Overview of recent experimental results from KSTAR

KSTAR research aims to achieve high performance plasma operation under tungsten wall conditions for ITER and future fusion reactors by mitigating tungsten impurity accumulation in the core. A significant reduction in core radiation losses has been achieved by minimizing tungsten impurity influx through rapid T_i pedestal formation and ELM control. Mitigation of type-I ELMs using edge-localized RMPs has been achieved for long pulses up to 32 seconds. Control of TAEs has been demonstrated using ECCD and a reduction in neutral beam drive. Real-time divertor detachment control has been demonstrated using surrogate models. Additionally, the position of peak divertor radiation has been successfully controlled in real time. Boron powder injection reduced tungsten line emission from the lower divertor and also decreased the radiated power. The first real-time demonstration of disruption avoidance by DECAF was produced through the application of the Event feedback control. Real-time disruption mitigation using a neural network-based disruption predictor and massive gas injection has been successfully demonstrated. Following the joint high β_p scenario experiment on DIII-D using KSTAR-like constraints, experiments in KSTAR have achieved promising results with an internal transport barrier formed at a large radius. The results of the experimental studies conducted during the 2024 KSTAR operation will be reported.