Publikationen von Y. Gao
Alle Typen
Zeitschriftenartikel (53)
1.
Zeitschriftenartikel
42, 101846 (2025)
In-vessel inspection of arc traces on the W7-X plasma facing components after the operation phase OP2.1. Nuclear Materials and Energy 2.
Zeitschriftenartikel
64, 126055 (2024)
Impact of spatially varying transport coefficients in EMC3-Eirene simulations of W7-X and assessment of drifts. Nuclear Fusion 3.
Zeitschriftenartikel
203, 114413 (2024)
Manufacturing, installation, commissioning and operation of endoscopes for monitoring water-cooled divertor in Wendelstein 7-X. Fusion Engineering and Design 4.
Zeitschriftenartikel
64, 086027 (2024)
Conditions and benefits of X-point radiation for the island divertor. Nuclear Fusion 5.
Zeitschriftenartikel
64, 076060 (2024)
Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X. Nuclear Fusion 6.
Zeitschriftenartikel
64, 112002 (2024)
Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components. Nuclear Fusion 7.
Zeitschriftenartikel
64, 086016 (2024)
Validation of the ERO2.0 code using W7-X and JET experiments and predictions for ITER operation. Nuclear Fusion 8.
Zeitschriftenartikel
34, 101401 (2023)
Physics Informed Neural Networks towards the real-time calculation of heat fluxes at W7-X. Nuclear Materials and Energy 9.
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 10.
Zeitschriftenartikel
190, 113524 (2023)
Implementation and performance evaluation of the real-time algorithms for Wendelstein 7-X divertor protection system for OP2.1. Fusion Engineering and Design 11.
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 12.
Zeitschriftenartikel
63, 026011 (2023)
On the interaction between the island divertor heat fluxes, the scrape-off layer radial electric field and the edge turbulence in Wendelstein 7-X plasmas. Nuclear Fusion 13.
Zeitschriftenartikel
34, 101352 (2023)
Assessment of carbon net erosion/deposition at the divertor of W7-X. Nuclear Materials and Energy 14.
Zeitschriftenartikel
37, 101514 (2023)
Performance of tungsten plasma facing components in the stellarator experiment W7-X: Recent results from the first OP2 campaign. Nuclear Materials and Energy 15.
Zeitschriftenartikel
63, 066005 (2023)
Modeling of plasma beta effects on the island divertor transport in the standard configuration of W7-X. Nuclear Fusion 16.
Zeitschriftenartikel
65, 105006 (2023)
Observation of impurity accumulation and its compatibility with high plasma performance in W7-X. Plasma Physics and Controlled Fusion 17.
Zeitschriftenartikel
62, 106011 (2022)
Parametrisation of target heat flux distribution and study of transport parameters for boundary modelling in W7-X. Nuclear Fusion 18.
Zeitschriftenartikel
62, 016006 (2022)
Plasma-surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components. Nuclear Fusion 19.
Zeitschriftenartikel
64, 125015 (2022)
Identification of fast ion wall loads in Wendelstein 7-X from thermographic measurements. Plasma Physics and Controlled Fusion 20.
Zeitschriftenartikel
15 (6), 2088 (2022)
Evaluation of NVIDIA Xavier NX Platform for Real-Time Image Processing for Plasma Diagnostics. Energies