Publications of B. Boeswirth
All genres
Journal Article (87)
2007
Journal Article
367-370, pp. 1444 - 1448 (2007)
High Heat Flux Facility GLADIS - Operational Characteristics and Results of W7-X Pre-Series Target Tests. Journal of Nuclear Materials
Journal Article
82, pp. 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 2005
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
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
Journal Article
9, pp. 127 - 139 (2005)
Characterisation of plasma-sprayed boron carbide and tungsten layers for fusion applications. High Temperature Material Processes 2004
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 2003
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)
2014
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
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
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 2006
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 (55)
2025
Talk
High heat flux testing of actively cooled graphite- and tungsten-armoured JT-60SA flattile divertor mock-ups. 20th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-20), Ljubljana (submitted)
2024
Talk
High Heat Flux Testing and Modeling of SPARC Plasma-Facing Components. 26th Technology of Fusion Energy Meeting (TOFE 2024), Madison, WI (2024)
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)
Talk
Manufacturing and testing of optimized composite heat sinks for plasma-facing component applications. DPG-Frühjahrstagung der Sektion Materie und Kosmos (SMuK), Göttingen (submitted)
Talk
Additive manufacturing for tungsten-based plasma-facing components. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (submitted)
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)
2023
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)
Talk
Liquid tin interaction with deuterium plasmas. 49th EPS Conference on Plasma Physics, Bordeaux (submitted)
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)