Sensitivity study on in-vessel LOCA of a Korean TBS in ITER

Korea has designed a Helium Cooled Ceramic Reflector (HCCR) based Test Blanket System (TBS) for ITER. Among eight selected reference accidents in Korean TBS, in-vessel LOCA is one of them. This accident is initiated by single or multiple rupture of Test Blanket Module (TBM) first wall (FW) cooling channels, causing a plasma disruption and pressurization of vacuum vessel (VV). In this type of accident governing parameters are various, for example operating pressure, gas temperature, TBS volume, VV volume and mass flow rate. Thus, sensitivity study is an essential strategy when attempting to determine proper design specification for Korean TBS. In this paper, given preliminary accident analysis results for the current HCCR TBS, parametric study was performed. For this transient simulation, Korean nuclear fusion reactor safety analysis code (GAMMA-FR) was used.