Publikationen von Y. Feng
Alle Typen
Poster (188)
541.
Poster
Power exhaust in high-performance plasmas in Wendelstein 7-X. 48th EPS Conference on Plasma Physics, Virtual (eingereicht)
542.
Poster
Overview of the neutral gas pressures in Wendelstein 7-X under boronized wall conditions. 86. Jahrestagung der DPG und DPG-Frühjahrstagung der Sektion Materie und Kosmos (SMuK), Dresden (eingereicht)
543.
Poster
Measurements of impurity flows and line-radiation in the W7-X scrape-off layer. 4th IAEA Technical Meeting on Divertor Concepts, Vienna (2022)
544.
Poster
Assessing simple models for density build up and impurity exhaust in the island divertor of W7-X. 4th IAEA Technical Meeting on Divertor Concepts, Vienna (eingereicht)
545.
Poster
Compatibility of high-Z impurity accumulation with high plasma performance in ECR-heated W7-X plasmas. 48th EPS Conference on Plasma Physics, Virtual (eingereicht)
546.
Poster
Use of tungsten heavy-alloy as material for plasma-facing components in the fusion experiments LHD and W7-X. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
547.
Poster
Analysis of 3D effects on SOL transport in DIII-D impurity powder dropper experiments. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (2021)
548.
Poster
Enhanced Divertor Power Exhaust through Injection of Low-Z Powders in DIII-D. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (2021)
549.
Poster
Divertor Detachment in ITER during Application of Resonant Magnetic Perturbations for ELM Suppression. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (2021)
550.
Poster
Overview of baffle loads in W7-X and improvement in diffusive field line tracing for heat distribution predictions. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
551.
Poster
First feedback-controlled divertor detachment in W7-X: experience from TDU operation and prospects for operation with actively cooled divertor. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
552.
Poster
Three-dimensional simulations of impurity transport and power exhaust for neon- and argon-seeded edge plasma on HL-2M tokamak. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (2021)
553.
Poster
Investigation of heat flux distribution with neon injected at different toroidal positions on EAST. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (2021)
554.
Poster
Peripheral Plasma Transport Characteristics arising from 3D Magnetic Field Structure in Heliotron J. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (2021)
555.
Poster
EMC3-EIRENE simulations of injected lithium transport for H-mode plasma of EAST with different upstream densities. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (2021)
556.
Poster
Investigation of plasma flow stagnation regions for the Wendelstein 7-X magnetic island chain. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
557.
Poster
Investigating spectroscopic measurements in W7X seeded detachment experiments with EMC3 simulations. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
558.
Poster
Influence of Li source location on divertor SOL width and neutral radiation with EMC3-EIRENE modelling. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (2021)
559.
Poster
Effects of local gas puffing with 3D magnetic topology on the divertor flux. 47th EPS Conference on Plasma Physics, Virtual (2021)
560.
Poster
First Attempt to Quantify the Recycling Neutrals in W7-X by Means of Experiment-model Comparison. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (eingereicht)