Publications of B. Boeswirth
All genres
Journal Article (85)
81.
Journal Article
75-79, pp. 333 - 338 (2005)
Vacuum plasma-sprayed tungsten on EUROFER and 316L: Results of characterisation and thermal loading tests. Fusion Engineering and Design 82.
Journal Article
75-79, pp. 345 - 350 (2005)
Design, performance and construction of a 2 MW ion beam test facility for plasma facing components. Fusion Engineering and Design 83.
Journal Article
9, pp. 127 - 139 (2005)
Characterisation of plasma-sprayed boron carbide and tungsten layers for fusion applications. High Temperature Material Processes 84.
Journal Article
329-333, pp. 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 85.
Journal Article
66-68, pp. 447 - 452 (2003)
Final design of W7-X divertor plasma facing components – tests and thermo-mechanical analysis of baffle prototypes. Fusion Engineering and Design Conference Paper (4)
86.
Conference Paper
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, September 09, 2013 - September 13, 2013. Review of Scientific Instruments 87.
Conference Paper
455 (1-3), pp. 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, October 20, 2013 - October 26, 2013. Journal of Nuclear Materials 88.
Conference Paper
455 (1-3), pp. 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, October 20, 2013 - October 26, 2013. Journal of Nuclear Materials 89.
Conference Paper
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, October 10, 2006 - October 12, 2006. (2006)
Talk (53)
90.
Talk
High Heat Flux Testing and Modeling of SPARC Plasma-Facing Components. 26th Technology of Fusion Energy Meeting (TOFE 2024), Madison, WI (2024)
91.
Talk
High heat flux testing of plasma-facing component mock-ups with tailored tungsten-copper composite heat sinks. The Nuclear Materials Conference (NuMat 2024), Singapore (submitted)
92.
Talk
Additive manufacturing for tungsten-based plasma-facing components. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (submitted)
93.
Talk
High heat flux testing of plasma-facing components for the compact, high field tokamak SPARC. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (submitted)
94.
Talk
Results and conclusions of high-power cycling of European DEMO divertor target mock-ups. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (submitted)
95.
Talk
Liquid tin interaction with deuterium plasmas. 49th EPS Conference on Plasma Physics, Bordeaux (submitted)
96.
Talk
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 (submitted)
97.
Talk
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 (submitted)
98.
Talk
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 (submitted)
99.
Talk
Development of tungsten fibre-reinforced copper alloy composites for application as heat sink materials in DEMO high heat flux components. CIMTEC 2022: 15th International Ceramics Congress and 9th Forum on New Materials, Perugia (submitted)
100.
Talk
High-heat-flux performance limit of the DEMO divertor targets: Implications on power exhaust capacity from a technology point of view. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (submitted)