CleanupBot at 04:18, 2 January 2022

2022-01-02T04:18:27Z

New page

{{short description|Indian nuclear reactor design}}
{{Infobox nuclear reactor
| name = IPHWR-700 Reactor Class
| image = PHWR under Construction at Kakrapar Gujarat India.jpg
| image_size = 300px
| caption = [[Kakrapar Atomic Power Station]] reactor units 3 and 4, under construction in the Indian state of [[Gujarat]]
| concept = [[pressurized heavy-water reactor]]
| generation = [[Generation III reactor]]
| reactor_line= IPHWR
| type_label =
| type =
| design = [[Bhabha Atomic Research Centre]]
| maker = [[NPCIL]]
| status = *1 completed
*5 under construction
*10 planned
| fuel_type = NU_SEU_LEU
| fuel_state = Solid
| spectrum = THERMAL
| control = control rods
| coolant = [[Heavy water]]
| moderator = [[Heavy water]]

| electric = 700 MWe
| thermal = 2166 MWth

| use = Generation of electricity
}}

The '''IPHWR-700''' ('''Indian Pressurized Heavy Water Reactor-700''') is an Indian [[pressurized heavy-water reactor]] designed by the [[Bhabha Atomic Research Centre]].<ref>{{cite web |title=ANU SHAKTI: Atomic Energy In India |url=http://www.barc.gov.in/about/anushakti_phwr.html |publisher=BARC}}</ref> It is a [[Generation III+ reactor]] developed from earlier [[CANDU reactor|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).

== Development ==
PHWR technology was introduced in India in the late 1960s with the construction of [[Rajasthan Atomic Power Station|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.<ref name=nti>{{cite web|url= http://www.nti.org/learn/facilities/76/ |title= Rajasthan Atomic Power Station (RAPS) |publisher= [[Nuclear Threat Initiative]] |date= 1 September 2003 |accessdate= 18 February 2017}}</ref>

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, NPCIL 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.<ref>{{cite web |title=Pressurised Heavy Water Reactor |url=https://pib.gov.in/newsite/mbErel.aspx?relid=166852 |website=PIB |publisher=Dr. S Banerjee}}</ref>

==Design==
[[File:I-PHWR700 Model.png|thumb|I-PHWR700 Model installed in GCNEP Office, Haryana]]
Like other [[pressurized heavy-water reactor]]s, IPHWR-700 uses [[heavy water]] (deuterium oxide, D2O) as its [[Nuclear reactor coolant|coolant]] and [[neutron moderator]]. The design retains the features of other standardized Indian PHWR units, which include:<ref>{{cite web |title=Status report 105 - Indian 700 MWe PHWR (IPHWR-700) |url=https://aris.iaea.org/PDF/IPHWR-700.pdf |publisher=IAEA}}</ref>

*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]].<ref>{{cite web |title=Advanced Large Water Cooled Reactors |url=https://aris.iaea.org/Publications/IAEA_WRC_Booklet.pdf |publisher=IAEA}}</ref>

==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.<ref>{{cite web |title=Advanced Large Water Cooled Reactors |url=https://aris.iaea.org/Publications/IAEA_WRC_Booklet.pdf |publisher=IAEA}}</ref>

Unit 3 of [[Kakrapar Atomic Power Station]] was connected to the grid on 10 January 2021.<ref name="lm-102021">{{cite web|url=https://www.livemint.com/industry/energy/unit-3-of-kakrapar-nuclear-plant-synchronised-to-grid-11610365657066.html|title=Unit 3 of Kakrapar nuclear plant synchronised to grid|publisher=Live Mint|date=10 January 2021|access-date=18 January 2021}}</ref>

==Reactor fleet==
{| class="wikitable"
|+IPHWR-700 Reactor fleet
! Power station
!Location
! Operator !! Units !! data-sort-type="numeric"|Total capacity !!Status !!Operation start
|-
! colspan=7 |In Operation
|-
| [[Kakrapar Atomic Power Station|KAPS-3]]
|[[Surat|Kakrapar]], Gujarat
| [[Nuclear Power Corporation of India|NPCIL]] || align="center" |700 x 1 || align="right"|700 ||align="center"| Operational|| 2021<ref name="lm-102021"/><ref>{{cite web|accessdate=2020-04-13|title=Bright prospects for India’s future fleet|url=https://www.neimagazine.com/features/featurebright-prospects-for-indias-future-fleet-5901895/|website=Nuclear Engineering International}}</ref>
|-
! colspan=7 |Under Construction
|-
| [[Kakrapar Atomic Power Station|KAPS-4]]
|[[Surat|Kakrapar]], Gujarat
| rowspan="5" | [[Nuclear Power Corporation of India|NPCIL]] || align="center" |700 x 1 || align="right"|700 || rowspan="5" align="center" | Under construction||2021
|-
|[[Rajastan Atomic Power Project|RAPS-7]]
| rowspan="2" |[[Rawatbhata]], Rajasthan
| rowspan="2" |700 x 2
| rowspan="2" align="right"|1400
| rowspan="2" |2022<ref name="AR_DAE" />
|-
| [[Rajastan Atomic Power Project|RAPS-8]]
|-
| [[Gorakhpur Nuclear Power Plant|GHAVP-1]]
| rowspan="2" |[[Gorakhpur, Haryana|Gorakhpur]], Haryana
| rowspan="2" |700 x 2
| rowspan="2" align="right"|1400|| rowspan="2" |2025<ref name="AR_DAE">{{cite web|url=http://www.dae.gov.in/writereaddata/DAR2018-2019.pdf|title=Annual Report 2018-19 DAE|publisher=Department of Atomic Energy|accessdate=13 February 2020}}</ref><ref>{{cite web|url=https://www.business-standard.com/article/news-cm/first-phase-gorakhpur-haryana-atomic-power-plant-expected-to-be-completed-in-2025-119010200627_1.html|title= First phase Gorakhpur Haryana Atomic Power Plant expected to be completed in 2025 |publisher=Business Standard|accessdate=2 January 2019}}</ref>
|-
|[[Gorakhpur Nuclear Power Plant|GHAVP-2]]
|-
! colspan=7 |Planned
|-

| [[Banswara|Mahi Banswara]]
|[[Banswara]], Rajasthan
| rowspan="6" | [[Nuclear Power Corporation of India|NPCIL]] || align="center" |700 x 4 || align="right"|2,800 || rowspan="6" align="center" |Planned || rowspan="6" |TBD
|-
| [[Kaiga Atomic Power Station|KGS-5]]
| rowspan="2" |[[Kaiga]], Karnataka|| rowspan="2" align="center" |700 x 2 || rowspan="2" align="right" |1400
|-
|[[Kaiga Atomic Power Station|KGS-6]]
|-
|[[Chutka Nuclear Power Plant|Chutka]]
|Chutka, Madhya Pradesh
|700 x 2
|align="right"|1400
|-
| [[Gorakhpur Nuclear Power Plant|GHAVP-3]]
| rowspan="2" |[[Gorakhpur, Haryana|Gorakhpur]], Haryana
| rowspan="2" |700 x 2
| rowspan="2" align="right"|1400
|-
|[[Gorakhpur Nuclear Power Plant|GHAVP-4]]
|}

== Technical specifications ==
{| class="wikitable"
!Specifications
!IPHWR-220<ref name="aris_220">{{Cite news|date=2011-04-04|title=Status report 74 - Indian 220 MWe PHWR (IPHWR-220)|work=International Automic Energy Agency|url=https://aris.iaea.org/PDF/IPHWR-220.pdf|url-status=live|access-date=2021-03-21}}</ref>
!IPHWR-540<ref>{{Cite news|last=Soni|first=Rakesh|last2=Prasad|first2=PN|others=S. Vijayakumar, A.G. Chhatre, K.P.Dwivedi|title=Fuel technology evolution for Indian PHWRs|work=International Atomic Energy Agency|url=https://inis.iaea.org/collection/NCLCollectionStore/_Public/37/098/37098316.pdf|url-status=live}}</ref><ref>{{Cite journal|last=Muktibodh|first=U.C|date=2011|title=Design, Safety and Operability performances of 220 MWe, 540 MWe and 700 MWe PHWRs in India|journal=Inter-Regional Workshop On Advanced Nuclear Reactor Technology for Near-term Deployment}}</ref><ref>{{Cite journal|last=Bajaj|first=S.S|last2=Gore|first2=A.R|date=2006|title=The Indian PHWR|journal=Nuclear Engineering and Design|volume=236|pages=701–722|doi=10.1016/j.nucengdes.2005.09.028}}</ref><ref name="baitej">{{Cite journal|last=Singh|first=Baitej|date=July 2006|title=Physics design and Safety assessment of 540 MWe PHWR|url=http://barc.gov.in/publications/nl/2006/200607-2.pdf|journal=BARC Newsletter|volume=270}}</ref>
!IPHWR-700<ref name="aris_700">{{Cite news|date=2011-08-01|title=Status report 105 - Indian 700 MWe PHWR (IPHWR-700)|work=International Atomic Energy Agency|url=https://aris.iaea.org/PDF/IPHWR-700.pdf|url-status=live|access-date=2021-03-20}}</ref>
|-
|Thermal output, MWth
|754.5
|1730
|2166
|-
|Active power, MWe
|220
|540
|700
|-
|[[Electrical efficiency|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
| colspan="3" |Heavy Water
|-
|Secondary coolant material
| colspan="3" |Light Water
|-
|Moderator material
| colspan="3" |Heavy Water
|-
|Reactor operating pressure, kg/cm2 (g)
|87
|100
|100
|-
|Active core height, cm
|508.5
|594
|594
|-
|Equivalent core diameter, cm
|451
| rowspan="3" | -
|638.4
|-
|Average fuel power density
|9.24 KW/KgU
|235 MW/m3
|-
|Average core power density, MW/m3
|10.13
|12.1
|-
|Fuel
| colspan="3" |Sintered Natural UO2 pellets
|-
|Cladding tube material
|Zircaloy-2
| colspan="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
| colspan="3" |0.7% U-235
|-
|Fuel cycle length, Months
|24
|12
|12
|-
|Average fuel [[burnup]], MW · day / ton
|6700
|7500
|7050
|-
|Control rods
|SS/Co
| colspan="2" |Cadmium/SS
|-
|Neutron absorber
|Boric Anhydride
| colspan="2" |Boron
|-
|Residual heat removal system
|Active: Shutdown cooling system
Passive: Natural circulation through steam generators
| colspan="2" |Active: Shutdown cooling system
Passive: Natural circulation through steam generators

and Passive Decay heat removal system
|-
|Safety injection system
| colspan="3" |Emergency core cooling system
|}

==See also==
* [[IPHWR]], a class of Indian PHWRs.
* [[IPHWR-220]], earlier lower power variant of IPHWR-700
* [[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 ==
{{reflist}}

{{Nuclear power in India}}
{{Nuclear fission reactors}}

[[Category:Nuclear power reactor types]]

IPHWR-700 - Revision history

CleanupBot at 04:18, 2 January 2022