Reaktor air berat bertekanan: Perbedaan antara revisi
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[[File:CANDU Reactor Schematic.svg|thumb|400px|Diagram skema reaktor CANDU: {{color box|#f2cd44}} Panas dan {{color box|#feeda9}} sisi dingin dari loop air berat primer; {{color box|#e12c2c}} panas dan {{color box|#3d99fa}} sisi dingin dari lingkaran cahaya-air sekunder; dan {{color box|#ffccff}} moderator air berat dingin di calandria, bersama dengan batang pengatur yang dimasukkan sebagian (seperti batang kendali CANDU yang dikenal).
{{Columns-list|colwidth=30em|
{{ordered list
| Fuel bundle
| Calandria (reactor core)
| Adjuster rods
| [[Heavy-water]] pressure reservoir
| [[Steam generator (nuclear power)|Steam generator]]
| [[Water|Light-water]] [[pump]]
| Heavy-water pump
| Fueling machines
| Heavy-water [[neutron moderator|moderator]]
| Pressure tube
| Steam going to [[steam turbine]]
| Cold water returning from turbine
| [[Containment building]] made of [[reinforced concrete]]
}}
}}
Desain reaktor CANDU PHWR ini adalah sejumlah bundel bahan bakar dalam banyak selubung tabung kaliandria dan ditata horisontal mendatar seperti tumpukan gelondong, pendingin air berat panas dialirkan dengan banyak pipa ke steam generator menghasilkan uap panas tekanan tinggi yang dialirkan menggerakkan turbin generator listrik. Sedangkan pada reaktor lain sejumlah bundel bahan bakar dipasang tegak vertikal disatukan dalam satu kolam wadah bejana reaktor panas dan tekanan tinggi. Desain PHWR ini memudahkan penggantian bahan bakar secara online.
]]
'''Reaktor air berat''' atau '''reaktor air berat bertekanan''' ('''''pressurized heavy-water reactor''''', '''PWHR''') adalah [[reaktor nuklir]] daya [[PLTN]] generasi II berbahan bakar [[uranium alam]] kadang [[uranium]] diperkaya sangat rendah yang menggunakan [[air berat]] ([[deuterium oksida]], D<sub>2</sub>O) sebagai [[pendingin reaktor nuklir|zat pendingin]] dan [[moderator neutron|moderator (pelambat) neutron]]. Air berat atau [[deuterium oksida]] adalah air dengan isotop [[deuterium]] (<sup>2</sup>H) sebagai hidrogennya. Air berat ini diberi tekanan tinggi agar dapat menyerap panas dan memiliki suhu tinggi tanpa mengalami pendidihan. Prinsip ini mirip [[reaktor air bertekanan|reaktor air tekanan tinggi]] biasa. Walaupun air berat jauh lebih mahal dibanding air biasa, penggunannya meningkatkan [[ekonomi neutron]] dari reaktor tersebut. Contoh jenis reaktor PHWR adalah [[Reaktor CANDU]] yang dikembangkan oleh negara [[Kanada]] dan reaktor [[IPHWR]] [[India]]. Pada awal tahun 2001, 31 PHWR beroperasi, memiliki kapasitas total 16,5 GW(e), mewakili sekitar 7,76% berdasarkan jumlah dan 4,7% dengan kapasitas pembangkit dari semua reaktor yang beroperasi saat ini.<ref>{{cite web|url=https://www.euronuclear.org/info/encyclopedia/n/naturaluranium.htm|title=Natural uranium|author=Marion Brünglinghaus|work=euronuclear.org|access-date=11 September 2015|archive-url=https://web.archive.org/web/20180612140227/https://www.euronuclear.org/info/encyclopedia/n/naturaluranium.htm|archive-date=12 Juni 2018|url-status=dead}}</ref><ref>{{cite book|url=http://books.nap.edu/openbook.php?record_id=11320&page=50 |title=An International Spent Nuclear Fuel Storage Facility - Exploring a Russian Site as a Prototype: Proceedings of an International Workshop |doi=10.17226/11320 |year=2005 |isbn=978-0-309-09688-1 |author1=National Research Council }}{{page needed|date=August 2019}}</ref><ref>{{Cite journal |doi = 10.1016/j.nucengdes.2013.12.056|title = Negative power coefficient on PHWRS with CARA fuel|journal = Nuclear Engineering and Design|volume = 270|pages = 185–197|year = 2014|last1 = Lestani|first1 = H.A.|last2 = González|first2 = H.J.|last3 = Florido|first3 = P.C.}}</ref><ref name=":0">{{Cite journal|last=Waltham|first=Chris|date=Juni 2002|title=An Early History of Heavy Water|journal=Department of Physics and Astronomy, University of British Columbia|pages=28|arxiv=physics/0206076|bibcode=2002physics...6076W}}</ref><ref>{{cite web|url=http://nuclearweaponarchive.org/India/IndiaSmiling.html|title=India's Nuclear Weapons Program: Smiling Buddha: 1974|access-date=23 Juni 2017}}</ref>
Air adalah moderator neutron cepat yang sangat baik, memungkinkan mereka untuk bertransisi menjadi neutron termal yang mampu mendukung reaksi berantai dari bahan bakar nuklir yang diperkaya (Uranium mengandung sekitar 3% isotop 235), karena selain memoderasi neutron, ia cenderung menyerap banyak jumlah itu dan untuk membentuk deuterium.
Baris 5 ⟶ 25:
Air berat hanyalah air yang bukannya hidrogen sudah memiliki isotop deuteriumnya, sudah dilengkapi dengan neutron, yang mempengaruhi kemampuan menyerap neutron dan oleh karena itu memungkinkan kelangsungan reaksi berantai bahan bakar yang tidak diperkaya.
;Keuntungan PHWR:
* Penggunaan Uranium yang Tidak Diperkaya. Reaktor air berat dapat menggunakan uranium alam, uranium yang sedikit diperkaya (konsentrasi U-235 0,71 hingga 2%).
* Penggunaan uranium "bekas". Di CANDU juga diuji penggunaan "off uranium" (campuran plutonium dan limbah radioaktif lainnya) dari batangan bahan bakar bekas dari reaktor nuklir lain (tanpa pengolahan ulang kimia, melalui siklus Dupic). Meskipun cukup "dibakar", limbah yang dihasilkan dari penggunaan ini jauh lebih berbahaya karena mengandung persentase tinggi neptunium-237 (sangat larut dalam air), plutonium-239 dan xenon-110 (selain uranium-238). Saat ini, rendahnya biaya uranium membuat daur ulang tidak diperlukan.
Baris 13 ⟶ 33:
* Produksi tritium. Produk sampingan dari radiasi neutron deuterium (dalam air berat) adalah tritium, yang suatu hari nanti dapat dimanfaatkan oleh beberapa jenis reaktor fusi nuklir yang diusulkan (tetapi juga dalam bom termonuklir, sebagai penambah litium hidrida).
;Kekurangan PHWR:
* Tingginya biaya air berat. Untuk reaktor nuklir dari rantai pasokan CANDU telah dihitung bahwa air berat mewakili rata-rata sekitar 20% dari biaya modal untuk setiap reaktor. Di Semenanjung Bruce di Ontario, sebuah pabrik dibangun yang mampu menghasilkan 1 liter air berat untuk setiap 320.000 liter air dari Great Lakes (ditenagai oleh energi panas dan listrik yang dihasilkan oleh reaktor itu sendiri), tetapi setelah akumulasi surplus besar-besaran air berat, dan karena meningkatnya masalah lingkungan yang disebabkan oleh hidrogen sulfida, pabrik ditutup dan kemudian dibongkar.
* Iradiasi reaktor tinggi. Fluks intens neutron termal menyebabkan aktivasi radioaktif intens dari inti reaktor dan struktur bangunan penahan utama. Hal ini membutuhkan waktu tunggu yang lama antara de-fueling dan pembongkaran akhir reaktor nuklir, yang di lokasi dengan nilai komersial atau lanskap yang tinggi, dapat menyebabkan masalah ekonomi dan sosial yang signifikan.
* Hilangnya tritium ke lingkungan. Salah satu bahaya reaktor PHWR adalah polusi karena hilangnya sejumlah kecil tritium (beta-emitter) dalam air dari sirkuit pendingin sekunder reaktor.
;Daftar Reaktor nuklir PHWR:
{| class="wikitable sortable mw-datatable"
<includeonly>|+ List of nuclear reactors in Argentina [ [[List of nuclear reactors#Argentina|view/edit]] ]</includeonly>
|-
! rowspan="2" |[[PLTN]]
! rowspan="2" |Unit<br/>No.
! colspan="2" |Reaktor
! rowspan="2" |Status
! rowspan="2" |Negara
! colspan="2" |Kapasitas dalam MW
! rowspan="2" |Konstruksi mulai
! rowspan="2" |Operasi komersial
! rowspan="2" |Penutupan
|-
! Jenis ||Model ||Net ||Gross
|-
| rowspan=3| [[Atucha Nuclear Power Plant|Atucha]]<ref>{{cite web |title=Nuclear Power in Argentina {{!}} Argentinian Nuclear Energy - World Nuclear Association |url=https://www.world-nuclear.org/information-library/country-profiles/countries-a-f/argentina.aspx |website=www.world-nuclear.org |access-date=4 August 2019}}</ref> || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[Siemens]]-KWU || {{yes|Operasional}} || [[Argentina]] || 335 || 362 || {{dts|1 Juni 1968}} || {{dts|24 Juni 1974}} ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || Siemens-KWU || {{yes|Operasional}} || [[Argentina]] || 692 || 745 || {{dts|14 Juli 1981}} (halted in 1994, restarted in 2007) || {{dts|27 Juni 2014}} ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU-6]] || {{planned}}<ref>{{cite web|url=http://www.world-nuclear-news.org/NN-Atucha-3-contract-signed-0409145.html|title=Atucha 3 contract signed|access-date=20 August 2015}}</ref> || [[Argentina]] || 800 || || || ({{dts|2025}}) ||
|-
|[[Embalse nuclear power plant|Embalse]]<ref>{{cite web|url=http://www.candu.org/nasa.html|archive-url=https://web.archive.org/web/20070708162652/http://www.candu.org/nasa.html|title=NASA fact sheet|author=Yulia Kosarenko|archive-date=8 Juli 2007|access-date=20 August 2015}}</ref> || 1 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Argentina]] || 600 || 648 || {{dts|1 April 1974}} || 20 Januari 1984 || ({{dts|2049}})<ref>{{Cite web|url=https://www.bnamericas.com/en/news/the-embalse-nuclear-power-plant-returns-to-service-for-a-new-cycle-of-30-years|title=BNamericas - The Embalse Nuclear Power Plant returns to s...|website=BNamericas.com}}</ref>
|-
| rowspan=8| [[Pickering Nuclear Generating Station|Pickering]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 515 || 542 || Juni 1966 || {{dts|29 Juli 1971}} || ({{dts|2022}})
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{no|Shut down}} || [[Kanada]] || 515 || 542 || September 1966 || 30 Desember 1971 || {{dts|1997}}
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{no|Shut down}} || [[Kanada]] || 515 || 542 || Desember 1967 || {{dts|1 Juni 1972}} || {{dts|1997}}
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 515 || 542 || Mei 1968 || {{dts|17 Juni 1973}} || ({{dts|2022}})
|-
| 5 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 516 || 540 || November 1974 || 10 Mei 1983 || ({{dts|2024}})
|-
| 6 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 516 || 540 || Oktober 1975 || 1 Februari 1984 || ({{dts|2024}})
|-
| 7 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 516 || 540 || Maret 1976 || 1 Januari 1985 || ({{dts|2024}})
|-
| 8 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 516 || 540 || September 1976 || 28 Februari 1986 || ({{dts|2024}})
|-
| rowspan=4| [[Darlington Nuclear Generating Station|Darlington]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 878 || 934 || April 1982 || {{dts|14 November 1992}} || ({{dts|2052}})
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 878 || 934 || September 1981 || 9 Oktober 1990 || ({{dts|2050}})
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 878 || 934 || September 1984 || 14 Februari 1993 || ({{dts|2053}})
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 878 || 934 || Juli 1985 || {{dts|14 Juni 1993}} || ({{dts|2053}})
|-
| rowspan=8| [[Bruce Nuclear Generating Station|Bruce]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 750 || 805 || Juni 1971 || {{dts|1 September 1977}} || ({{dts|2042}})
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 750 || 805 || Desember 1970 || {{dts|1 September 1977}} || ({{dts|2043}})
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 750 || 805 || Juli 1972 || 1 Februari 1978 || ({{dts|2053}})
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 750 || 805 || September 1972 || 18 Januari 1979 || ({{dts|2054}})
|-
| 5 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 795 || 845 || Juni 1978 || 1 Maret 1985 || ({{dts|2052}})
|-
| 6 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 822 || 872 || Januari 1978 || {{dts|15 September 1984}} || ({{dts|2052}})
|-
| 7 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 822 || 872 || Mei 1979 || {{dts|10 April 1986}} || ({{dts|2052}})
|-
| 8 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 795 || 845 || August 1979 || 22 Mei 1987 || ({{dts|2052}})
|-
| [[Nuclear Power Demonstration|NPD]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{no|Shut down}} || [[Kanada]] || 19.5 || 22 || Januari 1958 || {{dts|4 Juni 1962}} || {{dts|1987}}
|-
| [[Douglas Point Nuclear Generating Station|Douglas Point]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{no|Shut down}} || [[Kanada]] || 200 || 220 || Februari 1960 || {{dts|26 September 1968}} || {{dts|1984}}
|-
| [[Gentilly Nuclear Generating Station|Gentilly]] || 2 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU-6]] || {{no|Shut down}} || [[Kanada]] || 635 || 675 || April 1974 || 1 Oktober 1983 || {{dts|2012}}
|-
| [[Point Lepreau Nuclear Generating Station|Point Lepreau]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 635 || 660 || Mei 1975 || 1 Februari 1983 || ({{dts|2041}})
|-
| rowspan=2| [[Qinshan Nuclear Power Plant|Qinshan]] || III-1 || [[PHWR]] || [[CANDU-6]] || {{yes|Operasional}} || [[China]] || 677 || 728 || {{dts|8 Juni 1998}} || 31 Desember 2002 ||
|-
| III-2 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[China]] || 677 || 728 || {{dts|25 September 1998}} || {{dts|24 Juli 2003}} ||
|-
| MZFR || 1 || [[PHWR]] || Heavy water-cooled pressure vessel reactor || {{no|Shut down}} || [[Jerman]] || 52 || 57 || 1 Desember 1961 || 19 Desember 1966 || 3 Mei 1984
|-
| rowspan=4| [[Bhimpur Nuclear Power Plant|Bhimpur]]<ref>{{Cite web|url=https://www.newindianexpress.com/nation/2015/apr/30/Government-Approves-10-Sites-for-New-Nuclear-Power-Projects-749056.html|title=Government Approves 10 Sites for New Nuclear Power Projects|website=The New Indian Express}}</ref> || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| rowspan=2| [[Chutka Nuclear Power Plant|Chutka]]<ref>[http://www.dae.gov.in/power/npcil.htm Indian Nuclear Power Program<!-- Bot generated title -->] {{webarchive|url=https://web.archive.org/web/20120701151250/http://www.dae.gov.in/power/npcil.htm |date=1 July 2012}}</ref> || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| rowspan=4| [[Gorakhpur Nuclear Power Plant|Gorakhpur]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{partial|Under construction}} || [[India]] || 630 || 700 ||(2019)<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|access-date=13 February 2020}}</ref> || ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{partial|Under construction}} || [[India]] || 630 || 700 || || ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| rowspan=6| [[Kaiga Atomic Power Station|Kaiga]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 September 1989}} || {{dts|16 November 2000}} ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200">{{cite web|url=https://aris.iaea.org/PDF/IPHWR-220.pdf}}</ref> || {{yes|Operasional}} || [[India]] || 202 || 220 || 1 Desember 1989 || 16 Maret 2000 ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || 30 Maret 2002 || {{dts|6 May 2007}} ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|10 May 2002}} || {{dts|20 January 2011}} ||
|-
| 5 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 6 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| rowspan=4| [[Kakrapar Atomic Power Station|Kakrapar]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || 1 Desember 1984 || {{dts|6 May 1993}} ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 April 1985}} || {{dts|1 September 1995}} ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-700<ref name="indianPHWR700" /> || {{partial|Under Construction}} || [[India]] || 630 || 700 || {{dts|22 November 2010}} || {{dts|5 May 2020}}||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-700<ref name="indianPHWR700" /> || {{partial|Under construction}} || [[India]] || 630 || 700 || {{dts|22 November 2010}} || ||
|-
| rowspan=2| [[Madras Atomic Power Station|Madras]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 205 || 220 || {{dts|1 January 1971}} || {{dts|27 January 1984}} ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 205 || 220 || {{dts|1 October 1972}} || 21 Maret 1986 ||
|-
| rowspan=4| [[Mahi Banswara Atomic Power Station|Mahi Banswara]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
|-
| rowspan=2| [[Narora Atomic Power Station|Narora]] || 1 || [[Pressurized heavy-water reactor|PHWR]] ||[[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || 1 Desember 1976 || {{dts|1 January 1991}} ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 November 1977}} || {{dts|1 July 1992}} ||
|-
| rowspan=8| [[Rajasthan Atomic Power Station|Rajasthan]] || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU]]<ref name="indianPHWR200" /> || {{no|Shut down}} || [[India]] || 90 || 100 || {{dts|1 August 1965}} || 16 Desember 1973 || October 2004<ref>{{cite web |title=Rajya Sabha unstarred question No. 466 |url=https://dae.gov.in/writereaddata/rsus466.pdf |website=Department of Atomic Energy |access-date=20 Maret 2021}}</ref>
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 187 || 200 || {{dts|1 April 1968}} || {{dts|1 April 1981}} ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 February 1990}} || {{dts|1 June 2000}} ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 October 1990}} || 23 Desember 2000 ||
|-
| 5 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|18 September 2002}} || {{dts|4 February 2010}} ||
|-
| 6 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|20 January 2003}} || 31 Maret 2010 ||
|-
| 7 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-700<ref name="indianPHWR700">{{cite web|url=https://aris.iaea.org/PDF/IPHWR-700.pdf}}</ref> || {{partial|Under construction}} || [[India]] || 630 || 700 || {{dts|18 July 2011}} || ||
|-
| 8 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-700<ref name="indianPHWR700" /> || {{partial|Under construction}} || [[India]] || 630 || 700 || {{dts|30 September 2011}} || ||
|-
| rowspan=2| [[Tarapur Atomic Power Station|Tarapur]] || 3 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-540 || {{yes|Operasional}} || [[India]] || 490 || 540 || {{dts|12 May 2000}} || {{dts|18 August 2006}} ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-540 || {{yes|Operasional}} || [[India]] || 490 || 540 || 8 Maret 2000 || {{dts|12 September 2005}} ||
|-
| [[Karachi Nuclear Power Plant|Karachi]] || 1 || [[PHWR]] || [[CANDU]]-137 MW || {{yes|Operasional}} || [[Pakistan]] || 90 || 100 || {{dts|1 August 1966}} || {{dts|7 December 1972}} ||
|-
| rowspan=5| [[Cernavodă Nuclear Power Plant|Cernavodă]] || 1 || [[PHWR]] || [[CANDU-6]] || {{yes|Operasional}} || [[Romania]] || 650 || 706 || {{dts|1 July 1982}} || {{dts|2 December 1996}} ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Romania]] || 650 || 705 || {{dts|1 July 1983}} || {{dts|31 October 2007}} ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{planned|Unfinished; restart planned}} || [[Romania]] || 650 || 705 || || ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{planned|Unfinished; restart planned}} || [[Romania]] || 650 || 705 || || ||
|-
| 5 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{BLACK|Unfinished}} || [[Romania]] || 650 || 705 || || ||
|-
| rowspan=4| [[Wolsong Nuclear Power Plant|Wolsong]] || 1 || [[PHWR]] || [[CANDU-6]] || {{no|Shut down}} || [[Korea Selatan]] || 657 || 687 || {{dts|30 October 1977}} || {{dts|22 April 1983}} || {{dts|24 December 2019}}
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Korea Selatan]] || 655 || 678 || {{dts|22 June 1992}} || {{dts|1 July 1997}} ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Korea Selatan]] || 684 || 698 || {{dts|17 March 1994}} || {{dts|1 July 1998}} ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Korea Selatan]] || 688 || 703 || {{dts|22 July 1994}} || {{dts|1 October 1999}} ||
|-
| [[Ågesta Nuclear Plant|Ågesta]] || 1 || [[Pressurized heavy-water reactor|PHWR]] ||R3 || {{no|Shut down/dismantled}} || [[Swedia]] || 10 || 12 || {{dts|1 December 1957}} || {{dts|1 May 1964}} || {{dts|2 June 1974}}
|}
== Referensi ==
Baris 30 ⟶ 227:
[[Kategori:Reaktor dengan bahan bakar uranium]]
[[Kategori:Reaktor dengan bahan bakar uranium alam]]
[[Kategori:Desain reaktor nuklir]]
[[Kategori:Reaktor PHWR]]
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