IPHWR

From Wikipedia, the free encyclopedia

The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre.[1] The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata, Rajasthan. The design was later expanded into 540 MW and 700 MW designs. Currently there are 17 units of various types operational at various locations in India.

IPHWR-220[]

Main article: IPHWR-220

The first PHWR units built in India (RAPS-1 and RAPS-2) are of Canadian CANDU design similar to the first full-scale Canadian reactor built at Douglas point, Ontario. The reactors were set up in collaboration with Government of Canada. Starting in 1963, 100 MWe RAPS-1 was mostly built with equipment and technology supplied by AECL, Canada. RAPS-1 was commissioned in 1973 but the cessation of Canadian cooperation in light of successful development of nuclear weapons by India as part of Operation Smiling Buddha the RAPS-2 commissioning could only be completed by 1981 where some elements of the design were indigenized by Bhabha Atomic Research Centre in partnership with Indian manufacturers Larsen & Toubro and Bharat Heavy Electricals Limited. Successively, a totally Indian design of 220 MWe power capacity was designed and two units were built at Kalpakkam in Tamil Nadu state christened MAPS-1 and MAPS-2. MAPS-1&2 design was evolved from RAPS-1&2, with modifications carried out to suit the coastal location and also introduction of suppression pool to limit containment peak pressure under loss of coolant accident (LOCA) in lieu of dousing tanks in RAPS-1&2. In addition, MAPS-1&2 have partial double containment. This design was further improved and all subsequent PHWR units in India have double containment.[2]

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 around 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[]

Main article: 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]

Technical specifications[]

Specifications IPHWR-220[2] IPHWR-540[5][6][7][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[]

References[]

  1. ^ "ANU SHAKTI: Atomic Energy In India". BARC.
  2. ^ a b "Status report 74 - Indian 220 MWe PHWR (IPHWR-220)" (PDF). International Automic Energy Agency. 2011-04-04. Retrieved 2021-03-21.{{cite news}}: CS1 maint: url-status (link)
  3. ^ a b Singh, Baitej (July 2006). "Physics design and Safety assessment of 540 MWe PHWR" (PDF). BARC Newsletter. 270.
  4. ^ a b "Status report 105 - Indian 700 MWe PHWR (IPHWR-700)" (PDF). International Atomic Energy Agency. 2011-08-01. Retrieved 2021-03-20.{{cite news}}: CS1 maint: url-status (link)
  5. ^ Soni, Rakesh; Prasad, PN. "Fuel technology evolution for Indian PHWRs" (PDF). International Atomic Energy Agency. S. Vijayakumar, A.G. Chhatre, K.P.Dwivedi.{{cite news}}: CS1 maint: url-status (link)
  6. ^ 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.
  7. ^ 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.
Retrieved from ""