French SFR R and D Program and Design Activities for SFR Prototype ASTRID
Description
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.)
Availability note (English)
Available from doi: http://dx.doi.org/10.1016/j.egypro.2011.06.040Additional details
Identifiers
Publishing Information
- Journal Title
- Energy Procedia (Online)
- Journal Volume
- 7
- Journal Page Range
- p. 314-316
- ISSN
- 1876-6102
Conference
- Title
- 2. International Conference on Asian Nuclear Prospects
- Acronym
- ANUP 2010
- Dates
- 10-13 Oct 2010
- Place
- Mamallapuram (India)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- France
- INIS RN
- 44000918
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; ACTINIDES; COMPUTERIZED SIMULATION; DESIGN; ENERGY CONVERSION; FAST NEUTRONS; FINANCING; FRANCE; IN-SERVICE INSPECTION; PHENIX REACTOR; RADIATION PROTECTION; RESEARCH PROGRAMS; S CODES; TRANSMUTATION
- Descriptors DEC
- BARYONS; BREEDER REACTORS; COMPUTER CODES; CONVERSION; DEVELOPED COUNTRIES; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EUROPE; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; HADRONS; INSPECTION; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; METALS; NEUTRONS; NUCLEONS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; SODIUM COOLED REACTORS; WESTERN EUROPE