[1G12-15] Thermal Hydraulics of Sodium-Cooled Fast Reactors 2

[1G13] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(19)Experimental study on aerosol transport behavior in multi-cell facility connected with horizontal or vertical pipe

*Ryota Umeda¹, Norihiro Kikuchi¹, Akikazu Kurihara¹, Shin Kikuchi¹, Takashi Takata¹, Hiroyuki Ohshima¹ (1. JAEA)

Keywords:Sodium-cooled Fast Reactor, Sodium leak, Aerosol transport behavior

Multi-level, multi-scenario simulation systems as safety fundamental technology for sodium-cooled fast reactors (SFRs) has been developed. In this report, in order to understand the aerosol transport behavior in case of sodium fire, the experiment using multi-cell facility connected with horizontal or vertical pipe was performed as part of V&V for sodium fire analysis code.