[1D08-13] Thermal Hydraulics of Sodium-Cooled Fast Reactors 2

[1D11] Study on reactor vessel coolability of sodium-cooled fast reactor under severe accident condition

(3)Design study of large scale sodium test facility AtheNa-RV

＊Kunihiko NABESHIMA¹, Norihiro DODA¹, Nobuyuki ISHIKAWA¹, Katsunori AMANO¹, Hiroyuki OHSHIMA¹ (1.JAEA)

Keywords:sodium-cooled fast reactor, decay heat removal system, natural circulation, core thermal hydraulic, sodium test

AtheNa-SA project in JAEA is planned to evaluate the availability of cooling system in the reactor vessel under the severe accident of loop-type or pool-type sodium-cooled fast reactor. This report describes the design study of large scale sodium test facility AtheNa-RV, which could simulate natural circulation decay heat removal system in normal or damaged core.