IPHWR-220

IPHWR-220 Reactor Class
IPHWR-220 Reactor Class
	Kaiga Atomic Power Plant, showing four IPHWR-220 reactors
Generation	Generation II reactor
Reactor concept	pressurized heavy-water reactor
Reactor line	IPHWR (Indian Pressurized Heavy-water Reactor)
Designed by	Bhabha Atomic Research Centre
Manufactured by	PPED, DAE (now part of NPCIL)
Status	14 Operational
Main parameters of the reactor core
Fuel (fissile material)	235U (NU/SEU/LEU)
Fuel state	Solid
Neutron energy spectrum	Thermal
Primary control method	control rods
Primary moderator	Heavy water
Primary coolant	Heavy water
Reactor usage
Primary use	Generation 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 a small modular reactor due to its modularization.^[2]

Quick Facts Generation, Reactor concept ...

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

Power station	Location	Operation start	Status
MAPS-1	Kalpakkam, Tamil Nadu	27 January 1984	Operational
MAPS-2	Kalpakkam, Tamil Nadu	21 March 1986
NAPS-1	Narora, Uttar Pradesh	1 January 1991
NAPS-2	Narora, Uttar Pradesh	1 July 1992
KAPS-1	Kakrapar, Gujarat	6 May 1993
KAPS-2	Kakrapar, Gujarat	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

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

Reactor fleet