抄録
When cooling tubes installed in plasma-facing components (PFCs) of a fusion reactor are damaged by some accidents, water may be discharged into a plasma chamber (PC) and vacuum vessel (VV) of the fusion reactor. In such a case, the discharged water will impinge on a surface of PFCs at high temperature and evaporate and then the VV may be broken due to pressurization by steam. This event is called an ingress-of-coolant event (ICE). The water-vapor two-phase flow behavior in the PC and VV during the ICE was investigated using an integrated ICE test facility. Furthermore, the condensation effect due to vapor inside a suppression tank which is installed to reduce the pressurization by the ICE was observed visually. In addition, the thermal-hydraulics during the ICE were validated numerically by the TRAC-PF1 code and analytical results on the pressure rise were in good agreement with the experimental results.
