| IPHWR-220 Reactor Class | |
| Concept: | pressurized heavy-water reactor |
| Generation: | Generation II reactor |
| Reactor Line: | IPHWR |
| Design: | Bhabha Atomic Research Centre |
| Maker: | PPED, 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.[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.
| 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 | ||
| 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 |
| 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 systemPassive: Natural circulation through steam generators | Active: Shutdown cooling systemPassive: Natural circulation through steam generators and Passive Decay heat removal system | ||
| Safety injection system | Emergency core cooling system | |||