Publikationen von Z. Wang
Alle Typen
Zeitschriftenartikel (14)
2025
Zeitschriftenartikel
215, 114997 (2025)
ntermediate thermomechanical analysis and optimization of the ITER Upper port mounted bolometer camera. Fusion Engineering and Design 2024
Zeitschriftenartikel
204, 114495 (2024)
Thermal-hydraulic and structural analyses of an additive manufactured panel mock-up for Wendelstein 7-X. Fusion Engineering and Design 2023
Zeitschriftenartikel
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design
Zeitschriftenartikel
37, 101506 (2023)
Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy
Zeitschriftenartikel
192, 113768 (2023)
Electromagnetic analysis of the ITER port-mounted bolometer cameras. Fusion Engineering and Design
Zeitschriftenartikel
192, 113609 (2023)
Structural analysis of the ITER upper port mounted bolometer camera. Fusion Engineering and Design 2022
Zeitschriftenartikel
175, 112986 (2022)
Thermal loading test of a Wendelstein 7-X pumping gap panel. Fusion Engineering and Design 2021
Zeitschriftenartikel
167, 112290 (2021)
Thermal analyses of the W7-X plasma vessel for operation phase 2. Fusion Engineering and Design 2020
Zeitschriftenartikel
161, 111882 (2020)
Thermal and mechanical analyses of W7-X plasma facing components for operation phase 2. Fusion Engineering and Design 2019
Zeitschriftenartikel
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion 2018
Zeitschriftenartikel
46 (5), S. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science
Zeitschriftenartikel
46 (5), S. 1576 - 1579 (2018)
Thermal and Mechanical Analysis of the Wendelstein 7-X Cryo-Vacuum Pump Plug-In. IEEE Transactions on Plasma Science 2017
Zeitschriftenartikel
124, S. 292 - 296 (2017)
Structural analysis of the W7-X cryopump during the superconducting coil fast discharge event. Fusion Engineering and Design 2016
Zeitschriftenartikel
109-111, Pt. A, S. 773 - 776 (2016)
Prototyping phase of the high heat flux scraper element of Wendelstein 7-X. Fusion Engineering and Design Vortrag (2)
2023
Vortrag
Tungsten based target element development for Wendelstein 7-X. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
2017
Vortrag
Design and test of W7-X water-cooled Divertor Scraper. 27th IEEE Symposium on Fusion Engineering (SOFE 2017), Shanghai (eingereicht)
Poster (10)
2024
Poster
Thermomechanical Analysis and Optimization of the ITER Upper Port Mounted Bolometer Camera. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (eingereicht)
2023
Poster
Thermal and structural analyses of an additive manufactured panel mock-up for Wendelstein 7-X. 15th International Symposium on Fusion Nuclear Technology (ISFNT-15), Las Palmas de Gran Canaria (eingereicht)
2022
Poster
Conceptual design of the next generation of W7-X divertor W-target elements. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)
Poster
Electromagnetic Analysis of the ITER Port Bolometer Cameras. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)