history
 




General  



What links here
Related changes
Upload file
Special pages
Permanent link
Page information
Cite this page
Get shortened URL
Download QR code
Wikidata item
 




Print/export  



Download as PDF
Printable version
 
















Appearance
   

 






From Wikipedia, the free encyclopedia
 


IPHWR-220 Reactor Class
Kaiga Atomic Power Plant, showing four IPHWR-220 reactors
GenerationGeneration II reactor
Reactor conceptpressurized heavy-water reactor
Reactor lineIPHWR (Indian Pressurized Heavy-water Reactor)
Designed byBhabha Atomic Research Centre
Manufactured byPPED, DAE (now part of NPCIL)
Status14 Operational
Main parameters of the reactor core
Fuel (fissile material)235U (NU/SEU/LEU)
Fuel stateSolid
Neutron energy spectrumThermal
Primary control methodcontrol rods
Primary moderatorHeavy water
Primary coolantHeavy water
Reactor usage
Primary useGeneration of electricity
Power (thermal)754.5 MWth
Power (electric)220 MWe

The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre.[1] It is a Generation II reactor developed from earlier CANDU based RAPS-1 and 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 sometimes referred to as an small modular reactor due to its modularization.[2]

The IPHWR design was later expanded into 540 MW and 700 MW designs, as well as the AHWR-300 design.

Reactor fleet[edit]

IPHWR-220 Reactor fleet
Power station Location Operation start Status
MAPS-1 Kalpakkam, Tamil Nadu 27 January 1984 Operational
MAPS-2 21 March 1986
NAPS-1 Narora, Uttar Pradesh 1 January 1991
NAPS-2 1 July 1992
KAPS-1 Kakrapar, Gujarat 6 May 1993
KAPS-2 1 September 1995
RAPS-3 Rawatbhata, Rajasthan 1 June 2000
RAPS-4 23 December 2000
RAPS-5 4 February 2010
RAPS-6 31 March 2010
KGS-1 Kaiga, Karnataka 6 November 2000
KGS-2 6 May 2000
KGS-3 6 May 2007
KGS-4 27 November 2010

Technical specifications[edit]

Specifications IPHWR-220[3] IPHWR-540[4][5][6][7] IPHWR-700[8]
Thermal output, MWth 754.5 1730 2166
Active power, MWe 220 540 700
Efficiency, net % 27.8 28.08 29.08
Coolant temperature, °C: ?
     core coolant inlet 249 266
     core coolant outlet 293.4 310
Primary coolant material Heavy Water
Secondary coolant material Light Water
Moderator material Heavy Water
Reactor operating pressure, kg/cm2 (g) 87 100
Active core height, cm 508.5 594 594
Equivalent core diameter, cm 451 - 638.4
Average fuel power density 9.24 KW/KgU 235 MW/m3
Average core power density, MW/m3 10.13 12.1
Fuel Sintered Natural UO2 pellets
Cladding tube material Zircaloy-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 0.7% U-235
Fuel cycle length, Months 24 12
Average fuel burnup, MW · day / ton 6700 7500 7050
Control rods SS/Co Cadmium/SS
Neutron absorber Boric Anhydride Boron
Residual heat removal system Active: Shutdown cooling system

Passive: Natural circulation through steam generators

Active: Shutdown cooling system

Passive: Natural circulation through steam generators

and Passive Decay heat removal system

Safety injection system Emergency core cooling system

See also[edit]

References[edit]

  1. ^ "ANU SHAKTI: Atomic Energy In India". BARC. Archived from the original on 2020-06-26. Retrieved 2021-03-20.
  • ^ "ARIS - Technical Data". IAEA.
  • ^ "Status report 74 - Indian 220 MWe PHWR (IPHWR-220)" (PDF). International Automic Energy Agency. 2011-04-04. Retrieved 2021-03-21.
  • ^ Soni, Rakesh; Prasad, PN. "Fuel technology evolution for Indian PHWRs" (PDF). International Atomic Energy Agency. S. Vijayakumar, A.G. Chhatre, K.P.Dwivedi.
  • ^ Muktibodh, U.C (2011). "Design, Safety and Operability performances of 220 MWe, 540 MWe and 700 MWe PHWRs in India". Inter-Regional Workshop on Advanced Nuclear Reactor Technology for Near-term Deployment.
  • ^ Bajaj, S.S; Gore, A.R (2006). "The Indian PHWR". Nuclear Engineering and Design. 236 (7–8): 701–722. doi:10.1016/j.nucengdes.2005.09.028.
  • ^ Singh, Baitej (July 2006). "Physics design and Safety assessment of 540 MWe PHWR" (PDF). BARC Newsletter. 270. Archived from the original (PDF) on 2013-05-22. Retrieved 2021-03-21.
  • ^ "Status report 105 - Indian 700 MWe PHWR (IPHWR-700)" (PDF). International Atomic Energy Agency. 2011-08-01. Retrieved 2021-03-20.

  • Retrieved from "https://en.wikipedia.org/w/index.php?title=IPHWR-220&oldid=1199587022"

    Category: 
    Nuclear power reactor types
    Hidden categories: 
    Articles with short description
    Short description matches Wikidata
     



    This page was last edited on 27 January 2024, at 12:19 (UTC).

    Text is available under the Creative Commons Attribution-ShareAlike License 4.0; additional terms may apply. By using this site, you agree to the Terms of Use and Privacy Policy. Wikipedia® is a registered trademark of the Wikimedia Foundation, Inc., a non-profit organization.



    Privacy policy

    About Wikipedia

    Disclaimers

    Contact Wikipedia

    Code of Conduct

    Developers

    Statistics

    Cookie statement

    Mobile view



    Wikimedia Foundation
    Powered by MediaWiki