Journal
COMPTES RENDUS PHYSIQUE
Volume 13, Issue 4, Pages 365-371Publisher
ELSEVIER FRANCE-EDITIONS SCIENTIFIQUES MEDICALES ELSEVIER
DOI: 10.1016/j.crhy.2012.03.004
Keywords
ASTRID; Sodium; SFR; Fukushima; Safety; Prototype
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In France, the ASTRID prototype is a sodium-cooled fast neutron industrial demonstrator, fulfilling the criteria for Generation IV reactors. ASTRID will meet safety requirements as stringent as for 3rd generation reactors, and take 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, take advantage of the large thermal inertia of SFRs for decay heat removal, and provide for a design either eliminating the sodium-water reaction, or guaranteeing no consequences for safety in case such reaction would take place. (C) 2012 Published by Elsevier Masson SAS on behalf of Academie des sciences.
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