Development of numerical estimation method for thermal hydraulics in reactor vessel of sodium-cooled fast reactor under decay heat removal operation; Validation practice with decay heat removal test

Tanaka, Masaaki  ; Miyake, Yasuhiro*; Hamase, Erina ; Ezure, Toshiki 

For safety enhancement of sodium-cooled fast reactor, decay heat removal system (DHRS) by using the natural circulation without depending on the pump as the mechanical equipment is recognized as one of the most effective methods. The numerical estimation method which can predict thermal hydraulic phenomena in the reactor vessel during DHRS operation is necessarily required. In this study, the numerical analysis of a sodium test for decay heat removal conducted at the scaled sodium experimental facility named PLANDTL-2 was implemented to validate the RV-CFD model.