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We simulate ion loss induced by neutral beam injection (NBI) in three-dimensional (3D) space with high fidelity on the plasma-facing components (PFCs) of the Korea Superconducting Tokamak Advanced Research (KSTAR) device. Utilizing a 3D collision detection routine added to the NuBDeC code and computer-aided design data reflecting the recent upgrade to a tungsten divertor, we have characterized 3D heat flux distribution and patterns over PFCs due to the NB ion loss throughout parameter scans. First, we identify axial asymmetry in the heat flux distribution. The plasma-wetted areas extend along the direction of the plasma current and deviate diagonally in the direction of the NB ion's poloidal turn. Additionally, on the PFC surfaces, local heat flux peaks are observed along both poloidal and toroidal directions. These local peaks emerge on the surfaces of the PFCs that protrude toward the regions swept by the NB ions. Second, through a case study of NB1-C (beam source C of neutral beam 1) that results in the most loss, we analyze several changes in the heat flux patterns observed on the divertor and the poloidal limiter. Such analysis allows us to examine how variations in the parameters affect the movement of the peak heat flux position and the extent of the plasma-wetted area, if formed. We observe that the ion loss increases under several conditions: shallower beam deposition, higher beam energy, larger poloidal beta, and lower plasma current. Ions born near the plasma edge due to shallow beam injection follow orbits with a larger minor radius. Flux surface shifts and ion drifts from changes in beam energy, poloidal beta, and plasma current move these orbits closer to the wall. These factors increase the chance of ion loss through wall collisions. This study is believed to help optimize design and operation of NBI systems. |
