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Breeder reactor
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=== Notable reactors === {| class="wikitable sortable" style="text-align:center" |+ Notable breeder reactors<ref name=":1" /><ref name="world-nuclear.org">{{cite web |title=Nuclear Fusion: WNA - World Nuclear Association |url=http://www.world-nuclear.org/info/Current-and-Future-Generation/Fast-Neutron-Reactors/ |access-date=2 March 2015 |url-status=live |archive-url=https://web.archive.org/web/20150316080643/http://world-nuclear.org/info/Current-and-Future-Generation/Fast-Neutron-Reactors/ |archive-date=16 March 2015}}</ref><ref name="pillai-2014">{{cite journal |title=Breeder reactors: A possible connection between metal corrosion and sodium leaks |author=S. R. Pillai, M. V. Ramana |journal=Bulletin of the Atomic Scientists |volume=70 |issue=3 |pages=49β55 |year=2014 |bibcode=2014BuAtS..70c..49P |s2cid=144406710 |doi=10.1177/0096340214531178 |url=http://bos.sagepub.com/content/70/3/49 |access-date=15 February 2015 |url-status=live |archive-url=https://web.archive.org/web/20151017114605/http://bos.sagepub.com/content/70/3/49 |archive-date=17 October 2015|url-access=subscription }}</ref><ref name="IAEA-PRIS">{{cite web |title=Database on Nuclear Power Reactors |publisher=IAEA |work=PRIS |url=http://www.iaea.org/PRIS/ |access-date=15 February 2015 |url-status=live |archive-url=https://web.archive.org/web/20130602010449/http://www.iaea.org/pris/ |archive-date=2 June 2013}}</ref><ref>{{cite web |title=Experimental Breeder Reactor 1 (EBR-1) - Cheeka Tales |url=http://cheekatales.weebly.com/experimental-breeder-reactor-1-ebr-1.html |access-date=2 March 2015 |url-status=live |archive-url=https://web.archive.org/web/20150402120752/http://cheekatales.weebly.com/experimental-breeder-reactor-1-ebr-1.html |archive-date=2 April 2015}}</ref> |- !Reactor !! Country<br>when built !! Started !! Shut down !! Design<br>MWe !! Final<br>MWe !! Thermal<br>Power MWt !! [[Capacity factor|Capacity<br>factor]] !! Number of<br>coolant leaks !! [[Neutron temperature|Neutron<br>temperature]] !! Coolant !! Reactor class |- |[[Dounreay#DFR|DFR]] || UK || 1962 || 1977 || 14 || 11 || 65 || 34% || 7 || Fast || [[NaK]] || Test |- |[[China Experimental Fast Reactor]] || China || 2012 || operating || 20 || 22 || 65|| 40% || 8 || Fast || [[Sodium]] || Test<ref>{{cite web |title=Chinese fast reactor begins high-power operation: New Nuclear - World Nuclear News |url=https://www.world-nuclear-news.org/Articles/Chinese-fast-reactor-begins-high-power-operation}}</ref> |- |[[CFR-600]] || China || 2017 || commissioning/2023 || 642 || 682 || 1882 || 34% || 27 || Fast || [[Sodium]] || Commercial<ref>{{cite web |title=China's New Breeder Reactors May Produce More Than Just Watts - IEEE Spectrum |url=https://spectrum.ieee.org/china-breeder-reactor}}</ref> |- |[[BN-350 reactor|BN-350]] || Soviet Union || 1973 || 1999 || 350 || 52 || 750 || 43% || 15 || Fast || [[Sodium]] || Prototype |- |[[Rapsodie]] || France || 1967 || 1983 || 0 || β || 40 || β || 2 || Fast || Sodium || Test |- |[[PhΓ©nix]] || France || 1975 || 2010 || 233 || 130 || 563 || 40.5% || 31 || Fast || Sodium || Prototype |- |[[Dounreay#PFR|PFR]] || UK || 1976 || 1994 || 234 || 234 || 650 || 26.9% || 20 || Fast || Sodium || Prototype |- |KNK II || Germany || 1977 || 1991 || 18 || 17 || 58 || 17.1% || 21 || Fast || Sodium || Research/Test |- |[[SNR-300]] || Germany || 1985 || 1991 || 327 || β || β || non-nuclear tests only || β || Fast || Sodium || Prototype/Commercial |- |[[BN-600 reactor|BN-600]] || Soviet Union || 1981 || {{sort|9997|operating}} || 560 || 560 || 1470 || 74.2% || 27 || Fast || Sodium || Prototype/Commercial (Gen2) |- |[[Fast Flux Test Facility|FFTF]] || US || 1982 || 1993 || 0 || β || 400 || β || 1 || Fast || Sodium || Test |- |[[SuperphΓ©nix]] || France || 1985 || 1998 || 1200 || 1200 || 3000 || {{sort|07.9|7.9%}} || 7 || Fast || Sodium || Prototype/Commercial (Gen2) |- |[[FBTR]] || India || 1985 || {{sort|9997|operating}} || 13 || β || 40 || β || 6 || Fast || Sodium || Test |- |[[Prototype Fast Breeder Reactor|PFBR]] || India || 2004 || 2024 || 500 || β || 1250 || β || β || Fast || Sodium || Prototype/Commercial (Gen3) |- |[[JΕyΕ (nuclear reactor)|JΕyΕ]] || Japan || 1977 || 2007 || 0 || β || 150 || β || β || Fast || Sodium || Test |- |[[Monju Nuclear Power Plant|Monju]] || Japan || 1995 || 2017 || 246 || 246 || 714 || {{sort|00.1|trial only}} || 1 || Fast || Sodium || Prototype |- |[[BN-800 reactor|BN-800]] || Russia || 2015 || {{sort|9997|operating}} || 789 || 880 || 2100 || 73.4% || β || Fast || Sodium || Prototype/Commercial (Gen3) |- |[[Molten-Salt Reactor Experiment|MSRE]] || US || 1965 || 1969 || 0 || β || 7.4 || β || β || Epithermal || Molten salt ([[FLiBe]]) || Test |- |[[Clementine (nuclear reactor)|Clementine]] || US || 1946 || 1952 || 0 || β || 0.025 || β || β || Fast || [[Mercury (element)|Mercury]] || World's First Fast Reactor<ref name=":1" /> |- |[[Experimental Breeder Reactor I|EBR-1]] || US || 1951 || 1964 || 0.2 || 0.2 || 1.4 || β || β || Fast || [[NaK]] || First Power Reactor |- |[[Enrico Fermi Nuclear Generating Station#Fermi 1|Fermi-1]] || US || 1963 || 1972 || 66 || 66 || 200 || β || β || Fast || Sodium || Prototype |- |[[Experimental Breeder Reactor II|EBR-2]] || US || 1964 || 1994 || 19 || 19 || 62.5 || β || β || Fast || Sodium || Experimental/Test |- |[[Shippingport Atomic Power Station|Shippingport]] || US || 1977<br>as breeder || 1982 || 60 || 60 || 236 || β || β || Thermal || Light Water || Experimental-Core3 |- |} {{Clear}} The Soviet Union constructed a series of fast reactors, the first being mercury-cooled and fueled with plutonium metal, and the later plants sodium-cooled and fueled with plutonium oxide. BR-1 (1955) was 100W (thermal) was followed by BR-2 at 100 kW and then the 5 MW BR-5.<ref name="Korobeinikov_2014">{{cite conference |author=Valerii Korobeinikov |title=Innovative Concepts Based on Fast Reactor Technology |conference=1st Consultancy Meeting for Review of Innovative Reactor Concepts for Prevention of Severe Accidents and Mitigation of their Consequences |website=International Atomic Energy Agency |date=31 March β 2 April 2014 |url=https://www.iaea.org/NuclearPower/Downloadable/Meetings/2014/2014-03-31-04-02-CM-INPRO/RUSSIA_PPT_MS_Presentations_1st_CM_on_RISC_.pdf |url-status=dead |archive-url=https://web.archive.org/web/20160304072421/https://www.iaea.org/NuclearPower/Downloadable/Meetings/2014/2014-03-31-04-02-CM-INPRO/RUSSIA_PPT_MS_Presentations_1st_CM_on_RISC_.pdf |archive-date=4 March 2016}}</ref> BOR-60 (first criticality 1969) was 60 MW, with construction started in 1965.<ref>{{cite web |title=Experimental fast reactor BOR-60 |author=FSUE "State Scientific Center of Russian Federation Research Institute of Atomic Reactors" |url=http://www-dev.niiar.ru/ofibr/en/e_bor60.htm |access-date=15 June 2012 |url-status=live |archive-url=https://web.archive.org/web/20121231133752/http://www-dev.niiar.ru/ofibr/en/e_bor60.htm |archive-date=31 December 2012}}</ref>
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