Study on cooling process of decay heat removal systems in a reactor vessel of sodium-cooled fast reactor by scaled water experiments, 3; Temperature measurement in a reactor vessel simulating operation of reactor vessel auxiliary cooling system

Aizawa, Kosuke ; Tsuji, Mitsuyo ; Kobayashi, Jun ; Kurihara, Akikazu ; Nakane, Shigeru*; Ishida, Katsuji*

Thermal-hydraulic phenomena driven by natural circulation in a reactor vessel was investigated by using scaled model water experiments simulating a reactor vessel in order to enforce of safety and optimize design and operation of decay heat removal systems under normal operation and severe accident conditions. This paper shows temperature measurement results of natural convection flow field in reactor vessel simulating operation of reactor vessel auxiliary cooling system. In addition, it is shown that the affect of dispersal condition of molten fuel on temperature distribution in reactor vessel.