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. 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.
The IPHWR design was later expanded into 540 MW and 700 MW designs, as well as the AHWR-300 design.
Reactor fleet +IPHWR-220 Reactor fleetPower stationLocationOperation startStatusMAPS-1Kalpakkam, Tamil Nadu27 January 1984OperationalMAPS-221 March 1986NAPS-1Narora, Uttar Pradesh1 January 1991NAPS-21 July 1992KAPS-1Kakrapar, Gujarat6 May 1993KAPS-21 September 1995RAPS-3 Rawatbhata, Rajasthan1 June 2000RAPS-423 December 2000RAPS-54 February 2010RAPS-631 March 2010KGS-1Kaiga, Karnataka6 November 2000KGS-26 May 2000KGS-36 May 2007KGS-427 November 2010
Technical specifications +SpecificationsIPHWR-220IPHWR-540IPHWR-700Thermal output, MWth754.517302166Active power, MWe220540700Efficiency, net %27.828.0829.08Coolant temperature, °C:? core coolant inlet249266 core coolant outlet293.4310Primary coolant materialHeavy WaterSecondary coolant materialLight WaterModerator materialHeavy WaterReactor operating pressure, kg/cm2 (g)87100Active core height, cm508.5594594Equivalent core diameter, cm451 -638.4Average fuel power density9.24 KW/KgU235 MW/m3Average core power density, MW/m310.1312.1FuelSintered Natural UO2 pelletsCladding tube materialZircaloy-2Zircaloy-4Fuel assemblies367250964704 fuel bundles in 392 channelsNumber of fuel rods in assembly19 elements in 3 rings3737 elements in 4 ringsEnrichment of reload fuel0.7% U-235Fuel cycle length, Months2412Average fuel burnup, MW · day / ton670075007050Control rodsSS/CoCadmium/SSNeutron absorberBoric AnhydrideBoronResidual heat removal systemActive: Shutdown cooling system Passive: Natural circulation through steam generatorsActive: Shutdown cooling system Passive: Natural circulation through steam generators
and Passive Decay heat removal systemSafety injection systemEmergency core cooling system See also India's three-stage nuclear power programme Nuclear power in India
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