Abstract :
Korea has designed a helium cooled ceramic reflector (HCCR) based test blanket system (TBS) for an ITER. An in-vessel loss of coolant accident is one eight selected reference accidents in the Korean TBS. This accident is initiated by a single or multiple rupture of the test blanket module first wall cooling channels, causing a plasma disruption, and pressurization of the vacuum vessel (VV). In this type of accident, the governing parameters are various, for example, the operating pressure, gas temperature, TBS volume, VV volume, and mass flow rate. Thus, a scoping study is an essential strategy when attempting to determine the proper design specification for a Korean TBS. In this paper, given the preliminary accident analysis results for the current HCCR TBS, a parametric study was performed. For this transient simulation, the Korean nuclear fusion reactor safety analysis code (GAMMA-FR) was used.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor safety; plasma boundary layers; plasma toroidal confinement; ITER; Korean TBS in-vessel LOCA; Korean nuclear fusion reactor safety analysis code; TBS volume; VV volume; coolant accident; design specification; first wall cooling channels; gas temperature; helium cooled ceramic reflector; mass flow rate; plasma disruption; test blanket module; test blanket system; transient simulation; vacuum vessel pressurization; Accidents; Cooling; Heating; Helium; Plasma temperature; Safety; ITER; In-vessel loss of coolant accident (LOCA); safety analysis; scoping study; test blanket system (TBS);
