Publikationen von R. Neu
Alle Typen
Poster (239)
881.
Poster
Status of design of the First Wall supports of the Divertor Tokamak Test facility. 30th IEEE Symposium on Fusion Engineering (SOFE), Oxford (eingereicht)
882.
Poster
Qualification activities of the DTT Divertor. 30th IEEE Symposium on Fusion Engineering (SOFE), Oxford (eingereicht)
883.
Poster
Sputter yield of tungsten materials with strongly different microstructure. 15th International Symposium on Fusion Nuclear Technology (ISFNT-15), Las Palmas de Gran Canaria (eingereicht)
884.
Poster
Design of the divertor for the DTT facility optimized for power exhaust experiments. 29th IAEA Fusion Energy Conference (FEC 2023), London (eingereicht)
885.
Poster
Galvanic process for infiltration of W fibre-reinforced heat sinks. 15th International Symposium on Fusion Nuclear Technology (ISFNT-15), Las Palmas de Gran Canaria (eingereicht)
886.
Poster
Build quality benchmark of tungsten powder bed fusion additive manufacturing processes. DPG-Frühjahrstagung 2024, Greifswald (eingereicht)
887.
Poster
Plasma-facing components based on tungsten fiber reinforced tungsten composites: mock-up production. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (2023)
888.
Poster
An engineering tool for the minimization of leading edges in a tungsten-based divertor for W7-X. DPG-Frühjahrstagung 2024, Greifswald (eingereicht)
889.
Poster
Engineering tool to optimize for leading edges in a full-W divertor for W7-X. 15th International Symposium on Fusion Nuclear Technology (ISFNT-15), Las Palmas de Gran Canaria (eingereicht)
890.
Poster
Testing of advanced tungsten materials under high particle flux and intense transients in DIII-D. 26th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 26), Marseille (eingereicht)
891.
Poster
Armor thickness assessment for the DTT divertor targets. 30th IEEE Symposium on Fusion Engineering (SOFE), Oxford (eingereicht)
892.
Poster
Conceptual design of the next generation of W7-X divertor W-target elements. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)
893.
Poster
Qualification of W Heavy Alloys as Plasma Facing Material. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
894.
Poster
Properties of Metal Droplets Ejected During Arcing. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
895.
Poster
Pre-conceptual design of a PFC provided with a W lattice armor for first wall sacrificial limiter applications in the EU-DEMO fusion reactor. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)
896.
Poster
An overview of the conceptual design of the plasma-facing components of the DTT divertor. 4th IAEA Technical Meeting on Divertor Concepts, Vienna (2022)
897.
Poster
Conceptual design of the main First Wall of the Divertor Tokamak Test facility. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)
898.
Poster
The GIRAFFE Experiment – Current Status and Future Developments for Material Testing under Fusion-Relevant Loads. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)
899.
Poster
Metallographic investigations of W-Ta- cold spray coatings on P92 after high heat flux loading. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
900.
Poster
Tungsten-copper composites based on additively manufactured tungsten preforms for high heat flux applications. 86. Jahrestagung der DPG und DPG-Frühjahrstagung der Sektion Materie und Kosmos (SMuK), Dresden (eingereicht)