Publikationen von B. Boeswirth
Alle Typen
Zeitschriftenartikel (86)
81.
Zeitschriftenartikel
82, S. 1713 - 1719 (2007)
High heat flux tests of the WENDELSTEIN 7-X pre-series target elements - Experimental evaluation of the thermo-mechanical behaviour. Fusion Engineering and Design 82.
Zeitschriftenartikel
75-79, S. 333 - 338 (2005)
Vacuum plasma-sprayed tungsten on EUROFER and 316L: Results of characterisation and thermal loading tests. Fusion Engineering and Design 83.
Zeitschriftenartikel
75-79, S. 345 - 350 (2005)
Design, performance and construction of a 2 MW ion beam test facility for plasma facing components. Fusion Engineering and Design 84.
Zeitschriftenartikel
9, S. 127 - 139 (2005)
Characterisation of plasma-sprayed boron carbide and tungsten layers for fusion applications. High Temperature Material Processes 85.
Zeitschriftenartikel
329-333, S. 849 - 854 (2004)
Evaluation of vacuum plasma-sprayed boron carbide protection for the stainless steel first wall of WENDELSTEIN 7-X. Journal of Nuclear Materials 86.
Zeitschriftenartikel
66-68, S. 447 - 452 (2003)
Final design of W7-X divertor plasma facing components – tests and thermo-mechanical analysis of baffle prototypes. Fusion Engineering and Design Konferenzbeitrag (4)
87.
Konferenzbeitrag
85, 02A718, (2014)
High energy flux thermo-mechanical test of 1D-carbon-carbon fibre composite prototypes for the SPIDER diagnostic calorimeter. 15th International Conference on Ion Sources (ICIS 2013) , Chiba, 09. September 2013 - 13. September 2013. Review of Scientific Instruments 88.
Konferenzbeitrag
455 (1-3), S. 681 - 684 (2014)
Surface morphology changes of tungsten exposed to high heat loading with mixed hydrogen/helium beams. 16th International Conference of Fusion Reactor Materials (ICFRM-16), Beijing, 20. Oktober 2013 - 26. Oktober 2013. Journal of Nuclear Materials 89.
Konferenzbeitrag
455 (1-3), S. 201 - 206 (2014)
Effects of temperature on surface modification of W exposed to He particles. 16th International Conference of Fusion Reactor Materials (ICFRM-16), Beijing, 20. Oktober 2013 - 26. Oktober 2013. Journal of Nuclear Materials 90.
Konferenzbeitrag
Status of the pre-series activities of the target elements for the W7-X divertor. Invited paper. In: 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-11), I17. 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-11), Greifswald, 10. Oktober 2006 - 12. Oktober 2006. (2006)
Vortrag (54)
91.
Vortrag
High Heat Flux Testing and Modeling of SPARC Plasma-Facing Components. 26th Technology of Fusion Energy Meeting (TOFE 2024), Madison, WI (2024)
92.
Vortrag
High heat flux testing of plasma-facing component mock-ups with tailored tungsten-copper composite heat sinks. The Nuclear Materials Conference (NuMat 2024), Singapore (eingereicht)
93.
Vortrag
Manufacturing and testing of optimized composite heat sinks for plasma-facing component applications. DPG-Frühjahrstagung der Sektion Materie und Kosmos (SMuK), Göttingen (eingereicht)
94.
Vortrag
Additive manufacturing for tungsten-based plasma-facing components. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (eingereicht)
95.
Vortrag
High heat flux testing of plasma-facing components for the compact, high field tokamak SPARC. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (eingereicht)
96.
Vortrag
Results and conclusions of high-power cycling of European DEMO divertor target mock-ups. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
97.
Vortrag
Liquid tin interaction with deuterium plasmas. 49th EPS Conference on Plasma Physics, Bordeaux (eingereicht)
98.
Vortrag
Testing of tungsten fibre-reinforced tungsten composites at the neutral beam facility GLADIS. 8th International Workshop on Plasma Material Interaction Facilities for Fusion Research, Eindhoven (eingereicht)
99.
Vortrag
Inhibited cavitation in lanthanum doped tungsten under multiple melting exposures in GLADIS and ASDEX-Upgrade. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
100.
Vortrag
Results of high heat flux overload tests of European DEMO tungsten divertor target mock-ups. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)