Robert S Wilcox Contact 858.455.2271 | wilcoxrs@ornl.gov All Publications Pellet triggering of edge localized modes in low collisionality pedestals at DIII-D Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E x B drift flows Simulations of divertor designs that spatially separate power and particle exhaust using mid-leg divertor particle pumping Characterization of the ELM-free negative triangularity edge on DIII-D... Understanding the L-H isotope effect at the DIII-D tokamak and advancements in synthetic turbulence diagnostics Interpretive modeling of tungsten divertor leakage during experiments with neon gas seeding High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas Runaway electron plateau current profile reconstruction from synchrotron imaging and Ar-II line polarization angle measurements in DIII-D Highest fusion performance without harmful edge energy bursts in tokamak... Prediction of pellet mass thresholds for ELM triggering in low-collisionality, ITER-like discharges Calibration improvements expand filterscope diagnostic use Tungsten erosion and divertor leakage from the DIII-D SAS-VW tungsten-coated divertor in experiments with neon gas seeding Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES PREDICTION OF PELLET MASS THRESHOLDS FOR ELM TRIGGERING IN LOW-COLLISIONALITY, ITER-LIKE DISCHARGES... Observation of D2 molecule line emission after massive D2 injection into runaway electron plateaus in DIII-D... In-situ coating of silicon-rich films on tokamak plasma-facing components with real-time Si material injection Spectroscopic measurement of increases in hydrogen molecular rotational temperature with plasma-facing surface temperature and due to collisional-radiative processes in tokamaks UEDGE-CRUMPET predicted isotopologue effect on atomic and molecular emission in DIII-D high-recycling divertor plasmas 13C surface characterization of midplane and crown collector probes on DIII-D Reducing the L-H transition power threshold in ITER-similar-shape DIII-D hydrogen plasmas E × B flow driven electron temperature bifurcation in a closed slot divertor with ion B × ∇B away from the X-point in the DIII-D tokamak DIII-D research advancing the physics basis for optimizing the tokamak approach to fusion energy Disruptive neoclassical tearing mode seeding in DIII-D with implications for ITER Growing neoclassical tearing modes seeded via transient-induced-multimode interactions Pellet ELM triggering in DIII-D with low collisionality, peeling-limited pedestals Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Fusion Energy Division Burning Plasma Foundations Section Advanced Tokamak Physics Group
