Pellet studies and core optimization to achieve high absolute parameters in the SVR ELMy scenario with dedicated detachment studies
2025 Research Campaign, Thrust: Shape Rise Divertor
Purpose of Experiment
Future devices are expected to operate at low collisionality at high density. These conditions lead to a situation where the scrape off layer (SOL) is expected to be opaque and neutrals will not effectively fuel the plasma contributing to low density gradients. Previous DIII-D experiments were not able to access this regime, but it is considered to be one of the largest outstanding questions in the tokamak path to magnetic fusion to close the Integrated Tokamak Exhaust Performance (ITEP) gap, which is often referred to as Core-Edge Integration (CEI).
Experimental Approach
This experiment will attempt to produce ELMy H-mode discharges with high pedestal pressure at high pedestal density that are predicted to be accessible in the Super-H regime with strong plasma shaping at high plasma current.
See more details, including project leads, at U.S. Department of Energy, Office of Scientific and Technical Information (OSTI).