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FNRs. Astrid is called a "self-generating" fast reactor rather than a breeder in order to demonstrate low net plutonium production. Astrid is designed to meet the stringent criteria of the Generation IV International Forum in terms of safety, economy and proliferation resistance. CEA plans to build it at Marcoule.
In September 2010 the government confirmed its support, and EUR 651.6 million funding to 2017, for a 600 MWe Astrid prototype with final decision on construction to be made in 2017. The CEA is responsible for the project and will design the reactor core and fuel, but will collaborate with Areva, which will design the nuclear steam supply system, the nuclear auxiliaries and the instrumentation and control system. According to a February 2010 study by Deloitte for the EU's Strategic Nuclear Energy Technology Platform, a 600 MWe sodium-cooled fast reactor would cost EUR 4.286 billion, with most of the financing coming from European institution loans, EU incentives and grants such as the EC's European Sustainable Nuclear Industrial Initiative, plus EUR 839 million from private investors.
The Astrid program includes development of the reactor itself and associated fuel cycle facilities: a dedicated MOX fuel fabrication line (possibly in Japan) and a pilot reprocessing plant for used Astrid fuel. The program also includes a workshop for fabricating fuel rods containing actinides for transmutation, called Alfa, scheduled to operate in 2023, though fuel containing minor actinides would not be loaded for transmutation in Astrid before 2025. A major tripartite France-US-Japan accord on developing fast reactors was signed in October 2010.
CNE is a high-level scientists’ panel set up under the 1991 nuclear waste management act and charged with reviewing the research and development programs of the organizations responsible for nuclear energy, research and waste. The CNE expressed a clear preference for the concept of heterogeneous recycling of minor actinides, called CCAM. In that process, minor actinides are separated out from used fuel in an advanced-technology reprocessing plant and then incorporated into blanket assemblies which are placed around the core of a future fast reactor. Such blanket assemblies could contain 20% minor actinides or more, dispersed in a uranium oxide matrix. (In homogeneous recycling, the actinides are incorporated into the actual fuel.)
The second line of FNR development is the gas-cooled fast reactor. A 50-80 MWt experimental version – Allegro – is envisaged to be built 2014-2020. This will have either a ceramic core with 850°C outlet temperature, or a MOX core at 560°C. The secondary circuit will be pressurized water. The CEA has encouraged Czech Republic, Hungary and Slovakia to host the demonstration project. Further detail in Fast Neutron Reactors paper.
In June 2010 the CEA signed a major framework agreement with Rosatom covering "nuclear energy development strategy, nuclear fuel cycle, development of next-generation reactors, future gas coolant reactor systems, radiation safety and nuclear material safety, prevention and emergency measures." Much of the collaboration will be focused on reprocessing and wastes, also sodium-cooled fast reactors. Subsequently EdF signed a further cooperation agreement covering R&D, nuclear fuel, and nuclear power plants - both existing and under construction.
In December 2009, as part of a €35 billion program to improve France's competitiveness, the government awarded €1 billion to the CEA for Generation IV nuclear reactor and fuel cycle development. CEA has two priorities in this area:
- fast neutron reactors with sodium or gas cooling and a closed fuel cycle, and
- in collaboration with industry partners, a very high temperature 600 MWt reactor for electricity around 2025 and long-term for process heat applications such as hydrogen production. Areva is developing Antares, the French version of General Atomics' GT-MHR – a high-temperature gas-cooled reactor with fuel in prismatic blocks. It says that it "is using the Antares program to make VHTR a pivotal aspect of its new product development."
In March 2007 the CEA started construction of a 100 MWt materials test reactor at Cadarache. The Jules Horowitz reactor is the first such unit to be built for several decades, and has been identified by the EU as a key infrastructure facility to support nuclear power development, as well as producing radioisotopes and irradiating silicon for high-performance electronic use. The €500 million cost is being financed by a consortium including CEA (50%), EdF (20%), Areva (10%) and EU research institutes (20%). Since the anticipated planned high-density U-Mo fuel will not be ready in time for 2013, it will start up on uranium silicide fuel enriched to 27%.
Also at Cadarache, Areva TA with DCNS is building a test version of its Réacteur d’essais à terre (RES), a land-based equivalent of its K15 naval reactor of 150 MW, running on low-enriched fuel. It has also designed the NP-300 reactor based on these, able to be built in sizes up to about 300 MWe.
In January 2011 DCNS announced the Flexblue submerged nuclear power plant concept, developed in collaboration with Areva, EdF and CEA. A 50 to 250 MWe nuclear power system (reactor, steam generators and turbine-generator) would be housed in a submerged 12,000 tonne cylinder about 100 metres long and 12-15 metres diameter, offshore at about 60-100 m depth. DCNS is a state-owned naval defence group formed in 2007 from the merger of DCN shipyard and Thales SA, and makes nuclear submarines and surface ships. It has built 18 nuclear reactors for the French navy and is building the RES test reactor and some components for EPR reactors. Subject to market evaluation, DCNS could start building a prototype Flexblue unit in 2013 in its shipyard at Cherbourg for launch and deployment in 2016. The concept eliminates the need for civil engineering, and refueling or major service can be undertaken by refloating it and returning to the shipyard.
In relation to introduction of Generation IV reactors by 2040, the CEA is investigating several fuel cycle strategies:
FNRs. Astrid is called a "self-generating" fast reactor rather than a breeder in order to demonstrate low net plutonium production. Astrid is designed to meet the stringent criteria of the Generation IV International Forum in terms of safety, economy and proliferation resistance. CEA plans to build it at Marcoule.
In September 2010 the government confirmed its support, and EUR 651.6 million funding to 2017, for a 600 MWe Astrid prototype with final decision on construction to be made in 2017. The CEA is responsible for the project and will design the reactor core and fuel, but will collaborate with Areva, which will design the nuclear steam supply system, the nuclear auxiliaries and the instrumentation and control system. According to a February 2010 study by Deloitte for the EU's Strategic Nuclear Energy Technology Platform, a 600 MWe sodium-cooled fast reactor would cost EUR 4.286 billion, with most of the financing coming from European institution loans, EU incentives and grants such as the EC's European Sustainable Nuclear Industrial Initiative, plus EUR 839 million from private investors.
The Astrid program includes development of the reactor itself and associated fuel cycle facilities: a dedicated MOX fuel fabrication line (possibly in Japan) and a pilot reprocessing plant for used Astrid fuel. The program also includes a workshop for fabricating fuel rods containing actinides for transmutation, called Alfa, scheduled to operate in 2023, though fuel containing minor actinides would not be loaded for transmutation in Astrid before 2025. A major tripartite France-US-Japan accord on developing fast reactors was signed in October 2010.
CNE is a high-level scientists’ panel set up under the 1991 nuclear waste management act and charged with reviewing the research and development programs of the organizations responsible for nuclear energy, research and waste. The CNE expressed a clear preference for the concept of heterogeneous recycling of minor actinides, called CCAM. In that process, minor actinides are separated out from used fuel in an advanced-technology reprocessing plant and then incorporated into blanket assemblies which are placed around the core of a future fast reactor. Such blanket assemblies could contain 20% minor actinides or more, dispersed in a uranium oxide matrix. (In homogeneous recycling, the actinides are incorporated into the actual fuel.)
The second line of FNR development is the gas-cooled fast reactor. A 50-80 MWt experimental version – Allegro – is envisaged to be built 2014-2020. This will have either a ceramic core with 850°C outlet temperature, or a MOX core at 560°C. The secondary circuit will be pressurized water. The CEA has encouraged Czech Republic, Hungary and Slovakia to host the demonstration project. Further detail in Fast Neutron Reactors paper.
In June 2010 the CEA signed a major framework agreement with Rosatom covering "nuclear energy development strategy, nuclear fuel cycle, development of next-generation reactors, future gas coolant reactor systems, radiation safety and nuclear material safety, prevention and emergency measures." Much of the collaboration will be focused on reprocessing and wastes, also sodium-cooled fast reactors. Subsequently EdF signed a further cooperation agreement covering R&D, nuclear fuel, and nuclear power plants - both existing and under construction.
In December 2009, as part of a €35 billion program to improve France's competitiveness, the government awarded €1 billion to the CEA for Generation IV nuclear reactor and fuel cycle development. CEA has two priorities in this area:
- fast neutron reactors with sodium or gas cooling and a closed fuel cycle, and
- in collaboration with industry partners, a very high temperature 600 MWt reactor for electricity around 2025 and long-term for process heat applications such as hydrogen production. Areva is developing Antares, the French version of General Atomics' GT-MHR – a high-temperature gas-cooled reactor with fuel in prismatic blocks. It says that it "is using the Antares program to make VHTR a pivotal aspect of its new product development."
In March 2007 the CEA started construction of a 100 MWt materials test reactor at Cadarache. The Jules Horowitz reactor is the first such unit to be built for several decades, and has been identified by the EU as a key infrastructure facility to support nuclear power development, as well as producing radioisotopes and irradiating silicon for high-performance electronic use. The €500 million cost is being financed by a consortium including CEA (50%), EdF (20%), Areva (10%) and EU research institutes (20%). Since the anticipated planned high-density U-Mo fuel will not be ready in time for 2013, it will start up on uranium silicide fuel enriched to 27%.
Also at Cadarache, Areva TA with DCNS is building a test version of its Réacteur d’essais à terre (RES), a land-based equivalent of its K15 naval reactor of 150 MW, running on low-enriched fuel. It has also designed the NP-300 reactor based on these, able to be built in sizes up to about 300 MWe.
In January 2011 DCNS announced the Flexblue submerged nuclear power plant concept, developed in collaboration with Areva, EdF and CEA. A 50 to 250 MWe nuclear power system (reactor, steam generators and turbine-generator) would be housed in a submerged 12,000 tonne cylinder about 100 metres long and 12-15 metres diameter, offshore at about 60-100 m depth. DCNS is a state-owned naval defence group formed in 2007 from the merger of DCN shipyard and Thales SA, and makes nuclear submarines and surface ships. It has built 18 nuclear reactors for the French navy and is building the RES test reactor and some components for EPR reactors. Subject to market evaluation, DCNS could start building a prototype Flexblue unit in 2013 in its shipyard at Cherbourg for launch and deployment in 2016. The concept eliminates the need for civil engineering, and refueling or major service can be undertaken by refloating it and returning to the shipyard.
In relation to introduction of Generation IV reactors by 2040, the CEA is investigating several fuel cycle strategies:
- Optimising uranium and plutonium recycling from present and EPR reactors, then co-management of U&Pu and possibly Np in Gen IV fast reactors.
- Recycling these with a low proportion of minor actinides (eg 3% MA) in driver fuels of Gen IV fast reactors.
- Recycling (in about one third of France's reactors) with up to 30% of minor actinides in MOX blanket assemblies of Gen IV fast reactors.
Non-proliferation
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