IPHWR-220
| 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]
The IPHWR design was later expanded into 540 MW and 700 MW designs, as well as the AHWR-300 design.
Reactor fleet
[edit]| 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]- ^ "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.
