IPHWR
The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian
IPHWR-220
The first PHWR units built in India
With experience of design and operation of earlier units and indigenous R&D efforts, major modifications were introduced in NAPS-1&2. These units are the basis of standardized Indian PHWR units later designated as IPHWR-220.
The design of subsequent units i.e. KGS-1, KGS-2, RAPS-3, RAPS-4, RAPS-5, RAPS-6, KGS-3 and KGS-4 is of standard Indian PHWR design. The major improvements in these designs include valve-less primary heat transport system and a unitized control room concept. In addition, the design of these units included improvements in Control and Instrumentation system and incorporation of computer based systems to match with the advancement in technology.
IPHWR-540
Upon completion of the design of IPHWR-220, a larger 540 MWe design was started c. 1984 under the aegis of BARC in partnership with NPCIL.[3] Two reactors of this design were built in Tarapur, Maharashtra starting in the year 2000 and the first was commissioned on 12 September 2005.
IPHWR-700
The IPHWR-540 design was later upgraded to a 700 MWe with the main objective to improve fuel efficiency and develop a standardized design to be installed at many locations across India as a fleet-mode effort. The design was also upgraded to incorporate Generation III+ features.
The 700 MWe PHWR design includes some features, which are introduced for the first time in Indian PHWRs which include partial boiling at the coolant channel outlet, interleaving of primary heat transport system feeders, passive decay heat removal system, regional over power protection, containment spray system, mobile fuel transfer machine, and a steel liner on the inner containment wall.[4]
By 2031–2032, NPCIL plans to construct 18 more nuclear power reactors, which together have the potential to produce 13,800 MWe of electricity. This will bring the total amount of atomic power in the energy mix to 22,480 MWe.[5]
Technical specifications
Specifications | IPHWR-220[2] | IPHWR-540[6][7][8][3] | IPHWR-700[4] |
---|---|---|---|
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 | 266 |
core coolant outlet | 293.4 | 310 | 310 |
Primary coolant material | Heavy Water | ||
Secondary coolant material | Light Water | ||
Moderator material | Heavy Water | ||
Reactor operating pressure, kg/cm2 (g) | 87 | 100 | 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 | 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
- IPHWR-220, first version of the IPHWR class of recators
- IPHWR-700, Generation III+ successor to the IPHWR-220 design
- CANDU, predecessor to Indian PHWR designs
- AHWR-300, thorium fuelled PHWR design for the Indian Three stage nuclear power programme
- India's three-stage nuclear power programme
- Nuclear power in India
References
- ^ "ANU SHAKTI: Atomic Energy In India". BARC. Archived from the original on 2020-06-26. Retrieved 2021-03-21.
- ^ a b "Status report 74 - Indian 220 MWe PHWR (IPHWR-220)" (PDF). International Automic Energy Agency. 2011-04-04. Retrieved 2021-03-21.
- ^ a b 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.
- ^ a b "Status report 105 - Indian 700 MWe PHWR (IPHWR-700)" (PDF). International Atomic Energy Agency. 2011-08-01. Retrieved 2021-03-20.
- ^ "India to add 18 more nuclear power reactors with total capacity of 13,800 MWe by 2032: NPCIL". The Indian Express. 2024-02-25. Retrieved 2024-03-04.
- ^ 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.
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