Understanding Carbon Sourcing and Transport Originating from the Helicon Antenna Surfaces During High-Power Helicon Discharge in DIII-D Tokamak
This study utilizes the integrated STRIPE modeling framework to demonstrate that rectified RF sheath potentials near the DIII-D helicon antenna drive carbon erosion and transport, revealing that while current graphite-wall conditions limit core impurity accumulation, specific plasma configurations can still facilitate significant net erosion and core-directed impurity flux, underscoring the necessity for sheath-aware antenna designs in future high-power fusion devices.