[1O09-12] SFR 3

[1O11] Studies on relocation behavior of molten core materials in core disruptive accidents of sodium-cooled fast reactors

(11) Coolability of molten fuel discharged into a depth- and volume-limited sodium plenum

*Ken-ichi Matsuba¹, Shinya Kato¹, Kenji Kamiyama¹, Assan Akayev², Viktor Baklanov² (1. JAEA, 2. NNC)

Keywords:Sodium-cooled fast reactor, Core disruptive accident, Molten core material, Material relocation, Coolability

Japan Atomic Energy Agency and National Nuclear Center of Kazakhstan discussed the coolability of molten fuel discharged into a depth- and volume-limited sodium plenum, based on results of a series of out-of-pile experiments using simulated molten fuel (molten alumina).