Publikationen von B. Böswirth
Alle Typen
Vortrag (49)
121.
Vortrag
Cyclic Heat Load Testing of Improved CFC/Cu Bonding for the W7-X Divertor Targets. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice (2007)
122.
Vortrag
Testing of improved CFC/Cu Bondings for the W7-X Divertor Targets. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice (2007)
123.
Vortrag
Results of HHF tests of W7-X target elements - the influence of degradation of heat transfer. ITER Divertor Meeting, Barcelona (2007)
124.
Vortrag
Fabrication and testing of W7-X pre-series target elements. 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-11), Greifswald (2006)
125.
Vortrag
Status of the pre-series activities of the target elements for the W7-X divertor. ITER Divertor Meeting, St. Petersburg (2006)
126.
Vortrag
Recent testing in the GLADIS HHF test facility in Garching. ITER Divertor Meeting, St. Petersburg (2006)
127.
Vortrag
High Heat Flux Facility GLADIS - Operational Characteristics and Results of W7-X Pre-Series Target Tests. 12th International Conference on Fusion Reactor Materials (ICFRM-12), Santa Barbara,CA (2005)
128.
Vortrag
Characterisation of Plasma Sprayed Boron Carbide and Tungsten Layers for Fusion Applications. E-MRS Spring Meeting 2004, Symposium S: TTP8 Thermal Plasma Processes, Strasbourg (2004)
129.
Vortrag
Evaluation of Vacuum Plasma-Sprayed Boron Carbide Protection for the Stainless Steel First Wall of W7-X. 11th International Conference on Fusion Reactor Materials (ICFRM-11), Kyoto (2003)
130.
Vortrag
Plasma Sprayed Tungsten Coatings on Steel. ITER Divertor Meeting, Naka (2003)
Poster (63)
131.
Poster
Additive manufacturing of divertor components with novel cooling structures. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (2023)
132.
Poster
Assessment of potassium-doped tungsten by high heat flux testing of small-scale divertor mock-up. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
133.
Poster
Tungsten coatings on Inconel for COMPASS Upgrade plasma-facing components. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (2023)
134.
Poster
High heat flux tests in support of the 3D computational modelling of melting for the EU-DEMO first wall limiters. 30th IEEE Symposium on Fusion Engineering (SOFE), Oxford (eingereicht)
135.
Poster
Armor thickness assessment for the DTT divertor targets. 30th IEEE Symposium on Fusion Engineering (SOFE), Oxford (eingereicht)
136.
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)
137.
Poster
Investigation of heat load limits of European DEMO divertor target mock- ups. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)
138.
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)
139.
Poster
Microstructural evolution of tungsten as divertor target armor under thermal loads: A comparative study between cyclic high heat flux loading and isochronous furnace heating. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
140.
Poster
Summary of thermal performance tests of European DEMO divertor target concepts. 31st Symposium on Fusion Technology (SOFT 2020), Virtual Edition (eingereicht)