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Materials arising from EdF's decommissioning include: 500 tonnes of long-liver intermediate-level wastes, 18,000 tonnes of graphite, 41,000 tones of short-lived intermediate-level wastes and 105,000 tonnes of very low level wastes.
The Eurodif gaseous diffusion enrichment plant at Tricastin is expected to generate 110,000 tonnes of steel and 20,000 tonnes of aluminium that could be recycled for use in ANDRA’s disposal centres or elsewhere in the industry.
Organisation and financing of final decommissioning of the UP1 reprocessing plant at Marcoule was settled in 2004, with the Atomic Energy Commission (CEA) taking it over. The total cost is expected to be some EUR 5.6 billion. The plant was closed in 1997 after 39 years of operation, primarily for military purposes but also taking the spent fuel from EdF's early gas-cooled power reactors. It was operated under a partnership - Codem, with 45% share by each of CEA and EdF and 10% share by Cogema (now Areva NC). EdF and Areva will now pay CEA EUR 1.5 billion and be clear of further liability.
EdF puts aside EUR 0.14 cents/kWh for decommissioning and at the end of 2004 it carried provisions of EUR 9.9 billion for this. By 2010 it will have fully funded the eventual decommissioning of its nuclear power plants (from 2035). Early in 2006 it held EUR 25 billion segregated for this purpose, and is on track for EUR 35 billion in 2010. Areva has dedicated assets already provided at the level of its future liabilities.
In April 2008 ASN issued a draft policy on decommissioning which proposes that French nuclear installation licensees adopt "immediate dismantling strategies" rather than safe storage followed by much later dismantling. The policy foresees broad public information in connection with the decommissioning process.
In 2006 the new Nuclear Safety Authority (Autorite de Surete Nucleaire - ASN) ) - an independent body with five commissioners - became the regulatory authority responsible for nuclear safety and radiological protection, taking over these functions from the DGSNR, and reporting to the Ministers of Environment, Industry & Health. However, its major licensing decisions will still need government approval.
Research is undertaken by the IRSN - the Institute for Radiological Protection & Nuclear Safety, also set up in 2002 from two older bodies. IRSN is the main technical support body for ASN and also advises DGSNR.
There have been two INES Level 4 accidents at French nuclear plants, both involving the St Laurent A gas-cooled graphite reactors. In October 1969, soon after commissioning, about 50 kg of fuel melted in unit 1, and in March 1980 some annealing occurred in the graphite of unit 2, causing a brief heat excursion. On each occasion the reactor was repaired, and the two were eventually taken out of service in 1990 and 1992.
The Atomic Energy Commission (Commissariat a l'Energie Atomique - CEA) was set up in 1945 and is the public R&D corporation responsible for all aspects of nuclear policy, including R&D. In 2009 it was re-named Commission of Atomic Energy and Alternative Energy (CEA).
The CEA has 14 research reactors of various types and sizes in operation, all started up 1959 to 1980, the largest of these being 70 MWt. About 17 units dating from 1948 to 1982 are shut down or decommissioning.
In 2004 the US energy secretary signed an agreement with the French Atomic Energy Commission (CEA) to gain access to the Phenix experimental fast neutron reactor for research on nuclear fuels. The US Department of Energy acknowledged that this fast neutron "capability no longer exists in the USA". The US research with Phenix irradiated fuel loaded with various actinides under constant conditions to help identify what kind of fuel might be best for possible future waste transmutation systems.
In mid 2006 the CEA signed a four-year EUR 3.8 billion R&D contract with the government, including development of two types of fast neutron reactors which are essentially Generation IV designs: an improved version of the sodium-cooled type which already has 45 reactor-years operational experience in France, and an innovative gas-cooled type. Both would have fuel recycling, and by mid 2012 a decision is due to be taken on whether and how to transmute minor actinides. The CEA is seeking support under the EC's European Sustainable Nuclear Industrial Initiative and partnerships with Japan and China to develop the sodium-cooled model. However, it notes that China (like India) is aiming for high breeding ratios to produce enough plutonium to crank up a major push into fast reactors.
The National Scientific Evaluation Committee (CNE) in mid 2009 said that the sodium-cooled model, Astrid (Advanced Sodium Technological Reactor for Industrial Demonstration), should be a high priority in R&D on account of its actinide-burning potential. It is envisaged as a 600 MWe prototype of a commercial series which is likely to be deployed from about 2050. It will have high fuel burnup, including minor actinides in the fuel elements, and use an
| Reactor | Type | MWe | operational |
|---|---|---|---|
| Chooz A | PWR | 300 | 1967-91 |
| Brennilis | GCHWR | 70 | 1967-85 |
| Marcoule G1 | GCR | 2 | 1956-68 |
| Marcoule G2 | GCR | 40 | 1959-80 |
| Marcoule G3 | GCR | 40 | 1960-84 |
| Chinon A1 | GCR | 70 | 1963-73 |
| Chinon A2 | GCR | 200 | 1965-85 |
| Chinon A3 | GCR | 480 | 1966-90 |
| Saint-Laurent A1 | GCR | 480 | 1969-90 |
| Saint-Laurent A2 | GCR | 515 | 1971-92 |
| Bugey 1 | GCR | 540 | 1972-94 |
| Creys-Malville | FNR | 1240 | 1986-97 |
| Phenix | FNR | 233 | 1973-2009 |
Materials arising from EdF's decommissioning include: 500 tonnes of long-liver intermediate-level wastes, 18,000 tonnes of graphite, 41,000 tones of short-lived intermediate-level wastes and 105,000 tonnes of very low level wastes.
The Eurodif gaseous diffusion enrichment plant at Tricastin is expected to generate 110,000 tonnes of steel and 20,000 tonnes of aluminium that could be recycled for use in ANDRA’s disposal centres or elsewhere in the industry.
Organisation and financing of final decommissioning of the UP1 reprocessing plant at Marcoule was settled in 2004, with the Atomic Energy Commission (CEA) taking it over. The total cost is expected to be some EUR 5.6 billion. The plant was closed in 1997 after 39 years of operation, primarily for military purposes but also taking the spent fuel from EdF's early gas-cooled power reactors. It was operated under a partnership - Codem, with 45% share by each of CEA and EdF and 10% share by Cogema (now Areva NC). EdF and Areva will now pay CEA EUR 1.5 billion and be clear of further liability.
EdF puts aside EUR 0.14 cents/kWh for decommissioning and at the end of 2004 it carried provisions of EUR 9.9 billion for this. By 2010 it will have fully funded the eventual decommissioning of its nuclear power plants (from 2035). Early in 2006 it held EUR 25 billion segregated for this purpose, and is on track for EUR 35 billion in 2010. Areva has dedicated assets already provided at the level of its future liabilities.
In April 2008 ASN issued a draft policy on decommissioning which proposes that French nuclear installation licensees adopt "immediate dismantling strategies" rather than safe storage followed by much later dismantling. The policy foresees broad public information in connection with the decommissioning process.
Regulation & Safety
The General Directorate for Nuclear Safety and Radiological Protection (DGSNR) was set up in 2002 by merging the Directorate for Nuclear Installation Safety (DSIN) with the Office for Protection against Ionising Radiation (OPRI) to integrate the regulatory functions and to "draft and implement government policy."In 2006 the new Nuclear Safety Authority (Autorite de Surete Nucleaire - ASN) ) - an independent body with five commissioners - became the regulatory authority responsible for nuclear safety and radiological protection, taking over these functions from the DGSNR, and reporting to the Ministers of Environment, Industry & Health. However, its major licensing decisions will still need government approval.
Research is undertaken by the IRSN - the Institute for Radiological Protection & Nuclear Safety, also set up in 2002 from two older bodies. IRSN is the main technical support body for ASN and also advises DGSNR.
There have been two INES Level 4 accidents at French nuclear plants, both involving the St Laurent A gas-cooled graphite reactors. In October 1969, soon after commissioning, about 50 kg of fuel melted in unit 1, and in March 1980 some annealing occurred in the graphite of unit 2, causing a brief heat excursion. On each occasion the reactor was repaired, and the two were eventually taken out of service in 1990 and 1992.
The Atomic Energy Commission (Commissariat a l'Energie Atomique - CEA) was set up in 1945 and is the public R&D corporation responsible for all aspects of nuclear policy, including R&D. In 2009 it was re-named Commission of Atomic Energy and Alternative Energy (CEA).
The CEA has 14 research reactors of various types and sizes in operation, all started up 1959 to 1980, the largest of these being 70 MWt. About 17 units dating from 1948 to 1982 are shut down or decommissioning.
In 2004 the US energy secretary signed an agreement with the French Atomic Energy Commission (CEA) to gain access to the Phenix experimental fast neutron reactor for research on nuclear fuels. The US Department of Energy acknowledged that this fast neutron "capability no longer exists in the USA". The US research with Phenix irradiated fuel loaded with various actinides under constant conditions to help identify what kind of fuel might be best for possible future waste transmutation systems.
In mid 2006 the CEA signed a four-year EUR 3.8 billion R&D contract with the government, including development of two types of fast neutron reactors which are essentially Generation IV designs: an improved version of the sodium-cooled type which already has 45 reactor-years operational experience in France, and an innovative gas-cooled type. Both would have fuel recycling, and by mid 2012 a decision is due to be taken on whether and how to transmute minor actinides. The CEA is seeking support under the EC's European Sustainable Nuclear Industrial Initiative and partnerships with Japan and China to develop the sodium-cooled model. However, it notes that China (like India) is aiming for high breeding ratios to produce enough plutonium to crank up a major push into fast reactors.
The National Scientific Evaluation Committee (CNE) in mid 2009 said that the sodium-cooled model, Astrid (Advanced Sodium Technological Reactor for Industrial Demonstration), should be a high priority in R&D on account of its actinide-burning potential. It is envisaged as a 600 MWe prototype of a commercial series which is likely to be deployed from about 2050. It will have high fuel burnup, including minor actinides in the fuel elements, and use an
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