Publications of B. Böswirth
All genres
Journal Article (71)
61.
Journal Article
T138, 014031 (5pp) (2009)
Qualification of tungsten coatings on plasma-facing components for JET. Physica Scripta 62.
Journal Article
T128, pp. 195 - 199 (2007)
Fabrication and testing of W7-X pre-series target elements. Physica Scripta 63.
Journal Article
82, pp. 1634 - 1638 (2007)
Results of the examinations of the W7-X pre-series target elements. Fusion Engineering and Design 64.
Journal Article
T128, pp. 218 - 221 (2007)
Power load limits of the WENDELSTEIN 7-X target elements - comparison of experimental results and design values for power loads up to the critical heat flux. Physica Scripta 65.
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 66.
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 67.
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 68.
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 69.
Journal Article
9, pp. 127 - 139 (2005)
Characterisation of plasma-sprayed boron carbide and tungsten layers for fusion applications. High Temperature Material Processes 70.
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 71.
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)
72.
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 73.
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 74.
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 75.
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 (45)
76.
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)
77.
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)
78.
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 Interactions in Controlled Fusion Devices (PSI 25), Jeju (submitted)
79.
Talk
Tungsten Fibre-reinforced Copper – A High-conductivity, High-strength Composite Material for Plasma-facing Component Applications. TMS 2021 Virtual Annual Meeting & Exhibition, Virtual (submitted)
80.
Talk
Tungsten Fibre-reinforced Copper – A High-conductivity, High-strength Composite Material for Plasma-facing Component Applications. TMS2021 - Composite Materials for Nuclear Applications, Virtual (submitted)