Controlling the NT shape boundary flux to expand achievable parameter space in NT plasmas (with possible EFC piggyback)
2024 Research Campaign, Negative Triangularity
Purpose of Experiment
Negative triangularity (NT) plasmas have shown exceptional promise in recent DIII-D and TCV experiments, offering a pathway to an inherently ELM-free fusion pilot plant (FPP). However, since all existing machines are designed with positive triangularity in mind, it is difficult to answer outstanding questions regarding NT FPP operation without the construction of a new device. This experiment aims to mitigate that challenge by providing methods with which the DIII-D tokamak can be more fully utilized to study remaining NT challenges. If successful, this would enable a more robust assessment of NT FPP physics without requiring the construction of an entirely new tokamak facility. The overall goal of this diverted negative triangularity plasma control study is to identify and incorporate more optimized algorithmic and hardware configurations that allow us to expand DIII-D’s achievable NT plasma parameter operating space to the fullest extent possible given the existing DIII-D Poloidal Field (PF) coilset and actuating power supplies.