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Decommissioning Nuclear Facilities

(Updated March 2014)

  • To date, about 100 mines, over 100 commercial power reactors, 46 experimental or prototype reactors, over 250 research reactors and a number of fuel cycle facilities, have been retired from operation. Some of these have been fully dismantled.
  • Most parts of a nuclear power plant do not become radioactive, or are contaminated at only very low levels. Most of the metal can be recycled.
  • Proven techniques and equipment are available to dismantle nuclear facilities safely and these have now been well demonstrated in several parts of the world.
  • Decommissioning costs for nuclear power plants, including disposal of associated wastes, are reducing and contribute only a small fraction of the total cost of electricity generation.

All power plants, coal, gas and nuclear, have a finite life beyond which it is not economically feasible to operate them. Generally speaking, early nuclear plants were designed for a life of about 30 years, though some have proved capable of continuing well beyond this. Newer plants are designed for a 40 to 60 year operating life. At the end of the life of any power plant, it needs to be decommissioned, cleaned up and demolished so that the site is made available for other uses. 

For nuclear plants, the term decommissioning includes all clean-up of radioactivity and progressive dismantling of the plant. This may start with the owner's decision to write it off or declare that it is permanently removed from operation. For practical purposes it includes defueling and removal of coolant, though NRC at least defines it as strictly beginning only after fuel and coolant are removed. It concludes with licence termination after decontamination is verified and wastes removed.

A Table showing over 140 decommissioned reactors is at the end of this paper.

Decommissioning Options

The International Atomic Energy Agency (IAEA) has defined three options for decommissioning, the definitions of which have been internationally adopted:

  • Immediate Dismantling (or Early Site Release/'Decon' in the US): This option allows for the facility to be removed from regulatory control relatively soon after shutdown or termination of regulated activities. Final dismantling or decontamination activities can begin within a few months or years, depending on the facility. Following removal from regulatory control, the site is then available for re-use.
  • Safe Enclosure ('Safstor') or deferred dismantling: This option postpones the final removal of controls for a longer period, usually in the order of 40 to 60 years. The facility is placed into a safe storage configuration until the eventual dismantling and decontamination activities occur after resudual radioactivity has decayed.
  • Entombment (or 'Entomb'): This option entails placing the facility into a condition that will allow the remaining on-site radioactive material to remain on-site without ever removing it totally. This option usually involves reducing the size of the area where the radioactive material is located and then encasing the facility in a long-lived structure such as concrete, that will last for a period of time to ensure the remaining radioactivity is no longer of concern.

Each approach has its benefits and disadvantages. National policy determines which approach or combination of approaches is adopted or allowed. In the case of immediate dismantling (or early site release), responsibility for completion of decommissioning is not transferred to future generations. The experience and skills of operating staff can also be utilised during the decommissioning program. Alternatively, Safe Enclosure (or Safstor) allows significant reduction in residual radioactivity, thus reducing radiation hazard during the eventual dismantling. The expected improvements in mechanical techniques should also lead to a reduction in the hazard and also costs.

In the case of nuclear reactors, about 99% of the radioactivity is associated with the fuel which is removed following permanent shutdown. Apart from any surface contamination of plant, the remaining radioactivity comes from "activation products" such as steel components that have long been exposed to neutron irradiation. Their atoms are changed into different isotopes such as iron-55, iron, 59 and zinc-65. Several are highly radioactive, emitting gamma rays. However, their half life is such (2.7 years, 45 days, 5.3 years, 245 days respectively) after 50 years from closedown their radioactivity is much diminished and the occupational risk to workers largely gone.

Decommissioning Experience

Considerable experience has been gained in decommissioning various types of nuclear facilities. About 85 commercial power reactors, 45 experimental or prototype power reactors, as well as over 250 research reactors and a number of fuel cycle facilities, have been retired from operation. Of the 140+ power reactors including experimental and prototype units, at least 15 have been fully dismantled, over 50 are being dismantled, over 50 are in Safstor, three have been entombed, and for others the decommissioning strategy is not yet specified.

(Ships and numerous submarines have also been decommissioned but are not included in this paper.)

European reactors

To decommission its retired gas-cooled reactors at the Chinon, Bugey and St Laurent nuclear power stations, Electricité de France (EdF) chose partial dismantling and postponed final dismantling and demolition for 50 years. As other reactors will continue to operate at those sites, monitoring and surveillance do not add to the cost.

A recycling plant for steel from dismantled nuclear facilities is at Marcoule, in France. This metal will contain some activation products, but it can be recycled for other nuclear plants.

Decommissioning has begun at 29 UK reactors, 25 of them early Magnox types with graphite moderators.* One of the first was Berkeley nuclear power station (2 x 138 MWe), closed for economic reasons in 1989 after 27 years of operation, where defuelling was completed in 1992. The cooling ponds were then drained, cleaned and filled in and the turbine hall was dismantled and demolished. The reactor buildings are in an extended Safstor period. Ultimately they too will be dismantled, leaving the site to be leveled and landscaped. The same pattern is being followed at other UK reactor sites.

* Costs for decommissioning gas-cooled reactors are much higher per unit of capacity than for light water reactors – at least five times for Magnox. This is due to the large volume of material and the need to dispose of a lot of graphite moderator. Decommissioning waste volumes per unit capacity for Magnox are ten times those for western light water reactors. See also following subsection on Graphite.

Spain's Vandellos 1, a 480 MWe gas-graphite reactor, was closed down in 1990 after 18 years operation, due to a turbine fire which made the plant uneconomic to repair. In 2003 ENRESA concluded phase 2 of the reactor decommissioning and dismantling project, which allowed much of the site to be released. After 30 years Safestor, when activity levels have diminished by 95%, the remainder of the plant will be removed. The cost of the 63-month project was EUR 93 million.

Eleven of Germany’s 19 decommissioned units are subject to immediate dismantling. (It is not yet clear if and when the eight units shut down in March 2011 for political reasons will be decommissioned. The four operators have EUR 30 billion set aside for decommissioning and waste disposal.)

Germany chose immediate dismantling over safe enclosure for the closed Greifswald nuclear power station in the former East Germany, where five reactors had been operating. Similarly, the site of the 100 MWe Niederaichbach nuclear power plant in Bavaria was declared fit for unrestricted agricultural use in mid-1995. The 250 MWe Gundremmingen A unit was Germany's first commercial nuclear reactor, operating 1966-77. Decommissioning work started in 1983, and moved to the more contaminated parts in 1990, using underwater cutting techniques. This project demonstrated that decommissioning could be undertaken safely and economically without long delays, and recycling most of the metal.

Japan's Tokai 1 reactor, a 160 MWe UK Magnox design, is being decommissioned after 32 years service to 1998. After 10 years storage, in Phase 2 (to 2011) the steam generators and turbines were removed, and in Phase 3 (to 2018) the reactor will be dismantled, the buildings demolished and the site left ready for re-use. The total cost will be JPY 93 billion (USD 1.04 billion) – 35 billion for dismantling and 58 billion for waste treatment which will include the graphite moderator (which escalates the cost significantly, see subsection below).

US reactors

Experience in the USA has varied, but 13 power reactors are using the Safestor approach, while 16 – mostly single-unit plants – are using, or have used, Decon. 

Procedures are set by the Nuclear Regulatory Commission (NRC), and considerable experience has now been gained. A total of 32 power reactors have been closed and decommissioned. NRC requires that the operating license of a closed reactor be terminated and decommissioning activities be completed within 60 years. Site release often excludes the on-site used fuel storage in an ISFSI (independent spent fuel storage installation), which usually remains, to await the Department of Energy taking away the used fuel (over which it has title) to a national repository sometime in the future.

Rancho Seco (single 913 MWe, PWR) was closed in 1989, and in 1995 NRC approved a Safestor plan for it. However, the utility subsequently decided upon incremental dismantling and this was completed in 2009, leaving about 3 ha still under NRC licence for waste storage. About 32 ha has been released for unrestricted use.

At multi-unit nuclear power stations, the choice has been to place the first closed unit into storage until the others end their operating lives, so that all can be decommissioned in sequence. This will optimise the use of staff and the specialised equipment required for cutting and remote operations, and achieve cost benefits.

Thus, after 14 years of comprehensive clean-up activities, including the removal of fuel, debris and water from the 1979 accident, Three Mile Island 2 was placed in Post-Defuelling Monitored Storage (Safstor) until the operating licence of Unit 1expires, so that both units can be dismantled together.

San Onofre 1, which closed in 1992, was put into Safestor until licences for Units 2 and 3 expired in 2022-23.  However, after NRC changes, dismantling was brought forward to 1999, so it became an active Decon project which was largely completed in 2008. A small amount of work remains to be completed with eventual dismantling of units 2 & 3 on the site, which were shut down in May 2013. The cost of fully decommissioning them is estimated at $4 billion.

A US Decon project was the 60 MWe Shippingport reactor, which operated commercially from 1957 to 1982. It was used to demonstrate the safe and cost-effective dismantling of a commercial scale nuclear power plant and the early release of the site. Defuelling was completed in two years, and five years later the site was released for use without any restrictions. Because of its size, the pressure vessel could be removed and disposed of intact. For larger units, such components have to be cut up.

Immediate Decon also the option chosen for Fort St Vrain, a 330 MWe high temperature gas-cooled reactor which was closed in 1989. This took place on a fixed-price contract for US$ 195 million (hence costing less than 1 cent/kWh despite only a 16-year operating life) and the project proceeded on schedule to clear the site and relinquish its licence early in 1997 - the first US power reactor of this size to achieve this. 

Shoreham BWR, on Long Island, generated very little power and never received a full operating licence, so the level of activation products was minimal. It was shut down in 1989 and became a Decon project, completed in 1994. The 59 MWe Pathfinder prototype BWR in South Dakota, shut down in 1967 after a very short life was also a Decon project, completed in 1992. Haddam Neck 560 MWe PWR in Connecticut, closed in 1996 after 29 years operation, was a further Decon project, completed in 2007.

For Trojan (1180 MWe, PWR) in Oregon the dismantling was undertaken by the utility itself. The plant closed in 1993, steam generators were removed, transported and disposed of at Hanford in 1995, and the reactor vessel (with internals) was removed and transported to Hanford in 1999. Except for the used fuel storage, the site was released for unrestricted use in 2005. The cooling tower was demolished in 2006.

Another US Decon project was Maine Yankee, a 860 MWe PWR plant which closed down in 1996 after 24 years operation. The containment structure was finally demolished in 2004 and except for 5 ha with the dry store for used fuel, the site was released for unrestricted public use in 2005, on budget and on schedule.

Connecticut Yankee (590 MWe PWR) also shut down in 1996 after 28 years operation. Decommissioning work began in 1998 and demolition was concluded in 2006. The site was released for unrestricted public use in 2007, apart from 2 ha for dry cask used fuel storage. Residual contamination on the land is below NRC's limit of 0.25 millisievert per year for maximum radiation dose.

In 2006 the site of 72 MWe Big Rock Point nuclear power plant in Michigan, shut down in 1997 after 35 years operation, was largely returned to greenfield status. In January 2007 most of the land was released for derestricted public use, though 43 hectares still has the dry cask storage facility where used fuel is stored pending transfer to the national repository.

With Exelon's Zion 1&2 reactors (2 x 1098 MWe) closed down in 1998 and initially in Safstor, a slightly different process is envisaged, considerably accelerating the decommissioning. Exelon has contracted with a specialist company – EnergySolutions – to remove the plant and return the site to greenfield status. To achieve this, the plant's licence and decommissioning funds will be transferred to EnergySolutions, which will then be owner and licensee, and the site will be returned to Exelon about 2018. Used fuel would remain on site until taken to the national repository.

Duke’s Crystal River 3 is expected to cost $1.18 billion (2013 dollars) to decommission via Safstor over 60 years, during which time the funds reserved for the purpose will accrue interest, thereby fully covering the cost, despite the fact that is was closed after only 35 years of operation. Decon would cost only $994 million, but this would be over only a few years, so the decommissioning fund would have less time to grow sufficiently to cover it. A $195 million impact on Florida ratepayers would result. Safstor will begin in July 2015 after used fuel is removed, and will end with removal of the unit’s remaining components about 2070 and site restoration in 2074. To August 2019 the spent fuel will remain in pools and from then to 2036 it will be held in a planned dry cask storage facility onsite. The spent fuel will then be moved to a federal facility.

In summary, US plants with Decon completed are: Big Rock Point, Elk River, Fort St Vrain, Haddam Neck, Maine Yankee, Pathfinder, Rancho Seco, San Onofre 1, Saxton, Shippingport, Shoreham, Trojan and Yankee Rowe. (Also Santa Susana Sodium Reactor Experimental which is not included in Tables.) Decon is in progress at Fermi 1, Humboldt Bay 3, LaCrosse, Zion 1&2.

US plants in Safstor include Crystal River 3, Dresden 1, Fermi 1, Indian Point 1, LaCrosse, Kewaunee, Millstone 1, Peach Bottom 1, and Zion 1&2, as well as NS Savannah. Three Mile Island 2 is in post-defueling monitored storage. San Onofre 2&3 and later Vermont Yankee will also enter Safstor when defuelled.

The only US plants subject to the Entomb option are small experimental ones: Bonus BWR in Puerto Rico, Piqua organic-moderated reactor in Ohio, and Hallam graphite-moderated sodium-cooled reactor in Nebraska. No NRC-licensed plant has used this option.

In addition to the above is the first floating nuclear power plant, installed in a former liberty ship, and utilised at Panama 1967-76. The Sturgis had a 45 MWt/ 10 MWe (net) PWR which provided power to the Canal Zone. After it was defuelled in 1977, some 89 m3 of solid radioactive waste and 363 m3 of liquid waste was removed and the vessel placed in safstor at Fort Belvoir, Virginia until 2027.

Further information on decommissioning in USA is available from the Nuclear Energy Institute, and from NRC.

Russian reactors

Rostechnadzor oversees a major program of decommissioning old fuel cycle facilities, financed under the Federal target program on Nuclear and Radiation Safety. Six civil reactors are being decommissioned: three early LWGRs, the Melekess VK-50 prototype BWR, and two larger prototype VVER-440 units at Novovoronezh. Most were shut down 1981-90, the fuel removed, and they now await dismantling, which is staring to progress at Novovronezh.

Graphite

A number of first-generation reactors had graphite blocks as moderator. This is high-quality reactor-grade material produced at about 3000°C which accumulates some radionuclide contamination while in service, particularly carbon-14 at levels which often means that it must be classified as intermediate-level waste. While it oxidizes slightly under neutron bombardment and also at high temperatures (to CO), it does not burn, but sublimes at 3652°C. There is no risk of oxidation under Safstor conditions.

A 2006 report commissioned by EPRI states: "The graphite moderators of retired gas-cooled nuclear reactors present a difficult challenge during demolition activities. As a result, utilities have not dismantled any moderators of CO2 cooled power reactors to date." However, it concludes that adequate information exists to enable the safe dismantling and processing of graphite moderators, and that the three main options for disposal of this graphite are oxidation to the gas phase and release as carbon dioxide (difficult), direct burial, or recycling into new products for the nuclear industry. In each case, opportunities exist for pre-processing to concentrate or remove radionuclides to enhance the safety of the chosen option. The radionuclide inventory of irradiated graphite is unusual in comparison with other nuclear wastes. Cobalt-60 and tritium are the principal isotopes of short-term importance, carbon-14 and chlorine-36 are dominant in the longer term.

Other facilities

The French Atomic Energy Commission is decommissioning the UP1 reprocessing plant at Marcoule. This plant started up in 1958 and treated 18,600 tonnes of metal fuels from gas-cooled reactors (both defence and civil) to 1997. Progressive decontamination and dismantling of the plant and waste treatment will span 40 years and cost some EUR 5.6 billion, nearly half of this for treatment of the wastes stored on the site.

Areva is decommissioning the Eurodif enrichment plant at Marcoule from 2012. This will involve over 2012-15 the decontamination with ClF3 gas to remove the residual uranium left inside, and extract it as UF6, then recovery of all produced chloride and fluoride gas before the opening of equipments and circuits. Then over 2016-25 the plant will be dismantled.

Many nuclear submarines have been decommissioned over the last decade. In USA, after defuelling, the reactor compartments are cut out of the vessels and are transported inland to Hanford, where they are buried as low-level waste. Russia has decommissioned three nuclear powered icebreakers: Lenin, Sibir and Arktika.

Cost and Finance

In most countries the operator or owner is responsible for the decommissioning costs.

The total cost of decommissioning is dependent on the sequence and timing of the various stages of the program. Deferment of a stage tends to reduce its cost, due to decreasing radioactivity, but this may be offset by increased storage and surveillance costs.

Even allowing for uncertainties in cost estimates and applicable discount rates, decommissioning contributes a small fraction of total electricity generation costs. In USA many utilities have revised their cost projections downwards in the light of experience.

Financing methods vary from country to country. Among the most common are:
Prepayment, where money is deposited in a separate account to cover decommissioning costs even before the plant begins operation. This may be done in a number of ways but the funds cannot be withdrawn other than for decommissioning purposes.
External sinking fund (Nuclear Power Levy): This is built up over the years from a percentage of the electricity rates charged to consumers. Proceeds are placed in a trust fund outside the utility's control. This is the main US system, where sufficient funds are set aside during the reactor's operatinig lifetime to cover the cost of decommissioning.
Surety fund, letter of credit, or insurance purchased by the utility to guarantee that decommissioning costs will be covered even if the utility defaults.

In USA, utilities are collecting 0.1 to 0.2 cents/kWh to fund decommissioning. They must then report regularly to the NRC on the status of their decommissioning funds. About two thirds of the total estimated cost of decommissioning all US nuclear power reactors has already been collected, leaving a liability of about $9 billion to be covered over the remaining operating lives of 100 reactors (on basis of average $320 million per unit).

An OECD survey published in 2003 reported US dollar (2001) costs by reactor type. For western PWRs, most were $200-500/kWe, for VVERs costs were around $330/kWe, for BWRs $300-550/kWe, for CANDU $270-430/kWe. For gas-cooled reactors the costs were much higher due to the greater amount of radioactive materials involved, reaching $2600/kWe for some UK Magnox reactors. This last figure remains to be tested in experience.

Constraints on recycling

Recycling materials from decommissioned nuclear facilities is constrained by the level of radioactivity in them. This is also true for materials from elsewhere, such as gas plants, but the levels specified can be very different. For example, scrap steel from gas plants may be recycled if it has less than 500,000 Bq/kg (0.5 MBq/kg) radioactivity (the exemption level). This level however is one thousand times higher than the clearance level for recycled material (both steel and concrete) from the nuclear industry, where anything above 500 Bq/kg may not be cleared from regulatory control for recycling.

There is increasing concerned about double standards developing in Europe which allow 30 times the dose rate from non-nuclear recycled materials than from those out of the nuclear industry. Norway and Holland are the only countries with consistent standards. Elsewhere, 0.3 to 1.0 mSv/yr individual dose constraint is applied to oil and gas recyclables, and 0.01 mSv/yr for release of materials with the same kind of radiation from the nuclear industry. The double standard means that the same radionuclide, at the same concentration, can either be sent to deep disposal or released for use in building materials, depending on where it comes from. The 0.3 mSv/yr dose limit is still only one tenth of most natural background levels, and two orders of magnitude lower than those experienced naturally by many people, who suffer no apparent ill effects.

The main radionuclide in scrap from the oil and gas industry is radium-226, with a half-life of 1600 years as it decays to radon. Those in nuclear industry scrap are cobalt-60 and caesium-137, with much shorter half-lives. Application of a 0.3 mSv/yr dose limit results in a clearance level for Ra-226 of 500 Bq/kg, compared with 10 Bq/kg for nuclear material.

In 2011, 16 decommissioned steam generators from Bruce Power in Canada were to be shipped to Sweden for recycling. Although the Canadian Nuclear Safety Commission (CNSC) approved Bruce Power’s plans in 2011 and confirmed steam generator processing is an excellent example of responsible and safe nuclear waste management practices, this caused public controversy at the time, and following the Fukushima nuclear accident plans for this shipment were shelved. These steam generators were each 12m long and 2.5m diameter, with mass 100 t, and contained some 4g of radionuclides with about 340 GBq of activity. Exposure was 0.08 mSv/hr at one metre. They were classified as low-level waste (LLW). Studsvik in Sweden would recycle much of the metal and return about 10% of the overall volume as LLW for disposal in Ontario. The balance would be under 100 Bq/kg, which appeared to be the clearance level.

In 2012 five steam generators from UK plants were shipped to Studsvik in Sweden for recycling. Studsvik has also set up a plant in the UK, at Lillyhall in Cumbria, to recycle materials from nuclear facilities, and this became fully operational in 2013 after processing 2000 t of metal from numerous sites and recycling 96% of it. The balance went to a LLW repository.

International Cooperation

The IAEA, the OECD's Nuclear Energy Agency and the Commission of the European Communities are among a number of organisations through which experience and knowledge about decommissioning is shared among technical communities in various countries.

In 1985, the OECD Nuclear Energy Agency launched an International Co-operative Program for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects. This international collaboration, covering 15 reactors and six fuel-cycle facilities, has produced a great deal of technical and financial information.

In 2013, following the Fukushima accident, an International Research Institute for Nuclear Decommissioning (IRID) was established, based in Japan. As well as bringing together knowledge and experience from wrecked reactors, IRID will build up the knowledge base for routine decommissioning.

The important areas where experience is being gained and shared are the assessment of the radioactive inventories, decontamination methods, cutting techniques, remote operation, radioactive waste management and health and safety. The aims are to minimise the radiological hazards to workers and to optimise the dismantling sequence and timing to reduce the total decommissioning cost.

Reasons for shutdown

Most decommissioned reactors were shut down because there was no longer any economic justification for running them. Practically all are relatively early-model designs, and about 45 are experimental or prototype power reactors. Three categories are listed here:
1. Experimental, early commercial types and commercial unit whose continued operation was no longer justified, usually for economic reasons. Most of these started up before 1980 and their short life is not surprising for the first couple of decades of a major new technology. At least 41 of this 101 (* asterisked) ran relatively full-term, for a design life of 25-35 years or so (design lives today are 40-60 years). Total 104.
2. Units which closed following an accident or serious incident (not necessarily to the reactor itself) which meant that repair was not economically justified. Total 11.
3. Units which were closed prematurely by political decision or due to regulatory impediment without clear or significant economic or technical justification. Total 25, 17 of these being early Soviet designs.
In fact the distinctions are not always sharp, eg Chernobyl 2 was closed in 1991 after a turbine fire when it would have been politically impossible to repair and restart it, Rheinsberg was closed in 1990 though it was nearly at the end of its design life - both these are in the 'political decision' category.

Note that the eight German reactors shut down in 2011 are not yet listed here.

Reactors closed following damage in an accident or serious incident (11)

Country Reactor Type MWe net Years operating Shut down reason
Germany Greifswald 5 VVER-440/V213 408 0.5 11/1989 Partial core melt
  Gundremmingen A BWR 237 10 1/1977 Botched shutdown
Japan Fukushima Daiichi 1 BWR 439 40 3/2011 Core melt from cooling loss
  Fukushima Daiichi 2 BWR 760 37 3/2011 Core melt from cooling loss
  Fukushima Daiichi 3 BWR 760 35 3/2011 Core melt from cooling loss
  Fukushima Daiichi 4 BWR 760 32 3/2011 Damage from hydrogen explosion
Slovakia Bohunice A1 Prot GCHWR 93 4 1977 Core damage from fuelling error
Spain Vandellos 1 GCR 480 18 mid 1990 Turbine fire
Switzerland St Lucens Exp GCHWR 8 3 1966 Core Melt
Ukraine Chernobyl 4 RBMK LWGR 925 2 4/1986 Fire and meltdown
USA Three Mile Island 2 PWR 880 1 3/1979 Partial core melt

Reactors closed prematurely by political decision or consideration (27)

Country Reactors Type MWe net each Years operating each Shut down
Armenia Metsamor 1 VVER-440/V270 376 13 1989
Bulgaria Kozloduy 1-2 VVER-440/V230 408 27, 28 12/2002
  Kozloduy 3-4 VVER-440/V230 408 24, 26 12/2006
France Super Phenix FNR 1200 12 1999
Germany Greifswald 1-4 VVER-440/V230 408 10, 12, 15, 16 1990
  Muelheim-Kaerlich PWR 1219 2 1988
  Rheinsberg VVER-70/V210 62 24 1990
Italy Caorso BWR 860 12 1986
  Latina GCR 153 24 1987
  Trino PWR 260 25 1987
Japan Fukushima Daiichi 5 BWR 760 33 2011
  Fukushima Daiichi 6 BWR 1067 32 2011
Lithuania Ignalina 1 RBMK LWGR 1185 21 2005
  Ignalina 2 RBMK LWGR 1185 22 2009
Slovakia Bohunice 1 VVER-440/V230 408 28 12/2006
  Bohunice 2 VVER-440/V230 408 28 12/2008
Sweden Barseback 1 BWR 600 24 11/1999
  Barseback 2 BWR 600 28 5/2005
Ukraine Chernobyl 1 RBMK LWGR 740 19 12/1997
  Chernobyl 2 RBMK LWGR 925 12 1991
  Chernobyl 3 RBMK LWGR 925 19 12/2000
USA Shoreham BWR 820 3 1989

Reactors closed having fulfilled their purpose or being no longer economic to run (104+1)  

- prot= prototype, exp= experimental, * = ran approx full-term

Country Reactor type MWe net each Start-up Years operating each Shut down
Belgium BR-3 Prot PWR 10 1962 24 1987
Canada Douglas Point Prot PHWR 206 1967 17 1984
  Gentilly 1 Exp SGHWR 250 1971 6 1977
  Gentilly 2 PHWR 638 1982 30 2012
  Rolphton NPD Prot PHWR 22 1962 25 1987
France Bugey 1 GCR 540 1972 22 1994
  Chinon A1 Prot GCR 70 1963 10 1973
  Chinon A2 GCR 180 1965 20 1985
  Chinon A3 * GCR 360 1965 25 1990
  Chooz A Prot PWR 305 1967 24 1991
  Brennilis EL-4 exp GCHWR 70 1967 18 1985
  Marcoule G-1 Prot GCR 2 1956 12 1968
  Marcoule G-2 Prot GCR 39 1959 20 1980
  Marcoule G-3 Prot GCR 40 1960 24 1984
  Phenix * FNR 233 1973 37 2010
  St Laurent A1 GCR 390 1969 21 1990
  St Laurent A2 GCR 465 1971 21 1992
Germany Juelich AVR Exp HTR 13 1968 21 1989
  Uentrop THTR Prot HTR 296 1985 3 1988
  Kalkar KNK 2 Prot FNR 17 1978 13 1991
  Kahl VAK Exp BWR 15 1961 24 1985
  MZFR Exp PHWR 52 1966 18 1984
  Groswelzheim Prot BWR 25 1969 2 1971
  Lingen Prot BWR 183 1968 10 1979
  Niederaichbach Exp GCHWR 100 1973 1 1974
  Obrigheim * PWR 340 1968 36 2005
  Stade * PWR 640 1972 31 2003
  Wuergassen BWR 640 1972 22 1994
Italy Garigliano BWR 150 1964 18 1982
Japan Fugen Prot ATR 148 1978 24 2003
  Hamaoka 1 BWR 515 1974 26 2001
  Hamaoka 2 BWR 806 1978 25 2004
  JPDR Prot BWR 12 1963 13 1976
  Tokai 1 * GCR 137 1965 33 1998
Kazakhstan Aktau BN-350 Prot FNR 52 1973 27 1999
Netherlands Dodewaard * BWR 55 1968 28 1997
Russia Obninsk AM-1 Exp LWGR 6 1954 48 2002
  Beloyarsk 1 Prot LWGR 108 1964 19 1983
  Beloyarsk 2 Prot LWGR 160 1968 22 1990
  Melekess VK50 Prot BWR 50 1964 24 1988
  Novovoronezh 1 Prot VVER-440/V210 210 1964 23 1988
  Novovoronezh 2 Prot VVER-440/V365 336 1970 20 1990
 Spain Garona BWR 446 1971 42 2012
  Jose Cabrera * PWR 141 1968 38 2006
Sweden Agesta Prot HWR 10 1964 10 1974
UK Berkeley 1-2 * GCR 138 1962 26 1988-89
  Bradwell 1-2 * GCR 123 1962 39 2002
  Calder Hall 1-4 * GCR 50 1956-59 44-46 2003
  Chapelcross 1-4 * GCR 49 1959-60 44-45 2004
  Dungeness A 1-2 * GCR 225 1965 41 2006
  Hinkley Pt 1-2 * GCR 235 1965 35 2000
  Hunterston A 1-2* GCR 160 1964 25 1989-90
  Oldbury 1-2* GCR 217 1967 44 2011-12
  Sizewell A 1-2 * GCR 210 1966 41 2006
  Trawsfynydd 1-2 * GCR 196 1965 26 1993
  Wylfa 2* GCR 490 1971 41 2012
  Windscale Prot AGR 28 1963 18 1981
  Dounreay DFR Exp FNR 11 1962 18 1977
  Dounreay PFR Prot FNR 234 1975 19 1994
  Winfrith Prot SGHWR 92 1968 23 1990
USA Big Rock Point* BWR 67 1962 35 1997
  BONUS Exp BWR 17 1964 4 1968
  CVTR Exp PHWR 17 1963 4 1967
  Crystal River PWR 860 1977 35 2013
  Dresden 1 BWR 197 1960 18 1978
  Elk River BWR 22 1963 5 1968
  Enrico Fermi 1 Prot FNR 61 1966 6 1972
  Fort St. Vrain Prot HTR 330 1976 13 1989
  Haddam Neck* PWR 560 1967 29 1996
  Hallam Exp sodium cooled GR 75 1963 1 1964
  Humboldt Bay BWR 63 1963 13 1976
  Indian Point 1 PWR 257 1962 12 1974
  Kewaunee* PWR 566 1974 39 2013
  Lacrosse BWR 48 1968 19 1987
  Maine Yankee* PWR 860 1972 25 1997
  Millstone 1 BWR 641 1970 28 1998
  Pathfinder Prot BWR 59 1966 1 1967
  Peach Bottom 1 Exp HTR 40 1967 7 1974
  Piqua Exp Organic MR 12 1963 3 1966
  Rancho Seco 1 PWR 873 1974 15 1989
  San Onofre 1* PWR 436 1967 25 1992
  San Onofre 2* PWR 1070 1982 31 2013
  San Onofre 3* PWR 1070 1983 30 2013
  Saxton Exp PWR 3 1967 5 1972
  Shippingport Prot PWR 60 1957 25 1982
  Trojan PWR 1095 1975 17 1992
  Vallecitos Prot BWR 24 1957 6 1963
  Yankee NPS* PWR 167 1960 31 1991
  Zion 1-2 * PWR 1040 1973 25 1998
  Sturgis FNPP PWR 10 1967 9 1976

The last, Sturgis floating NPP, is the "+1" in top total

Main Sources & References:
''Nuclear Decommissioning", IMechE Conference transaction 1995 -7.
OECD/NEA 1992, Decommissioning Policies for Nuclear Facilities.
OECD/NEA 1992, International Co-operation on Decommissioning.
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