Publikationen von Y. Feng
Alle Typen
Zeitschriftenartikel (241)
1.
Zeitschriftenartikel
65, 016023 (2025)
A universal target plate design scheme for stellarators: theoretical basis and its application to heat load control. Nuclear Fusion 2.
Zeitschriftenartikel
42, 101837 (2025)
Numerical modeling of impurity powder injection in W7-X. Nuclear Materials and Energy 3.
Zeitschriftenartikel
42, 101881 (2025)
Integrated modelling of lithium transport and radiation under a liquid lithium divertor on EAST. Nuclear Materials and Energy 4.
Zeitschriftenartikel
66, 015005 (2024)
Analysis of the neutral fluxes in the divertor region of Wendelstein 7-X under attached and detached conditions using EMC3-EIRENE. Plasma Physics and Controlled Fusion 5.
Zeitschriftenartikel
64 (7-8) (2024)
Impact of multifold magnetic structure on spectroscopyanalysis in Heliotron J based on EMC3-EIRENE simulation. Contributions to Plasma Physics 6.
Zeitschriftenartikel
64, 126044 (2024)
A semi-automated algorithm for designing stellarator divertor and limiter plates and application to HSX. Nuclear Fusion 7.
Zeitschriftenartikel
64 (7-8), e202300154 (2024)
Toward plasma drifts in EMC3: Implementation of gradient, divergence, and particle tracing schemes. Contributions to Plasma Physics 8.
Zeitschriftenartikel
42, 101832 (2024)
Integrated modeling of boron powder injection for real-time plasma-facing component conditioning. Nuclear Materials and Energy 9.
Zeitschriftenartikel
64, 086027 (2024)
Conditions and benefits of X-point radiation for the island divertor. Nuclear Fusion 10.
Zeitschriftenartikel
64, 076035 (2024)
Heuristic predictions of RMP configurations for ELM suppression in ITER burning plasmas and their impact on divertor performance. Nuclear Fusion 11.
Zeitschriftenartikel
64, 076060 (2024)
Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X. Nuclear Fusion 12.
Zeitschriftenartikel
64, 112002 (2024)
Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components. Nuclear Fusion 13.
Zeitschriftenartikel
64, 096024 (2024)
Off-target gradient-driven flows in 3D simulations of ADITYA-Upgrade tokamak scrape-off layer plasma transport. Nuclear Fusion 14.
Zeitschriftenartikel
64, 056042 (2024)
Impurity leakage mechanisms in the Wendelstein 7-X island divertor under friction-dominated conditions. Nuclear Fusion 15.
Zeitschriftenartikel
64, 126047 (2024)
First experimental confirmation of island SOL geometry effects in a high radiation regime on W7-X. Nuclear Fusion 16.
Zeitschriftenartikel
34, 101380 (2023)
Plasma response impact on RMP divertor footprint modeling for KSTAR. Nuclear Materials and Energy 17.
Zeitschriftenartikel
65, 035015 (2023)
Simulations of lithium impurity transport with a liquid lithium divertor using EMC3-EIRENE and ITCD. Plasma Physics and Controlled Fusion 18.
Zeitschriftenartikel
63, 026031 (2023)
Improvement in the simulation tools for heat distribution predictions and control of baffle and middle divertor loads in Wendelstein 7-X. Nuclear Fusion 19.
Zeitschriftenartikel
65, 055024 (2023)
Overview over the neutral gas pressures in Wendelstein 7-X during divertor operation under boronized wall conditions. Plasma Physics and Controlled Fusion 20.
Zeitschriftenartikel
34, 101363 (2023)
First feedback-controlled divertor detachment in W7-X: Experience from TDU operation and prospects for operation with actively cooled divertor. Nuclear Materials and Energy