2019 Fall Meeting

Presentation information

Oral presentation

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

[2G06-09] Severe Accident of Sodium-Cooled Fast Reactor 2

Thu. Sep 12, 2019 10:50 AM - 11:55 AM Room G (Common Education Bildg. 2F C22)

Chair:Daisuke Ito(Kyoto Univ.)

11:35 AM - 11:50 AM

[2G09] Studies on Relocation Behavior of Molten Core Materials in the Core Disruptive Accident of Sodium-cooled Fast Reactors

(7)Validation of Analysis Models for the Melt Discharge Experiments into a Shallow Water Pool

*Kai Igarashi1, Takaaki Sakai1, Shinya Kato2, Kenichi Matsuba2, Kenji Kamiyama2 (1. Tokai University , 2. JAEA)

Keywords:Fast Reactors, Core Disruptive Accident, Relocation Behavior Molten Core Materials, SIMMER

In order to make clear behavior of core melt materials during the core disruptive accident of sodium-cooled fast reactors, analysis was conducted for a simulation experiment in which low-melting-point alloy was dropped into a shallow water pool using the SIMMER code. The present study shows that the validation results for the melt behavior by comparing the analysis with experimental data.