Thermal Hydraulic Analysis of in Vessel Loss of Coolant Accident and Loss of Flow Accident of First Wall Helium Cooling System of Generalized LLCB TBS in ITER Using Modified RELAP/SCDAPSIM MOD4.0 Code
India has proposed Lead Lithium cooled Ceramic Breeder (LLCB) Test Blanket Module (TBM) concept for testing in ITER. The First Wall of TBM (TBM FW) directly faces the plasma and is cooled by First Wall Helium Cooling System (FWHCS) it is considered as a critical component from ITER safety point of view. The scope of this work comprises of thermal hydraulic analysis of the Indian LLCB Test Blanket System (TBS) and the assessment of In Vacuum Vessel (VV) Loss of Coolant Accident (In Vessel LOCA) and Loss of Flow Accident (LOFA) in FWHCS on the ITER safety with the help of thermal hydraulic code RELAP/SCDAPSIM/MOD4.0.