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Experimental study on fragmentation behavior of molten core material during core disruptive accident for sodium-cooled fast reactors; Results of fragmentation test for molten oxide penetrating into a sodium pool

Matsuba, Kenichi  ; Kamiyama, Kenji ; Konishi, Kensuke* ; Toyoka, Junichi  ; Sato, Ikken ; Zuev, V.*; Kolodeshnikov, A.*; Yury, V.*

In-vessel retention of molten core fuel with the use of debris trays in a reactor lower plenum is being studied as a mitigation measure against core disruptive accident for sodium-cooled fast reactors. If the molten core fuel is finely fragmented before coming at the debris trays, fuel coolability on the debris trays can be enhanced. In the present study, the length for molten jet break-up due to fragmentation was measured with out-of-pile experiments in which about 10 kg of molten alumina was injected into a sodium pool.

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