2021 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[2F09-12] Safety Analysis

Thu. Mar 18, 2021 2:45 PM - 4:00 PM Room F (Zoom room 6)

Chair: Yoshiro Nishioka (Toshiba ESS)

3:00 PM - 3:15 PM

[2F10] Study on discharge behavior of molten core materials in core on core disruptive accidents of sodium cooled fast reactors

Consideration on discharge behavior through a sodium-filled channel with an internal structure

*Shinya Kato1, Kenichi Matsuba1, Kenji Kamiyama1, Anatoly Mikisha2, Assan Akayev2, Alexandr Vurim2, Viktor Baklanov2 (1. JAEA, 2. NNC)

Keywords:Sodium cooled fast reactor, Core disruptive accident, Molten core material, relocation phase, Discharge behavior

In order to enrich experimental knowledge of discharge behavior of molten core materials through a sodium-filled channel in core disruptive accidents of sodium cooled fast reactors, an out-of-pile experiment was conducted, in which molten alumina was used as a molten-fuel simulant and it penetrated into a sodium-filled channel with an internal structure reducing a flow area. In this presentation, consideration on effects of the internal structure on melt discharge-behavior will be presented based on experimental results.