Publications of Y. Feng
All genres
Journal Article (242)
2025
Journal Article
67, 045012 (2025)
Magnetic mesh generation and field line reconstruction for scrape-off layer and divertor modeling in stellarators. Plasma Physics and Controlled Fusion
Journal Article
65, 016023 (2025)
A universal target plate design scheme for stellarators: theoretical basis and its application to heat load control. Nuclear Fusion
Journal Article
42, 101837 (2025)
Numerical modeling of impurity powder injection in W7-X. Nuclear Materials and Energy
Journal Article
42, 101881 (2025)
Integrated modelling of lithium transport and radiation under a liquid lithium divertor on EAST. Nuclear Materials and Energy 2024
Journal Article
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
Journal Article
64 (7-8) (2024)
Impact of multifold magnetic structure on spectroscopyanalysis in Heliotron J based on EMC3-EIRENE simulation. Contributions to Plasma Physics
Journal Article
64, 126044 (2024)
A semi-automated algorithm for designing stellarator divertor and limiter plates and application to HSX. Nuclear Fusion
Journal Article
64 (7-8), e202300154 (2024)
Toward plasma drifts in EMC3: Implementation of gradient, divergence, and particle tracing schemes. Contributions to Plasma Physics
Journal Article
42, 101832 (2024)
Integrated modeling of boron powder injection for real-time plasma-facing component conditioning. Nuclear Materials and Energy
Journal Article
64, 086027 (2024)
Conditions and benefits of X-point radiation for the island divertor. Nuclear Fusion
Journal Article
64, 076035 (2024)
Heuristic predictions of RMP configurations for ELM suppression in ITER burning plasmas and their impact on divertor performance. Nuclear Fusion
Journal Article
64, 076060 (2024)
Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X. Nuclear Fusion
Journal Article
64, 112002 (2024)
Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components. Nuclear Fusion
Journal Article
64, 096024 (2024)
Off-target gradient-driven flows in 3D simulations of ADITYA-Upgrade tokamak scrape-off layer plasma transport. Nuclear Fusion
Journal Article
64, 056042 (2024)
Impurity leakage mechanisms in the Wendelstein 7-X island divertor under friction-dominated conditions. Nuclear Fusion
Journal Article
64, 126047 (2024)
First experimental confirmation of island SOL geometry effects in a high radiation regime on W7-X. Nuclear Fusion 2023
Journal Article
34, 101380 (2023)
Plasma response impact on RMP divertor footprint modeling for KSTAR. Nuclear Materials and Energy
Journal Article
65, 035015 (2023)
Simulations of lithium impurity transport with a liquid lithium divertor using EMC3-EIRENE and ITCD. Plasma Physics and Controlled Fusion
Journal Article
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
Journal Article
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