Editing Fast-neutron reactor (section)

==List of fast reactors==

===Decommissioned reactors===

====United States====
*[[Clementine (nuclear reactor)|Clementine]] was the first fast reactor, built in 1946 at [[Los Alamos National Laboratory]]. It used plutonium metal fuel, mercury coolant, achieved 25&nbsp;kW thermal and used for research, especially as a fast neutron source.
*[[Experimental Breeder Reactor I]] (EBR-I) at Argonne West, now [[Idaho National Laboratory]], near [[Arco, Idaho]], in 1951 became the first reactor to generate significant amounts of power. Decommissioned in 1964.
*[[Fermi 1]] near [[Detroit]] was a prototype fast breeder reactor that powered up in 1957 and shut down in 1972.
*[[Experimental Breeder Reactor II]] (EBR-II) at [[Idaho National Laboratory]], near [[Arco, Idaho]], was a prototype for the Integral Fast Reactor, 1965–1994.
*[[SEFOR]] in Arkansas, was a 20 [[MWt]] research reactor that operated from 1969 to 1972.
*[[Fast Flux Test Facility]] (FFTF), 400 MWt, operated flawlessly from 1982 to 1992, at [[Hanford Site|Hanford]] Washington. It used liquid sodium drained with argon backfill under care and maintenance.
*[[Sodium Reactor Experiment|SRE]] in California, was a 20 [[MWt]], 6.5 MWe commercial reactor operated from 1957 to 1964.
*[[LAMPRE-1]] was a molten plutonium fueled 1 MWth reactor.  It operated as a research reactor from 1961 to 1963 at Los Alamos national Lab.

====Europe====
*[[Dounreay Loop type Fast Reactor]] (DFR), 1959–1977, was a 14 MWe and [[Prototype Fast Reactor]] (PFR), 1974–1994, 250 MWe, in [[Caithness]], in the [[Highland (council area)|Highland]] area of [[Scotland]].
*[[Dounreay Pool type Fast Reactor]] (PFR), 1975–1994, was a 600 MWt, 234 MWe which used mixed oxide (MOX) fuel.
*[[Rapsodie]] in [[Cadarache]], France, (20 then 40 MW) operated between 1967 and 1982.
*[[Superphénix]], in France, 1200 MWe, closed in 1997 due to a political decision and high costs.
*[[Phénix]], 1973, France, 233 MWe, restarted 2003 at 140 MWe for experiments on transmutation of nuclear waste for six years, ceased power generation in March 2009, though it will continue in test operation and to continue research programs by CEA until the end of 2009. Stopped in 2010.
*KNK-II, in Germany a 21 MWe experimental compact sodium-cooled fast reactor operated from Oct 1977-Aug 1991. The objective of the experiment was to eliminate nuclear waste while producing energy.  There were minor sodium problems combined with public protests which resulted in the closure of the facility.

====USSR/Russia====
*Small lead-cooled fast reactors were used for [[nuclear marine propulsion|naval propulsion]], particularly by the [[Soviet Navy]].
*BR-5 - was a research-focused fast-neutron reactor at the Institute of Physics and Energy in Obninsk from 1959 to 2002.
*[[BN-350]] was constructed by the Soviet Union in Shevchenko (today's [[Aqtau]]) on the [[Caspian Sea]], It produced 130 MWe plus 80,000 tons of fresh water per day.
*IBR was a research-focused pulsed fast-neutron reactor at the Joint Institute of Nuclear Research in Dubna (near Moscow) put into operation in 1984 till 2006.
*RORSATs - 33 space fast reactors were launched by the Soviet Union from 1989 to 1990 as part of a program known as the Radar Ocean Reconnaissance Satellite (RORSAT) in the US.  Typically, the reactors produced approximately 3 kWe.
*[[BES-5]] - was a sodium cooled space reactor launched as part of the RORSAT program which produced 5 kWe.  
*[[BR-5]] - was a 5 MWt sodium fast reactor operated by the USSR in 1961 primarily for materials testing.
*[[Russian Alpha 8 PbBi]] - was a series of lead-bismuth cooled fast reactors used aboard submarines. The submarines functioned as killer submarines, staying in harbor then attacking due to the high speeds achievable by the sub.

====Asia====
*[[Monju reactor]], 300 MWe, in [[Japan]], was closed in 1995 following a serious sodium leak and fire. It was restarted on May 6, 2010, but in August 2010 another accident, involving dropped machinery, shut down the reactor again. As of June 2011, the reactor had generated electricity for only one hour since its first test two decades prior.{{citation needed|date=August 2019}}
*[[Aktau Reactor]], 150 MWe, in [[Kazakhstan]], was used for plutonium production, desalination, and electricity.  It closed 4 years after the plant's operating license expired.{{citation needed|date=August 2019}}

===Never operated===
*[[Clinch River Breeder Reactor]], United States
*[[Integral Fast Reactor]], United States. Design emphasized fuel cycle based on on-site electrolytic reprocessing. Cancelled in 1994 without construction.
*[[SNR-300]], Germany

===Active ===
*IBR-2 - a pulsed fast-neutron reactor at [[Joint Institute for Nuclear Research]] in Dubna. Located at the Laboratory of Neutron Physics (FLNP) named after. I.M. Frank as part of [[JINR]]. From 2006 to June 2011 it underwent modernization. The only nuclear reactor in the world with a movable reflector. Commissioned on February 10, 1984.
*[[BN-600 reactor|BN-600]] - a pool type sodium-cooled fast breeder reactor at the [[Beloyarsk Nuclear Power Station]]. It provides 560 MWe to the Middle Urals power grid. In operation since 1980.
*[[BN-800 reactor|BN-800]] - a sodium-cooled fast breeder reactor at the Beloyarsk Nuclear Power Station. It generates 880 MW of electrical power and started producing electricity in October, 2014. It reached full power in August, 2016.
*[[BOR-60]] - a sodium-cooled reactor at the [[Research Institute of Atomic Reactors]] in [[Dimitrovgrad, Russia]]. In operation since 1968. It produces 60MW for experimental purposes.<ref name=bor-60-parameters>{{cite web|url=https://www.niiar.ru/eng/node/2999|title=Parameters|website=niiar.ru|access-date=14 September 2024}}</ref>
*[[FBTR]] - a 40MWt,13.2MWe experimental reactor in India which focused on reaching significant burnup levels.
*[[China Experimental Fast Reactor]], a 60 MWth, 20 MWe, experimental reactor which went critical in 2011 and is currently operational.<ref>{{cite web|url=http://www.zoomchina.com.cn/new/content/view/23038/81/|title=China 's first Experimental Fast Reactor (CEFR) Put into Operation in 2009 – Zoom China Energy Intelligence-New site<!-- Bot generated title -->|website=zoomchina.com.cn|access-date=2008-06-01|archive-url=https://web.archive.org/web/20110707023122/http://www.zoomchina.com.cn/new/content/view/23038/81/|archive-date=2011-07-07|url-status=dead}}</ref> It is used for materials and component research for future Chinese fast reactors.
*[[Kilopower|KiloPower/KRUSTY]] is a 1-10 kWe research sodium fast reactor built at Los Alamos National Laboratory.  It first reach criticality in 2015 and demonstrates an application of a Stirling power cycle.

===Under repair===
*{{Nihongo|[[Jōyō (nuclear reactor)|Jōyō]]|常陽}}, 1977–1997 and 2004–2007, Japan, 140 MWt is an experimental reactor, operated as an irradiation test facility. After an incident in 2007, the reactor was suspended for repairing, recoworks were planned to be completed in 2014.<ref>T. SOGA, W. ITAGAKI, Y. KIHARA, Y. MAEDA. [http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/45/026/45026113.pdf Endeavor to improve in-pile testing techniques in the experimental fast reactor Joyo]. 2013.</ref>

===Under construction===
*[[PFBR]], Kalpakkam, India, 500 MWe reactor with criticality planned for the end of 2025. It is a sodium fast breeder reactor. [[Prime minister of India|Indian prime minister]] [[Narendra Modi|Modi]] was present for initial core loading in March 2024.{{cn|date=May 2025}}
*[[CFR-600]], China, 600 MWe.
*[[MBIR]] Multipurpose fast neutron research reactor. The Research Institute of Atomic Reactors (NIIAR) site at Dimitrovgrad in the Ulyanovsk region of western Russia, 150 MWt. Construction started in 2016 with completion scheduled for 2027.<ref name=pilot-fuel>{{cite web | url=https://www.world-nuclear-news.org/Articles/Pilot-fuel-produced-for-MBIR-fast-neutron-research | title=Pilot fuel elements produced for MBIR fast neutron research reactor }}</ref>
*[[BREST-300]], Seversk, Russia. Construction started at 8 June 2021<ref>{{cite web|url=https://world-nuclear-news.org/Articles/Russia-starts-building-lead-cooled-fast-reactor|title=Russia starts building lead-cooled fast reactor : New Nuclear - World Nuclear News|website=world-nuclear-news.org}}</ref>

===In design ===
*[[BN-1200 reactor|BN-1200]], construction is expected to start in 2027.<ref name=bn-1200-2027>{{cite web|url=https://www.neimagazine.com/advanced-reactors-fusion/russia-progresses-with-bn-1200m-sodium-cooled-fast-reactor-development/|title=Russia progresses with BN-1200M sodium-cooled fast reactor development|date=21 May 2024 |access-date=14 September 2024}}</ref>
*[[Toshiba 4S]] was planned to be shipped to [[Galena, Alaska]] (USA) but progress stalled (see [[Galena Nuclear Power Plant]])
*KALIME is a 600 MWe project in South Korea, projected for 2030.<ref>{{cite web|url=http://ehome.kaeri.re.kr/snsd/eng/organization/organization.htm|title=***지속가능원자력시스템***<!-- Bot generated title -->|website=kaeri.re.kr}}</ref> KALIMER is a continuation of the sodium-cooled, metal-fueled, fast-neutron reactor in a pool represented by the Advanced Burner Reactor (2006), [[S-PRISM]] (1998-present), [[Integral Fast Reactor]] (1984-1994), and [[Experimental Breeder Reactor II|EBR-II]] (1965-1995).
*[[Generation IV reactor]] ([[Gas-cooled fast reactor|helium]]·[[sodium-cooled fast reactor|sodium]]·[[lead-cooled fast reactor|lead]] cooled) US-proposed international effort, after 2030.
*JSFR, Japan, a project for a 1500 MWe reactor began in 1998, but without success.
*[[ASTRID (reactor)|ASTRID]], France, canceled project for a 600 MWe sodium-cooled reactor.
*Mars Atmospherically Cooled Reactor (MACR) is a 1 MWe project, planned to complete in 2033. MACR is a gas-cooled (carbon dioxide coolant) fast-neutron reactor intended to provide power to proposed Mars colonies.
*[[TerraPower]] is designing a molten salt reactor in partnership with [[Southern Company]], [[Oak Ridge National Laboratory]], [[Idaho National Laboratory]], [[Vanderbilt University]] and the [[Electric Power Research Institute]]. They expect to begin testing a loop facility in 2019 and is scaling up their salt manufacturing process. Data will be used to assess thermal hydraulics and safety analysis codes.<ref>{{cite web|url=https://www.nextbigfuture.com/2018/08/southern-company-partnering-with-bill-gates-backed-terrapower-on-molten-chloride-fast-reactor.html|title=Southern Company partnering with Bill Gates backed Terrapower on molten chloride fast reactor|last=Wang|first=Brian|date=August 24, 2018|website=www.nextbigfuture.com|language=en-US|access-date=2018-08-25}}</ref>
*[[Elysium Industries]] is designing a fast spectrum molten salt reactor.<ref>{{cite web|url=http://www.elysiumindustries.com/technology|title=Technology|access-date=2019-07-30|archive-date=2019-07-30|archive-url=https://web.archive.org/web/20190730182500/http://www.elysiumindustries.com/technology|url-status=dead}}</ref>
*[[ALFRED (nuclear reactor)|ALFRED]] (Advanced Lead Fast Reactor European Demonstrator) is a lead cooled fast reactor demonstrator designed by Ansaldo Energia from Italy, it represents the last stage of the ELSY and LEADER projects.<ref>{{cite web|url=https://www.ansaldoenergia.com/Pages/Generation-IV--SMR.aspx|title=Generation IV & SMR|website=www.ansaldoenergia.com}}</ref>
*[[Aurora nuclear reactor]], Idaho

===Planned===
*Future FBR, India, 600 MWe, after 2025<ref>{{cite web|url=https://www.scribd.com/document/171276959/Overview-of-Indian-Fast-Breeder-Nuclear-Reactor-Programme|title=Overview of Indian Fast Breeder Nuclear Reactor Programme - Nuclear Power - Nuclear Reactor|website=Scribd}}</ref>

===Chart===
{| class="wikitable"
|+ Fast reactors
! !!U.S. !!Russia !!Europe !!Asia
|- style="background:#ddd"
|'''Past''' ||[[Clementine (nuclear reactor)|Clementine]], [[EBR-I]]/[[EBR-II|II]], [[SEFOR]], [[Fast Flux Test Facility|FFTF]] ||[[BN-350]] ||[[Dounreay]], [[Rapsodie]], [[Superphénix]], [[Phénix|Phénix (stopped in 2010)]]||
|- style="background:#bbb"
|'''Cancelled''' ||[[Clinch River Breeder Reactor|Clinch River]], [[Integral Fast Reactor|IFR]] || ||[[SNR-300]], [[ASTRID (reactor)|ASTRID]]||
|-
|Under decommissioning
|
|
|
|[[Monju Nuclear Power Plant|Monju]]
|- style="background:#cfc"
|'''Operating''' || ||[[IBR-2]], [[BOR-60]], [[BN-600]],<br /> [[Beloyarsk Nuclear Power Station|BN-800]]<ref name="pris_russia">[https://pris.iaea.org/PRIS/CountryStatistics/CountryDetails.aspx?current=RU PRIS data base] (2021)</ref>||  || [[FBTR]], [[China Experimental Fast Reactor|CEFR]]
|- style="background:#ada"
|'''Under repair''' || || || ||[[Jōyō (nuclear reactor)|Jōyō]] 
|- style="background:#ffc"
|'''Under construction''' || ||[[MBIR]], [[BREST-300]] || ||[[PFBR]], [[CFR-600]]
|- style="background:#ccf"
|'''Planned''' ||[[Generation IV reactor|Gen IV]] ([[Gas-cooled fast reactor|Gas]]·[[sodium-cooled fast reactor|sodium]]·[[lead-cooled fast reactor|lead]]·[[Molten Salt Reactor#Chlorine|salt]]), [[TerraPower]], Elysium MCSFR, [[Versatile Test Reactor|DoE VTR]] ||[[Beloyarsk Nuclear Power Station|BN-1200]] ||[[Stable salt reactor|Moltex]], [[ALFRED (nuclear reactor)|ALFRED]] ||[[Toshiba 4S|4S]], [[JSFR]], [[KALIMER]]
|}