[en] France has a long history of R and D, construction and operation of fast neutron reactors. However, with the shutdown of Superphenix reactor more than 10 years ago and of Phenix in 2009, it is important to demonstrate that fast neutron reactors are part of the energy solution for the future, and that they can meet Generation IV (GENIV) requirements. It is therefore important to present the main objectives of Generation IV reactors, to describe briefly different technologies that are studied in the framework of the Generation IV International Forum, and to recall the main features of sodium-cooled fast reactors. To reach the GENIV criteria, R and D is needed and main topics of French R and D on sodium fast reactors will be presented. Along with the R and D, plans for the prototype ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) have been prepared. As an industrial prototype, it is foreseen to be put into operation around 2020. In 2010, in a broader investment plan for the future, ASTRID was confirmed as one of the priorities and received an appropriate funding for the design phase. (author)

[en] ASTRID, an acronym for 'advanced sodium technology reactor for industrial demonstration', refers to a prototype for a fast-neutron reactor that, cooled with sodium, breeds sufficient power for industrial purposes. It will be the first reactor of this sort in the world to meet the standards for fourth-generation nuclear reactors. This ambitious project, under a French act passed in June 2006 on the sustainable management of nuclear material and wastes, is preparing our country's future in the energy field. ASTRID's design will have innovative features such as: -) a negative emptying coefficient for the core reactivity, -) heat exchangers based on sodium and nitrogen in order to avoid the presence of water, -) a big thermal inertia, -) the taking into account of the resistance to airplane falls in the design, and -) an enhanced resistance to proliferation risks. The ASTRID reactor is planned to enter into service by 2023. (A.C.)

[en] The Generation IV International Forum (GIF) is an initiative of the American Department of Energy (DOE) whose purpose is to create an international cooperation for proposing and studying a new generation of nuclear reactors. GIF's work began in 2000 and 6 types of reactors were rapidly proposed. This article gives an overview of the work done so far. The sodium-cooled fast reactor is the most advanced concept because there is a technological continuity from the first sodium reactors operating in the fifties. The use of a lead eutectic as heat transfer fluid is hampered by its corrosion power on metals. The molten salt reactor is a very innovative concept that requires a complex and adapting chemistry for the on-line reprocessing. High-temperature and Very-High-Temperature reactors (HTR an VHTR) require materials that can sustain high temperatures. The difficulty to design such materials has hindered the development of this concept. Gas-cooled fast reactors show difficulties to evacuate residual heat in case of accident. The supercritical water-cooled reactor concept wants to take advantage of the increased heat capacity of water in particular conditions. Technical issues like the resistance to high pressure or corrosion or safety issues have delayed this concept so far. (A.C.)

[en] In France, the ASTRID prototype is an industrial demonstrator of a sodium-cooled fast neutron reactor (SFR), fulfilling the criteria for Generation IV reactors. ASTRID will meet safety requirements as stringent as for third generation reactors, and it takes into account lessons from the Fukushima accident. The objectives are to reinforce the robustness of the safety demonstration for all safety functions. ASTRID will feature an innovative core with a negative sodium void coefficient, it will take advantage of the large thermal inertia of SFR for decay heat removal, and will provide for a design either eliminating the sodium-water reaction, or guaranteeing no consequences for safety in case such reaction would take place. (author)

[en] France has a long history of R and D, construction and operation of fast neutron reactors. However, with the shutdown of Superphenix reactor more than 10 years ago and of Phenix in 2009, we are now entering a phase where we must convince that fast neutrons reactors are part of the energy solution for the future, and that they can meet Generation IV requirements. To that purpose, French R and D on fast reactors has been organized for the last 4 years around two systems: sodium cooled fast reactor SFR, as the reference option, and gas cooled fast reactor GFR as long term option. This paper concentrates on SFR R and D and prototype. Along with the R and D, plans for the prototype ASTRID (as for Advanced Sodium Technological Reactor for Industrial Demonstration) have been prepared. As an industrial prototype, it is foreseen to be put into operation around 2020. End of 2009, in a broader investment plan for the future, ASTRID was identified as one of the priorities to receive governmental funding. The ASTRID prototype (as for Advanced Sodium Technological Reactor for Industrial Demonstration) is seen as an industrial prototype prior to the first-of-a-kind, meaning that extrapolability of the technical options and of the safety demonstration is of outmost importance. The reactor will also provide some irradiation capabilities especially in order to validate the expected properties for the new fuel (big pin and ODS clad) and the ability to burn minor actinides up to an industrial scale. The ASTRID program defined by CEA also includes the facility to manufacture the fuel for the reactor, of limited capacity from 5-10 tons heavy metal per year. The refurbishment of existing testing facilities and the construction of new tools is part of the program as well. ASTRID shall be coupled to the grid with an electrical power of about 600 MW. It shall integrate operational feedback of past and current reactors. It is seen as a full Generation IV prototype reactor. Its safety level shall be at least as good as current 3. generation reactors, with strong improvements on core and sodium-related issues. After a learning period, the reactor shall have a high load factor (e.g. 70 to 80%). The reactor shall provide capability for demonstration of transmutation of minor actinides, at larger scale than previously done in Phenix. And of course, the investment costs of the prototype shall be kept to the lowest possible, with technical options compatible with later deployment on a commercial facility. The schedule associated to the ASTRID prototype is very ambitious and will be adapted in the course of the project, following R and D results and political decisions. End of 2009, in a broader investment plan for the future, ASTRID was identified as one of the priorities to receive governmental funding. Although collaborations and partnerships are sought, most of the financing for the design studies is secured (650 M of Euros). (O.M.)

[en] ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) is an integrated technology demonstrator designed to demonstrate the operability of the innovative choices enabling fast neutron reactor technology to meet the Generation IV criteria. ASTRID is a sodium-cooled fast reactor with an electricity generating power of 600 MWe. In order to meet the generation IV goals, ASTRID will incorporate the following decisive innovations: -) an improved core with a very low, even negative void coefficient; -) the possible installation of additional safety devices in the core. For example, passive anti-reactivity insertion devices are explored; -) more core instrumentation; -) an energy conversion system with modular steam generators, to limit the effects of a possible sodium-water reaction, or sodium-nitrogen exchangers; -) considerable thermal inertia combined with natural convection to deal with decay heat; -)elimination of major sodium fires by bunkerization and/or inert atmosphere in the premises; -) to take into account off-site hazards (earthquake, airplane crash,...) right from the design stage; -) a complete rethink of the reactor architecture in order to limit the risk of proliferation. ASTRID will also include systems for reducing the length of refueling outages and increasing the burn-up and the duration of the cycle. In-service inspection, maintenance and repair are also taken into account right from the start of the project. The ASTRID prototype should be operational by about 2023. (A.C.)

[en] France has a long history of R and D, construction and operation of fast neutron reactors. However, with the shutdown of Superphenix reactor more than 10 years ago and of Phenix in 2009, we are now entering a phase where we must convince that fast neutrons reactors are part of the energy solution for the future, and that they can meet Generation IV requirements. To that purpose, French R and D on fast reactors has been organized for the last 4 years around two systems: sodium cooled fast reactor SFR, as the reference option, and gas cooled fast reactor GFR as long term option. This paper concentrates on SFR R and D and prototype

[en] The 4. generation reactors meet the demand for sustainability of nuclear power through the saving of the natural resources, the minimization of the volume of wastes, a high safety standard and a high reliability. In the framework of the GIF (Generation 4. International Forum) France has decided to study the sodium-cooled fast reactor. Fast reactors have the capacity to recycle plutonium efficiently and to burn actinides. The long history of reprocessing-recycling of spent fuels in France is an asset. A prototype reactor named ASTRID could be entered into operation in 2020. This article presents the research program on the sodium-cooled fast reactor, gives the status of the ASTRID project and present the scenario of the progressive implementation of 4. generation reactors in the French reactor fleet. (A.C.)

[en] The pre-conceptual design of the ASTRID project was launched in 2010 by CEA. The objectives of this first phase are to consider innovative options to improve the safety level with progress made in SFR-specific fields. A few examples of these innovations are: a core with an overall negative sodium void effect, specific features to prevent and mitigate severe accidents, power conversion system decreasing drastically the sodium-water reaction risk, improvements in In-Service Inspection and Repair, etc. ASTRID will also be designed to pursue the R and D on sodium fast reactors and demonstrate the feasibility of transmutation of minor actinides. The paper describes the current status of the project, the mains results obtained during the pre-conceptual design and address also the main R and D needs and results, focused on sodium technology. Main R and D tracks and dedicated technological platforms have been identified, particularly thanks to the European project ADRIANA, and some more recent up-dates are described in this paper. (authors)

[en] The French research program on sodium fast reactors (SFR) was launched in 2007 and 4 axis of development were defined. First axis: proposing the design of an efficient fast reactor core with an enhanced safety level and the possibility to burn minor actinides. Second axis, proposing a better resistance to major accidents and to external attacks. Third axis, optimizing the energy conversion system while reducing sodium risks. And fourth axis: optimizing the economic competitiveness of the nuclear plant. The Astrid project means the design and construction of the Astrid reactor (Advanced Sodium Technological Reactor for Industrial Demonstration). This project implies the upgrading of the Masurca reactor that will be used to validate the innovative options of the Astrid's core. A preliminary draft of Astrid will have to be proposed by the end of 2012. (A.C.)