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RRFM 2009 Transactions - European Nuclear Society

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Owing to the important and satisfactory feedback experience built upon oxide fuels, MOX is<br />

the reference fuel for the SFR, at least for the start-up of the prototype (ASTRID). The<br />

objectives followed for the 4th generation SFR for safety (for example sodium void worth<br />

reduction and limited core reactivity excess) and cycle performances (self-sustainable core<br />

with a near zero breeding gain, reasonable in-core Pu inventory, MA transmutation) are<br />

achievable with an oxide fuel in large power cores (3600 MWt) while implementing adequate<br />

design features. Nevertheless, recent calculations show that the use of a dense and cold<br />

ceramic fuel might even improve the core performances. Carbide and nitride are candidate<br />

fuels to be investigated for SFRs of 4 th generation. Based on recent experimental results<br />

carbide is preferred to nitride by the CEA.<br />

For the GFR and the LFR, dense fuels are required to achieve self-generation because of<br />

the higher fraction of coolant in the core. Carbide and nitride are currently the reference fuels<br />

for the GFR and LFR, respectively.<br />

Experimental reactors are needed for further assessment of the in-pile behavior of fuels with<br />

representative materials and realistic conditions (burn-up, MA content, neutron flux…). An<br />

optimal use of existing irradiation reactors (Phenix, Joyo, Monju, BOR-60, BN-600) is<br />

necessary, until new reactors, under construction (JHR, CEFR, PFBR) or planned<br />

(ALLEGRO, ASTRID) can be put in operation. International collaboration is essential to<br />

assure the continuous availability of irradiation infrastructures.<br />

7. References<br />

[1] F. Carré et al, Outlook To France’s R&D Strategy On Future <strong>Nuclear</strong> Systems (From<br />

Gen II to Gen IV reactors and fuel cycle), <strong>RRFM</strong> IGORR 2007, Lyon, France, March<br />

11-14, 2007.<br />

[2] F. Carré, C. Renault et al, Les réacteurs rapides de 4 ème generation et leurs<br />

combustibles, RGN, 2006.<br />

[3] J.Y Malo et al, Gas Cooled Fast Reactor 2400 MWth, end of the preliminary viability<br />

phase, Proceedings of ICAPP 2008, Anaheim, CA USA, June 8-12, 2008.<br />

[4] P. Richard et al, GFR Fuel and Core Pre-Conceptual Design Studies, International<br />

Conference on the Physics of Reactors “<strong>Nuclear</strong> Power: A Sustainable Resource”,<br />

PHYSOR 2008, Interlaken, Switzerland, September 14-19, 2008<br />

[5] J. Rouault et al, Survey of candidate fuels for Gen IV Sodium Fast Reactors with a<br />

closed fuel cycle, Presentation at ICAPP 2007, Nice, France, May 13-18, 2007.<br />

[6] D. Petti, D. Crawford and N. Chauvin, Fuels for Advanced <strong>Nuclear</strong> Energy Systems,<br />

MRS Bulletin Vol 34, January <strong>2009</strong>.<br />

[7] F. Varaine et al, Review on transmutation studies at CEA: scientific feasibility<br />

according neutronic spectrum, Proceedings of GLOBAL 2005, Tsukuba, Japan,<br />

October 9-13, 2005.<br />

[8] J. Guidez, Status of Phenix Operation and of Sodium Fast Reactors in the World,<br />

Proceedings of ICAPP 2007, Nice, France, May 13-18, 2007.<br />

63 of 455<br />

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