Template:Infobox nuclear reactor
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 being used as a base for designing the Bharat small modular reactor (BSMR), for captive use by companies.[2]
The IPHWR design was later expanded into 540 MW and 700 MW designs, as well as the AHWR-300 design.
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
| 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
References
- ↑ ANU SHAKTI: Atomic Energy In India. BARC. Retrieved 2021-03-20.
- ↑ https://www.world-nuclear-news.org/articles/deadline-extended-to-allow-wider-participation-in-indian-small-reactor-rfp
- ↑ Status report 74 - Indian 220 MWe PHWR (IPHWR-220). International Automic Energy Agency(2011-04-04). Retrieved 2021-03-21.
- ↑ Fuel technology evolution for Indian PHWRs. International Atomic Energy Agency.
- ↑ 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({Template:Date).
- ↑ The Indian PHWR. Nuclear Engineering and Design({Template:Date).
- ↑ Physics design and Safety assessment of 540 MWe PHWR. BARC Newsletter({Template:Date).
- ↑ Status report 105 - Indian 700 MWe PHWR (IPHWR-700). International Atomic Energy Agency(2011-08-01). Retrieved 2021-03-20.
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