IPHWR-700

The IPHWR-700 (Indian Pressurized Heavy Water Reactor-700) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre.[1] It is a Generation III+ reactor developed from earlier CANDU based 220 MW and 540 MW designs. It can generate 700 MW of electricity. Currently there are 6 units under construction and 10 more units planned, at a cost of INR 1.05 trillion (US$ 14 billion total or US$2000 per kWe).

IPHWR-700 Reactor Class
Kakrapar Atomic Power Station reactor units 3 and 4, under construction in the Indian state of Gujarat
GenerationGeneration III reactor
Reactor conceptpressurized heavy-water reactor
Reactor lineIPHWR
Status
  • 1 completed
  • 5 under construction
  • 10 planned
Main parameters of the reactor core
Fuel (fissile material)235U (NU/SEU/LEU)
Fuel stateSolid
Neutron energy spectrumThermal
Primary control methodcontrol rods
Primary moderatorHeavy water
Primary coolantHeavy water
Reactor usage
Primary useGeneration of electricity
Power (thermal)2166 MWth
Power (electric)700 MWe

Development

PHWR technology was introduced in India in the late 1960s with the construction of RAPS-1, a CANDU reactor in Rajasthan. All the main components for the first unit were supplied by Canada. India did the construction, installation and commissioning. In 1974, after India conducted Smiling Buddha, its first nuclear weapons test, Canada stopped their support of the project. This delayed the commissioning of RAPS-2 until 1981.[2]

After Canada withdrew from the project, research, design and development work in the Bhabha Atomic Research Centre and Nuclear Power Corporation of India (NPCIL) enabled India to proceed without assistance. Some industry partners did manufacturing and construction work. Over four decades, fifteen 220-MW reactors of indigenous design were built. Improvements were made in the original CANDU design to reduce construction time and cost. New safety systems were incorporated. Reliability was enhanced, bringing better capacity factors and lower costs.

To get economies of scale, NPIL developed a 540 MW design. Two of these were constructed at the Tarapur Atomic Power Station.

After a redesign to utilise excess thermal margins, the 540 MW PHWR design achieved a 700 MW capacity without many design changes. Almost 100% of the parts of these indigenously designed reactors are manufactured by Indian industry.[3]

Design
I-PHWR700 Model installed in GCNEP Office, Haryana

Like other pressurized heavy-water reactors, IPHWR-700 uses heavy water (deuterium oxide, D2O) as its coolant and neutron moderator. The design retains the features of other standardized Indian PHWR units, which include:[4]

  • Two diverse and fast acting shutdown systems
  • Double containment of reactor building
  • A water filled calandria vault
  • An integral calandria - end shield assembly
  • Zr-2.5% Nb pressure tubes separated from respective calandria tubes
  • A calandria tube filled with carbon dioxide (which is recirculated) to monitor pressure tube leak

It also has some new features as well, including:

  • Partial boiling at the coolant channel outlet
  • Interleaving of primary heat transport system feeders
  • A system to remove passive decay heat
  • Regional protection from over power
  • A containment spray system
  • A mobile fuel transfer machine
  • A steel lined containment wall

The reactor has less excess reactivity. Therefore, it does not need neutron poison inside the fuel or moderator. These designs handle the case of a loss of coolant accident such as occurred in the Fukushima Daiichi nuclear disaster.[5]

Operation

The reactor fuel uses 0.7% enriched uranium with Zircaloy-4 cladding. The core produces 2166 MW of heat which is converted into 700 MW of electricity at an efficiency of 32%. Because there is less excess reactivity inside the reactor, it needs to be refuelled continually during operation. The reactor is designed for an estimated life of 40 years.[6]

The Unit 3 of KAPS was connected to the grid on 10 January 2020.[7]

Reactor fleet
IPHWR-700 Reactor fleet
Power station OperatorStateUnitsTotal capacity
StatusOperation start
In Operation
Kakrapar Unit 3 NPCILGujarat700 x 1700Operational2021[7][8]
Under Construction
Kakrapar Unit 4 NPCILGujarat700 x 1700Under construction2021
Rajasthan Unit 7 and 8 NPCILRajasthan700 x 21,4002022[9]
Gorakhpur Unit 1 and 2 NPCILHaryana700 x 21,4002025[9][10]
Planned
Mahi Banswara NPCILRajasthan700 x 42,800PlannedTBD
Kaiga NPCILKarnataka700 x 21,400
Chutka NPCILMadhya Pradesh700 x 21,400
Gorakhpur NPCILHaryana700 x 21,400

References
  1. "ANU SHAKTI: Atomic Energy In India". BARC.
  2. "Rajasthan Atomic Power Station (RAPS)". Nuclear Threat Initiative. 1 September 2003. Retrieved 18 February 2017.
  3. "Pressurised Heavy Water Reactor". PIB. Dr. S Banerjee.
  4. "Status report 105 - Indian 700 MWe PHWR (IPHWR-700)" (PDF). IAEA.
  5. "Advanced Large Water Cooled Reactors" (PDF). IAEA.
  6. "Advanced Large Water Cooled Reactors" (PDF). IAEA.
  7. "Unit 3 of Kakrapar nuclear plant synchronised to grid". Live Mint. 10 January 2020. Retrieved 18 January 2020.
  8. "Bright prospects for India's future fleet". Nuclear Engineering International. Retrieved 2020-04-13.
  9. "Annual Report 2018-19 DAE" (PDF). Department of Atomic Energy. Retrieved 13 February 2020.
  10. "First phase Gorakhpur Haryana Atomic Power Plant expected to be completed in 2025". Business Standard. Retrieved 2 January 2019.
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