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

[1G14] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(20)Numerical simulation of experiment on aerosol transport behavior in multi-cell facility connected with horizontal or vertical pipe

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

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

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 numerical simulation of experiment on aerosol transport behavior in multi-cell facility connected with horizontal or vertical pipe was performed as part of V&V for sodium fire analysis code.