[KSCI] Korea Science Citation Index Service

http://dx.doi.org/10.5516/NET.2007.39.4.237

FRENCH PROGRAM TOWARDS AN INNOVATIVE SODIUM COOLED FAST REACTOR

Martin, Ph. (CEA/Cadarache)
Anzieu, P. (CEA/Saclay, DEN/DDIN)
Rouault, J. (CEA/Saclay, DEN/DDIN)
Serpantie, J.P. (AREVA NP)
Verwaerde, D. (EDF R&D)

Publication Information

Nuclear Engineering and Technology / v.39, no.4, 2007 , pp. 237-248 More about this Journal

Abstract

Sodium-cooled fast reactor is considered in France as a potential candidate for a prototype of 4th generation system to be built by 2020. A detailed working program has been launched recently to identify by 2012 the potential improvement tracks for later industrial development of these reactors. The goals for innovation are first identified: Progress of the safety with a special attention to severe accidents risk minimization and mitigation (defense in depth approach); Economic competitiveness of the system mainly by reducing the capital cost, the investment risks by enhancing in service inspection and repair capacities, and raising the availability; Sustainability with fissile material management while reducing the proliferation risk; capacity for long-lived waste transmutation.

Keywords

Sodium Fast Reactors; Enhanced Safety Core; Severe Accidents; Energy Conversion; Inservice Inspection;

Citations & Related Records

Times Cited By Web Of Science : 2

Reference

1	L. BUIRON et al, 'Innovative core design for generation IV sodium-cooled fast reactors', Proc. of the ICAPP 2007 Conference, paper 7383
2	French Advisory Group on Safety, 'First deliberations on safety aspects of 4th generation reactors. Paths to improving safety Approach, tools and associated R&D', Proc. of the ICAPP 2007 Conference, paper 7168
3	Evaluation of material-coolant interaction and material movement and relocation in liquid metal fast reactors, IAEA Technical Committee Meeting, IWGFR-94, 09-06- 1994, O-Arai, Japan
4	RCC-MR AFCEN, Tour AREVA, F 92084 Paris la Défense CEDEX