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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 ringan sekunder; dan {{color box|#ffccff}} moderator air berat dingin di calandria[[kalandria]], bersama dengan batang pengatur yang dimasukkan sebagian (seperti batang kendali CANDU yang dikenal).
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Desain [[reaktor CANDU]] PHWR ini adalah sejumlah bundel bahan bakar dalam banyak selubungselongsong [[tabung]] kaliandria[[kalandria]] dan ditata horisontalhorizontal mendatar seperti tumpukan gelondong, pendingin [[air berat]] panas dialirkan dengan banyak pipa ke steam generator uap boiler 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.
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'''Reaktor air berat''' atau '''reaktor air berat bertekanan''' ('''''pressurized heavy-water reactor''''', '''PWHR''') adalah [[reaktor nuklir]] daya [[PLTN]] generasi II berbahandengan desain reaktor sejumlah selongsong banyak tabung horizontal berisi bundel pelet bahan bakar [[uranium alam]] kadang [[uranium]] diperkayasedikit sangat rendahdiperkaya 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.
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| 7 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 822 || 872 || Mei 1979 || {{dts|10 April 1986}} || ({{dts|2052}})
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| 8 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU reactor|CANDU]] || {{yes|Operasional}} || [[Kanada]] || 795 || 845 || AugustAgustus 1979 || 22 Mei 1987 || ({{dts|2052}})
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| [[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}}
Baris 124:
| 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 JulyJuli 2012}}</ref> || 1 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
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| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
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| 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 FebruaryFebruari 2020}}</ref> || ||
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| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{partial|Under construction}} || [[India]] || 630 || 700 || || ||
Baris 140:
| 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 MayMei 2007}} ||
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| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|10 MayMei 2002}} || {{dts|20 JanuaryJanuari 2011}} ||
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| 5 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
Baris 148:
| 6 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
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| 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 MayMei 1993}} ||
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| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 April 1985}} || {{dts|1 September 1995}} ||
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| 3 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-700<ref name="indianPHWR700" /> || {{partial|Under Construction}} || [[India]] || 630 || 700 || {{dts|22 November 2010}} || {{dts|5 MayMei 2020}} ||
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| 4 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-700<ref name="indianPHWR700" /> || {{partial|Under construction}} || [[India]] || 630 || 700 || {{dts|22 November 2010}} || ||
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| 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 JanuaryJanuari 1971}} || {{dts|27 JanuaryJanuari 1984}} ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 205 || 220 || {{dts|1 OctoberOktober 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 || || ||
Baris 168:
| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-700]] || {{planned}} || [[India]] || 630 || 700 || || ||
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| 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 JanuaryJanuari 1991}} ||
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| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 November 1977}} || {{dts|1 JulyJuli 1992}} ||
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| 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 AugustAgustus 1965}} || 16 Desember 1973 || OctoberOktober 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>
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| 2 || [[Pressurized heavy-water reactor|PHWR]] || [[CANDU]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 187 || 200 || {{dts|1 April 1968}} || {{dts|1 April 1981}} ||
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| 3 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 FebruaryFebruari 1990}} || {{dts|1 JuneJuni 2000}} ||
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| 4 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|1 OctoberOktober 1990}} || 23 Desember 2000 ||
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| 5 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|18 September 2002}} || {{dts|4 FebruaryFebruari 2010}} ||
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| 6 || [[Pressurized heavy-water reactor|PHWR]] || [[IPHWR-220]]<ref name="indianPHWR200" /> || {{yes|Operasional}} || [[India]] || 202 || 220 || {{dts|20 JanuaryJanuari 2003}} || 31 Maret 2010 ||
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| 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 JulyJuli 2011}} || ||
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| 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 MayMei 2000}} || {{dts|18 AugustAgustus 2006}} ||
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| 4 || [[Pressurized heavy-water reactor|PHWR]] || IPHWR-540 || {{yes|Operasional}} || [[India]] || 490 || 540 || 8 Maret 2000 || {{dts|12 September 2005}} ||
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| [[Karachi Nuclear Power Plant|Karachi]] || 1 || [[PHWR]] || [[CANDU]]-137 MW || {{yes|Operasional}} || [[Pakistan]] || 90 || 100 || {{dts|1 AugustAgustus 1966}} || {{dts|7 DecemberDesember 1972}} ||
|-
| rowspan=5| [[Cernavodă Nuclear Power Plant|Cernavodă]] || 1 || [[PHWR]] || [[CANDU-6]] || {{yes|Operasional}} || [[Romania]] || 650 || 706 || {{dts|1 JulyJuli 1982}} || {{dts|2 DecemberDesember 1996}} ||
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Romania]] || 650 || 705 || {{dts|1 JulyJuli 1983}} || {{dts|31 OctoberOktober 2007}} ||
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| 3 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{planned|Unfinished; restart planned}} || [[Romania]] || 650 || 705 || || ||
Baris 204:
| 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 OctoberOktober 1977}} || {{dts|22 April 1983}} || {{dts|24 DecemberDesember 2019}}
|-
| 2 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Korea Selatan]] || 655 || 678 || {{dts|22 JuneJuni 1992}} || {{dts|1 JulyJuli 1997}} ||
|-
| 3 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Korea Selatan]] || 684 || 698 || {{dts|17 MarchMaret 1994}} || {{dts|1 JulyJuli 1998}} ||
|-
| 4 || [[Pressurized heavy-water reactor|PHWR]] || CANDU-6 || {{yes|Operasional}} || [[Korea Selatan]] || 688 || 703 || {{dts|22 JulyJuli 1994}} || {{dts|1 OctoberOktober 1999}} ||
|-
| [[Ågesta Nuclear Plant|Ågesta]] || 1 || [[Pressurized heavy-water reactor|PHWR]] ||R3 || {{no|Shut down/dismantled}} || [[Swedia]] || 10 || 12 || {{dts|1 DecemberDesember 1957}} || {{dts|1 MayMei 1964}} || {{dts|2 JuneJuni 1974}}
|}
 
== Referensi ==
{{Reflist}}
* [http://www.cised.org/EconomicsofNuclearPowerfromHeavyWaterReactors.pdf Economics of Nuclear Power from Heavy Water Reactors] {{Webarchive|url=https://web.archive.org/web/20090225155112/http://www.cised.org/EconomicsofNuclearPowerfromHeavyWaterReactors.pdf |date=2009-02-25 }}
* [https://web.archive.org/web/20070927025911/http://www.dae.gov.in/publ/ar0203/chap1.pdf Nuclear Power Program – Stage1 – Pressurised Heavy Water Reactor]
* [https://www-pub.iaea.org/MTCD/publications/PDF/TRS407_scr/D407_scr1.pdf IAEA - Technical Reports Series No. 407]
Diperoleh dari "https://wiki-indonesia.club/wiki/Reaktor_air_berat_bertekanan"