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A generation III reactor is a development of generation II nuclear reactor designs incorporating evolutionary improvements in design developed during the lifetime of the generation II reactor designs. These include improved fuel technology, superior thermal efficiency, passive nuclear safety systems and standardised design for reduced maintenance and capital costs. The first Generation III reactor to begin operation was Kashiwazaki 6 (an ABWR) in 1996.

Due to the lack of reactor construction in the Western world, very few third generation reactors have been built in developed nations. In general, Generation IV designs are still in development, and might come online in the 2030s.^[1]

Overview

Though the distinction is arbitrary, the improvements in reactor technology in third generation reactors are intended to result in a longer operational life (60 years of operation, extendable to 120+ years of operation prior to complete overhaul and reactor pressure vessel replacement) compared with currently used generation II reactors (designed for 40 years of operation, extendable to 80+ years of operation prior to complete overhaul and pressure vessel replacement).

The core damage frequencies for these reactors are designed to be lower than for Generation II reactors – 60 core damage events for the EPR and 3 core damage events for the ESBWR^[2] per 100 million reactor-years are significantly lower than the 1,000 core damage events per 100 million reactor-years for BWR/4 generation II reactors.^[2]

The third generation EPR reactor was also designed to use uranium more efficiently than older Generation II reactors, using approximately 17% less uranium per unit of electricity generated than these older reactor technologies.^[3]

Response and criticism

Proponents of nuclear power and some who have historically been critical have acknowledged that third generation reactors as a whole are safer than older reactors. However, while there are some strong proponents of the American third generation designs that claim they are much safer than existing reactors in the US, other engineers, although not outright saying that they are not safer, are more conservative and have some specific concerns.

Edwin Lyman, a senior staff scientist at the Union of Concerned Scientists, has challenged specific cost-saving design choices made for two generation III reactors, both the AP1000 and ESBWR. Lyman, John Ma (a senior structural engineer at the NRC), and Arnold Gundersen (an anti-nuclear consultant) are concerned about what they perceive as weaknesses in the steel containment vessel and the concrete shield building around the AP1000 in that its containment vessel does not have sufficient safety margins in the event of a direct airplane strike.^[4]^[5] Other engineers do not agree with these concerns, and claim the containment building is more than sufficient in safety margins and factors of safety.^[5]^[6]

The Union of Concerned Scientists in 2008 referred to the EPR as the only new reactor design under consideration in the United States that "...appears to have the potential to be significantly safer and more secure against attack than today's reactors."^[7]^: 7

There have also been issues in fabricating the precision parts necessary to maintain safe operation of these reactors, with cost overruns, broken parts, and extremely fine steel tolerances causing issues with new reactors under construction in France.^[8]

Existing and future reactors

The first generation III reactors were built in Japan, in the form of Advanced Boiling Water Reactors, while several others are in construction in Europe, including the EPR at Flamanville. The next third generation reactor predicted to come on line is a Westinghouse AP1000 reactor, the Sanmen Nuclear Power Station in China, which was scheduled to become operational in 2015.^[9] Its completion has since been delayed until 2017.^[10]

In the USA, reactor designs are certified by the Nuclear Regulatory Commission (NRC). As of October 2014^[update] the commission has approved five designs, and is considering another five designs as well.^[11]

Generation III reactors

Generation III reactors operational or under construction.
Developer	Reactor name	Type	MWe (gross)	Notes
General Electric/Toshiba/Hitachi	ABWR	BWR	1356	In operation at Kashiwazari in 1996. NRC certified Aug 1997.^[7]
KEPCO	APR-1400	PWR	1450	In operation at Kori since Jan 2016.
CGNPG/CNNC	Hualong One			Development of the CPR-1000 and ACP1000 Chinese reactors.^[12]
OKB Gidropress	VVER-1200/392M		1200	Prototype unit expected to be operating by 2017 at Novovoronezh II NPP.
	VVER-1200/491			Sold as MIR-1200. Prototype unit expected to be operating by 2018 at Leningrad.
	VVER-1200/513			First unit expected to be completed by 2022 at Akkuyu.
OKBM	BN-800	FBR	880	Demonstration fast reactor in commercial operation at Beloyarsk 4 since Aug 2016.

Generation III designs not adopted or built yet

Developer	Reactor name	Type	MWe (gross)	Notes
Mitsubishi	APWR	PWR	1700	Two units planned at Tsuruga cancelled in 2011.
Westinghouse	AP600			NRC certified in 1999.^[7]Evolved into the larger AP1000 design.^[13]
Combustion Engineering	System 80+			NRC certified in May 1997.^[7] Provided a basis for the Korean APR-1400.^[14]
Candu Energy Inc.	EC6	PHWR	750
BARC	Advanced Heavy Water Reactor	PHWR		In developement by India to utilize thorium.

Generation III+ reactors

Generation III+ designs offer significant improvements in safety and economics over Generation III advanced reactor designs certified by the NRC in the 1990s.^[15]

Generation III+ reactors under construction.
Developer	Reactor name	Type	MWe (gross)	Notes
Westinghouse/Toshiba	AP1000	PWR	1200	NRC certified Dec 2005.^[7]First unit expected to be completed by 2022 at Akkuyu.
Areva	EPR		1750	First unit expected to be completed by 2022 at Akkuyu.
Areva/Mitsubishi	ATMEA1		1150	First unit expected to be completed by 2022 at Akkuyu.

Generation III+ designs not adopted or built yet

Developer	Reactor name	Type	MWe (gross)	Notes
General Electric/Hitachi	ESBWR	BWR	1600	Based on the ABWR.
KEPCO	APR+	PWR	1550	APR-1400 with increased output and safety features.
OKB Gidropress	VVER-1300/510		1255	Also referred to as VVER-TOI, based on V392M.
Babcock & Wilcox/Bechtel	B&W mPower		160	Small modular reactor. [1]
Candu Energy Inc.	ACR-1000	PHWR	1200

References

^ "Generation IV Nuclear Reactors". World Nuclear Association.
^ ^a ^b Next-generation nuclear energy: The ESBWR
^ page 126. 3 Rs of Nuclear Power: Reading, Recycling, and Reprocessing Making a Better ... By Jan Forsythe
^ Adam Piore (June 2011). "Nuclear energy: Planning for the Black Swan". Scientific American. {{cite web}}: Missing or empty |url= (help)
^ ^a ^b Matthew L. Wald. Critics Challenge Safety of New Reactor Design New York Times, April 22, 2010.
^ "Sunday Dialogue: Nuclear Energy, Pro and Con". New York Times. February 25, 2012.
^ ^a ^b ^c ^d ^e "Nuclear Power in a warming world" (PDF). Union of Concerned Scientists. Dec 2007. Retrieved 1 October 2008.
^ "Flaw found in French nuclear reactor - BBC News". BBC News. Retrieved 2015-10-29.
^ "China Nuclear Power". World Nuclear Association. Retrieved 2014-07-14.
^ "Newbuild: CNNC Reveals New Delay at Sanmen -- to 2017". Nuclear Intelligence Group. 29 May 2015. Retrieved 2 April 2016.
^ "Design Certification Applications for New Reactors". U.S. Nuclear Regulatory Commission.
^ "China's progress continues". Nuclear Engineering International. 11 August 2015. Retrieved 30 October 2015.
^ "New Commercial Reactor Designs". Archived from the original on 2009-01-02.
^ http://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html#_ftn4
^ http://www.gnep.energy.gov/pdfs/FS_GenIV.pdf DEAD URL - Try http://nuclear.energy.gov/pdfFiles/factSheets/NGNP-GENIV-Final-Jan31-07.pdf

External links

[1] "Generation IV Nuclear Reactors". World Nuclear Association.

[ansESBWR-2] Next-generation nuclear energy: The ESBWR

[3] 126. 3 Rs of Nuclear Power: Reading, Recycling, and Reprocessing Making a Better ... By Jan Forsythe

[bs11-4] Adam Piore (June 2011). "Nuclear energy: Planning for the Black Swan". Scientific American. {{cite web}}: Missing or empty |url= (help)

[mlw-5] Matthew L. Wald. Critics Challenge Safety of New Reactor Design New York Times, April 22, 2010.

[nytimes.com-6] "Sunday Dialogue: Nuclear Energy, Pro and Con". New York Times. February 25, 2012.

[ucs-npww-7] "Nuclear Power in a warming world" (PDF). Union of Concerned Scientists. Dec 2007. Retrieved 1 October 2008.

[8] "Flaw found in French nuclear reactor - BBC News". BBC News. Retrieved 2015-10-29.

[9] "China Nuclear Power". World Nuclear Association. Retrieved 2014-07-14.

[ei-887931-10] "Newbuild: CNNC Reveals New Delay at Sanmen -- to 2017". Nuclear Intelligence Group. 29 May 2015. Retrieved 2 April 2016.

[NRC-DCANR-11] "Design Certification Applications for New Reactors". U.S. Nuclear Regulatory Commission.

[nei-20150811-12] "China's progress continues". Nuclear Engineering International. 11 August 2015. Retrieved 30 October 2015.

[13] "New Commercial Reactor Designs". Archived from the original on 2009-01-02.

[14] ttp://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html#_ftn4

[gnep.energy.gov-15] ttp://www.gnep.energy.gov/pdfs/FS_GenIV.pdf DEAD URL - Try http://nuclear.energy.gov/pdfFiles/factSheets/NGNP-GENIV-Final-Jan31-07.pdf

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@@ Line 1: / Line 1: @@
+[[File:ABWR Toshiba 1.jpg|thumb|Model of Toshiba ABWR. The first Generation III reactor to come online in 1996.]]
-A '''generation III reactor''' is a development of [[Generation II reactor|generation II]] [[nuclear reactor]] designs incorporating evolutionary improvements in design developed during the lifetime of the generation&nbsp;II reactor designs. These include improved [[Nuclear fuel|fuel technology]], superior [[thermal efficiency]], [[passive nuclear safety]] systems and [[Design to standards|standardised design]] for reduced maintenance and capital costs. The first Generation III reactor to begin operation was [[Kashiwazaki-Kariwa Nuclear Power Plant|Kashiwazaki]] (an [[ABWR]]) in 1996.
+A '''generation III reactor''' is a development of [[Generation II reactor|generation II]] [[nuclear reactor]] designs incorporating evolutionary improvements in design developed during the lifetime of the generation&nbsp;II reactor designs. These include improved [[Nuclear fuel|fuel technology]], superior [[thermal efficiency]], [[passive nuclear safety]] systems and [[Design to standards|standardised design]] for reduced maintenance and capital costs. The first Generation III reactor to begin operation was [[Kashiwazaki-Kariwa Nuclear Power Plant|Kashiwazaki 6]] (an [[ABWR]]) in 1996.
 Due to the lack of reactor construction in the Western world, very few third generation reactors have been built in developed nations. In general, [[Generation IV reactor|Generation IV]] designs are still in development, and might come online in the 2030s.<ref>{{cite web|title=Generation IV Nuclear Reactors|url=http://www.world-nuclear.org/info/Nuclear-Fuel-Cycle/Power-Reactors/Generation-IV-Nuclear-Reactors/|publisher=World Nuclear Association}}</ref>
 == Overview ==
-The improvements in reactor technology in third generation reactors are intended to result in a longer operational life (60 years of operation, extendable to 120+&nbsp;years of operation prior to complete overhaul and [[reactor pressure vessel]] replacement) compared with currently used generation&nbsp;II reactors (designed for 40&nbsp;years of operation, extendable to 80+&nbsp;years of operation prior to complete overhaul and RPV replacement).
+Though the distinction is arbitrary, the improvements in reactor technology in third generation reactors are intended to result in a longer operational life (60 years of operation, extendable to 120+&nbsp;years of operation prior to complete overhaul and [[reactor pressure vessel]] replacement) compared with currently used generation&nbsp;II reactors (designed for 40&nbsp;years of operation, extendable to 80+&nbsp;years of operation prior to complete overhaul and pressure vessel replacement).
-The [[Core damage frequency|core damage frequencies]] for these reactors are designed to be lower than for Generation II reactors – 60 core damage events per 100 million reactor-years for the [[European Pressurized Reactor|EPR]]; 3 core damage events per 100 million reactor-years for the [[Economic Simplified Boiling Water Reactor|ESBWR]]<ref name="ansESBWR">[http://www.ans.org/pubs/magazines/nn/docs/2006-1-3.pdf Next-generation nuclear energy: The ESBWR]</ref> significantly lower than the 1,000 core damage events per 100 million reactor-years for BWR/4 generation II reactors.<ref name="ansESBWR" />
+The [[Core damage frequency|core damage frequencies]] for these reactors are designed to be lower than for Generation II reactors – 60 core damage events for the [[European Pressurized Reactor|EPR]] and 3 core damage events for the [[Economic Simplified Boiling Water Reactor|ESBWR]]<ref name="ansESBWR">[http://www.ans.org/pubs/magazines/nn/docs/2006-1-3.pdf Next-generation nuclear energy: The ESBWR]</ref> per 100 million reactor-years are significantly lower than the 1,000 core damage events per 100 million reactor-years for BWR/4 generation II reactors.<ref name="ansESBWR" />
 The third generation [[European Pressurized Reactor|EPR]] reactor was also designed to use [[uranium]] more efficiently than older [[Generation II reactor]]s, using approximately 17% less uranium per unit of electricity generated than these older reactor technologies.<ref>[http://books.google.ie/books?id=LZ7zBwWLyLEC&pg=PA121&lpg=PA121&dq=ipsr+reactor&source=bl&ots=RjrcdZBH5t&sig=CFdyY4mBX774oMKN2D-Z2OAiZKk&hl=en&sa=X&ei=C5gvUdSXA5GThgft44DQAw&ved=0CD4Q6AEwAg#v=onepage&q=ipsr%20reactor&f=false page 126.  3 Rs of Nuclear Power: Reading, Recycling, and Reprocessing Making a Better ... By Jan Forsythe]</ref>
@@ Line 15: / Line 16: @@
 [[Edwin Lyman]], a senior staff scientist at the [[Union of Concerned Scientists]], has challenged specific cost-saving design choices made for two generation III reactors, both the [[AP1000]] and [[ESBWR]]. Lyman, John Ma (a senior structural engineer at the NRC), and [[Arnold Gundersen]] (an [[anti-nuclear]] consultant) are concerned about what they perceive as weaknesses in the steel containment vessel and the concrete shield building around the AP1000 in that its containment vessel does not have sufficient safety margins in the event of a direct airplane strike.<ref name="bs11">{{cite web |title=Nuclear energy: Planning for the Black Swan |author=Adam Piore |date=June 2011 |work=Scientific American }}</ref><ref name="mlw">Matthew L. Wald. [http://green.blogs.nytimes.com/2010/04/21/critics-challenge-safety-of-new-nuclear-reactor-design/?src=busln Critics Challenge Safety of New Reactor Design] ''New York Times'', April 22, 2010.</ref> [[AP1000|Other engineers do not agree with these concerns]], and claim the containment building is more than sufficient in safety margins and [[factor of safety|factors of safety]].<ref name=mlw>Matthew L. Wald. [http://green.blogs.nytimes.com/2010/04/21/critics-challenge-safety-of-new-nuclear-reactor-design/?src=busln Critics Challenge Safety of New Reactor Design] ''New York Times'', April 22, 2010.</ref><ref name="nytimes.com">{{cite news |url=http://www.nytimes.com/2012/02/26/opinion/sunday/sunday-dialogue-nuclear-energy-pro-and-con.html?_r=2&pagewanted=all |title=Sunday Dialogue: Nuclear Energy, Pro and Con |author= |date=February 25, 2012 |work=New York Times }}</ref>
-The [[Union of Concerned Scientists]] in 2008 referred to the [[European Pressurized Reactor|EPR]] as the only new reactor design under consideration in the United States that "...appears to have the potential to be significantly safer and more secure against attack than today's reactors."<ref name="ucs-npww" />{{rp|7}}
+The [[Union of Concerned Scientists]] in 2008 referred to the [[European Pressurized Reactor|EPR]] as the only new reactor design under consideration in the United States that "...appears to have the potential to be significantly safer and more secure against attack than today's reactors."<ref name="ucs-npww">{{cite web|url=http://www.ucsusa.org/assets/documents/nuclear_power/nuclear-power-in-a-warming-world.pdf|title=Nuclear Power in a warming world.|date=Dec 2007|format=PDF|work=Union of Concerned Scientists|accessdate=1 October 2008}}</ref>{{rp|7}}
 There have also been issues in fabricating the precision parts necessary to maintain safe operation of these reactors, with cost overruns, broken parts, and extremely fine steel tolerances causing issues with new reactors under construction in [[Nuclear power in France|France]].<ref>{{Cite web|title = Flaw found in French nuclear reactor - BBC News|url = http://www.bbc.com/news/science-environment-33469774|website = BBC News|accessdate = 2015-10-29}}</ref>
 === Existing and future reactors ===
-The first generation III reactors were built in Japan, in the form of [[Advanced Boiling Water Reactor]]s, while several others are in construction in Europe, including the [[European Pressurized Reactor|EPR]] at Flamanville. The next third generation reactor predicted to come on line is a Westinghouse [[AP1000]] reactor, the [[Sanmen Nuclear Power Station]] in China, which was scheduled to become operational in 2015.<ref>{{cite web|title=China Nuclear Power|url=http://www.world-nuclear.org/info/Country-Profiles/Countries-A-F/China--Nuclear-Power/|publisher=World Nuclear Association|accessdate=2014-07-14}}</ref> Its completion has since been delayed until 2017.<ref name="ei-887931">{{cite news |url=http://www.energyintel.com/pages/articlesummary/887931/newbuild--cnnc-reveals-new-delay-at-sanmen----to-2017|publisher= Nuclear Intelligence Group |date=29 May 2015 |accessdate=2 April 2016|title=Newbuild: CNNC Reveals New Delay at Sanmen -- to 2017}}</ref>
+The first generation III reactors were built in Japan, in the form of [[Advanced Boiling Water Reactor]]s, while several others are in construction in Europe, including the [[European Pressurized Reactor|EPR]] at [[Flamanville Nuclear Power Plant|Flamanville]]. The next third generation reactor predicted to come on line is a Westinghouse [[AP1000]] reactor, the [[Sanmen Nuclear Power Station]] in China, which was scheduled to become operational in 2015.<ref>{{cite web|title=China Nuclear Power|url=http://www.world-nuclear.org/info/Country-Profiles/Countries-A-F/China--Nuclear-Power/|publisher=World Nuclear Association|accessdate=2014-07-14}}</ref> Its completion has since been delayed until 2017.<ref name="ei-887931">{{cite news |url=http://www.energyintel.com/pages/articlesummary/887931/newbuild--cnnc-reveals-new-delay-at-sanmen----to-2017|publisher= Nuclear Intelligence Group |date=29 May 2015 |accessdate=2 April 2016|title=Newbuild: CNNC Reveals New Delay at Sanmen -- to 2017}}</ref>
 In the USA, reactor designs are certified by the [[Nuclear Regulatory Commission]] (NRC). {{As of|2014|10}} the commission has approved five designs, and is considering another five designs as well.<ref name=NRC-DCANR>{{cite web |url=http://www.nrc.gov/reactors/new-reactors/design-cert.html |title=Design Certification Applications for New Reactors |website=U.S. Nuclear Regulatory Commission}}</ref>
 ==Generation III reactors==
+{| class="wikitable"
-*[[Advanced Boiling Water Reactor]] (ABWR) — a [[GE]] design that first went online in Japan in 1996. [[Nuclear Regulatory Commission|NRC]] certified Aug 1997.<ref name=ucs-npww/>
+|+Generation III reactors operational or under construction.
-*[[Advanced Pressurized Water Reactor]] (APWR) — developed by [[Mitsubishi Heavy Industries]].
+!Developer
-*Enhanced [[CANDU]] 6 (EC6) — developed by [[Candu Energy Inc.]] (former part of [[Atomic Energy of Canada Limited]]).
+!Reactor name
-*[[Hualong One]] — a Chinese development of the [[CPR-1000]] and ACP1000, originally based on the French 900 MWe design.<ref name=nei-20150811>{{cite news |url=http://www.neimagazine.com/features/featurechinas-progress-continues-4644048/ |title=China's progress continues |publisher=Nuclear Engineering International |date=11 August 2015 |accessdate=30 October 2015}}</ref>
+!Type
-*[[VVER]]-1000/392 (PWR) — in various modifications into [[AES-91]] and [[AES-92]].
+!MWe (gross)
+!Notes
+|-
+|[[General Electric]]/[[Toshiba]]/[[Hitachi]]
+|[[Advanced boiling water reactor|ABWR]]
+|[[Boiling water reactor|BWR]]
+|1356
+|In operation at [[Kashiwazaki-Kariwa Nuclear Power Plant|Kashiwazari]] in 1996. [[Nuclear Regulatory Commission|NRC]] certified Aug 1997.<ref name="ucs-npww" />
+|-
+|[[Korea Electric Power Corporation|KEPCO]]
+|[[APR-1400]]
+| rowspan="5" |[[Pressurized water reactor|PWR]]
+|1450
+|In operation at [[Kori Nuclear Power Plant|Kori]] since Jan 2016.
+|-
+|[[China General Nuclear Power Group|CGNPG]]/[[China National Nuclear Corporation|CNNC]]
+|[[CPR-1000|Hualong One]]
+|
+|Development of the [[CPR-1000]] and ACP1000 Chinese reactors.<ref name="nei-20150811">{{cite news|url=http://www.neimagazine.com/features/featurechinas-progress-continues-4644048/|title=China's progress continues|date=11 August 2015|publisher=Nuclear Engineering International|accessdate=30 October 2015}}</ref>
+|-
+| rowspan="3" |[[OKB Gidropress]]
+|[[VVER]]-1200/392M
+| rowspan="3" |1200
+|Prototype unit expected to be operating by 2017 at [[Novovoronezh Nuclear Power Plant II|Novovoronezh II NPP]].
+|-
+|VVER-1200/491
+|Sold as MIR-1200. Prototype unit expected to be operating by 2018 at [[Leningrad Nuclear Power Plant|Leningrad]].
+|-
+|VVER-1200/513
+|First unit expected to be completed by 2022 at [[Akkuyu Nuclear Power Plant|Akkuyu]].
+|-
+|OKBM
+|[[BN-800 reactor|BN-800]]
+|[[Breeder reactor|FBR]]
+|880
+|Demonstration fast reactor in commercial operation at [[Beloyarsk Nuclear Power Station|Beloyarsk 4]] since Aug 2016.
+|}
-===Third generation designs not adopted or built yet ===
+===Generation III designs not adopted or built yet ===
+{| class="wikitable"
-*[[AP600]] — A [[Westinghouse Electric Company]] design that received final design approval from the [[Nuclear Regulatory Commission]] in 1998; the [[Energy Information Administration|EIA]] states that "Westinghouse has deemphasized the AP600 in favor of the larger, though potentially even less expensive (on a cost per kilowatt or capacity basis) AP1000 design."<ref>{{cite web
+!Developer
-|title=New Commercial Reactor Designs
+!Reactor name
-|url=http://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html#_ftn1
+!Type
-|archiveurl=https://web.archive.org/web/20090102231140/http://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html
+!MWe (gross)
-|archivedate=2009-01-02}}</ref> NRC certified Dec 1999.<ref name=ucs-npww/>
+!Notes
-*[[System 80|System 80+]] — a [[Combustion Engineering]] (now incorporated into Westinghouse) design, which "provides a basis for the [[APR-1400|APR1400]] (Generation III+) design that has been developed in [[South Korea|Korea]] for future deployment and possible export."<ref>http://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html#_ftn4</ref> NRC certified May 1997.<ref name=ucs-npww>{{cite web |url=http://www.ucsusa.org/assets/documents/nuclear_power/nuclear-power-in-a-warming-world.pdf |title=Nuclear Power in a warming world. |date=Dec 2007 |work=Union of Concerned Scientists |format=PDF |accessdate=1 October 2008}}</ref>
+|-
-*[[Advanced Heavy Water Reactor]] being developed by [[Bhabha Atomic Research Centre|BARC]], India to utilize thorium.
+|[[Mitsubishi Heavy Industries|Mitsubishi]]
+|[[Mitsubishi APWR|APWR]]
+| rowspan="3" |PWR
+|1700
+|Two units planned at [[Tsuruga Nuclear Power Plant|Tsuruga]] cancelled in 2011.
+|-
+|[[Westinghouse Electric Company|Westinghouse]]
+|[[AP600]]
+|
+|NRC certified in 1999.<ref name="ucs-npww" />Evolved into the larger AP1000 design.<ref>{{cite web|url=http://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html#_ftn1|title=New Commercial Reactor Designs|archiveurl=https://web.archive.org/web/20090102231140/http://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html|archivedate=2009-01-02}}</ref>
+|-
+|[[Combustion Engineering]]
+|[[System 80|System 80+]]
+|
+|NRC certified in May 1997.<ref name="ucs-npww" /> Provided a basis for the [[South Korea|Korean]] [[APR-1400|APR-1400]].<ref>http://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html#_ftn4</ref>
+|-
+|[[Candu Energy Inc.]]
+|[[CANDU reactor|EC6]]
+| rowspan="2" |[[Pressurized heavy-water reactor|PHWR]]
+|750
+|
+|-
+|[[Bhabha Atomic Research Centre|BARC]]
+|[[Advanced Heavy Water Reactor]]
+|
+|In developement by India to utilize thorium.
+|}
 ==Generation III+ reactors==
 Generation III+ designs offer significant improvements in safety and economics over Generation III advanced reactor designs certified by the NRC in the 1990s.<ref name="gnep.energy.gov">http://www.gnep.energy.gov/pdfs/FS_GenIV.pdf DEAD URL - Try http://nuclear.energy.gov/pdfFiles/factSheets/NGNP-GENIV-Final-Jan31-07.pdf</ref>
+{| class="wikitable"
-*[[Advanced CANDU Reactor]] (ACR-1000)
+|+Generation III+ reactors under construction.
-*[[AP1000]] — based on the [[AP600]] with increased power output. [[Nuclear Regulatory Commission|NRC]] certified Dec 2005.<ref name=ucs-npww/>
+!Developer
-*[[European Pressurized Reactor]] (EPR) — an evolutionary descendant of the [[Framatome]] N4 and [[Siemens AG|Siemens Power Generation Division]] KONVOI reactors.<ref name="gnep.energy.gov"/>
+!Reactor name
-*[[Economic Simplified Boiling Water Reactor]] ([[ESBWR]]) — based on the [[ABWR]]
+!Type
-*[[APR-1400]] — an advanced PWR design evolved from the U.S. System 80+, which is the basis for the Korean Next Generation Reactor or KNGR [http://world-nuclear.org/info/default.aspx?id=528]
+!MWe (gross)
-*[[VVER]]-1200
+!Notes
-** V392M (PWR) — in design of [[AES-2006]]/92 with mainly passive safety features
+|-
-** V491 (PWR) — in design of [[AES-2006]]/91 with mainly active safety features, international sold as MIR.1200
+|Westinghouse/Toshiba
-** V513 (PWR) — in design of [[AES-2006]]/91M with active and passive safety features and VVER-TOI-features, based von V491 and V510
+|[[AP1000]]
-* VVER-1300
+| rowspan="3" |PWR
-** V510 (PWR) — in design of AES-2010 (also referred to as [[VVER-TOI]]), based on V392M
+|1200
-*EU-ABWR — based on the [[ABWR]] with increased power output and compliance with EU safety standard.
+|[[Nuclear Regulatory Commission|NRC]] certified Dec 2005.<ref name="ucs-npww" />First unit expected to be completed by 2022 at [[Akkuyu Nuclear Power Plant|Akkuyu]].
-* [[B&W mPower]] — an Advanced Light Water Reactor in development by [[Babcock & Wilcox]] and [[Bechtel]] [http://www.babcock.com/products/modular_nuclear/generation_mpower.html]
+|-
-The first Generation III+ reactor released electricity to the grid on 5 Aug 2016 (Unit 6 of Novovoronezh NPP also known as Unit 1 of [[Novovoronezh Nuclear Power Plant II|Novovoronezh II NPP]], VVER-1200/392M).<ref>[http://rosatom.ru/en/press-centre/news/newest-most-powerful-in-russia-nuclear-reactor-of-novovoronezh-npp-has-released-first-electricity-to/ Newest, most powerful in Russia nuclear reactor of Novovoronezh NPP has released first electricity to the grid] //  Information and Public Relations Department of Concern Rosenergoatom JSC, Information and Public Relations Department of Novovoronezh NPP, Rosatom</ref>
+|[[Areva]]
+|[[EPR (nuclear reactor)|EPR]]
+|1750
+|First unit expected to be completed by 2022 at [[Akkuyu Nuclear Power Plant|Akkuyu]].
+|-
+|Areva/[[Mitsubishi Heavy Industries|Mitsubishi]]
+|ATMEA1
+|1150
+|First unit expected to be completed by 2022 at [[Akkuyu Nuclear Power Plant|Akkuyu]].
+|}
+=== Generation III+ designs not adopted or built yet ===
+{| class="wikitable"
+!Developer
+!Reactor name
+!Type
+!MWe (gross)
+!Notes
+|-
+|General Electric/Hitachi
+|[[Economic Simplified Boiling Water Reactor|ESBWR]]
+|BWR
+|1600
+|Based on the [[ABWR]].
+|-
+|KEPCO
+|[[APR-1400|APR+]]
+| rowspan="3" |PWR
+|1550
+|APR-1400 with increased output and safety features.
+|-
+|OKB Gidropress
+|VVER-1300/510
+|1255
+|Also referred to as [[VVER-TOI]], based on V392M.
+|-
+|[[Babcock & Wilcox]]/[[Bechtel]]
+|[[B&W mPower]]
+|160
+|[[Small modular reactor]]. [http://www.babcock.com/products/modular_nuclear/generation_mpower.html]
+|-
+|Candu Energy Inc.
+|[[Advanced CANDU reactor|ACR-1000]]
+|PHWR
+|1200
+|
+|}
 ==See also==