[2F05-09] Fast Reactor Thermal Hydraulics 1

[2F08] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(13)Experimental study on aerosol transport behavior using the multi-cell facility

*Ryota Umeda¹, Akikazu Kurihara¹, Shin Kikuchi¹, Norihiro Kikuchi¹, Takata Takashi¹, Ohshima Hiroyuki¹ (1. JAEA)

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

Multi-level,multi-scenario simulation systems have been developed as safety fundamental technology for sodium-cooled fast reactors. In this report, as part of the verification and validation of the sodium fire analysis codes, in order to grasp the transport behavior of combustion generated aerosol during of sodium leak, the resluts of the transport behavior experiment using simulanted particles is presented.