Publikationen von B. Böswirth
Alle Typen
Zeitschriftenartikel (69)
61.
Zeitschriftenartikel
82, S. 1634 - 1638 (2007)
Results of the examinations of the W7-X pre-series target elements. Fusion Engineering and Design 62.
Zeitschriftenartikel
T128, S. 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 63.
Zeitschriftenartikel
367-370, S. 1444 - 1448 (2007)
High Heat Flux Facility GLADIS - Operational Characteristics and Results of W7-X Pre-Series Target Tests. Journal of Nuclear Materials 64.
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 65.
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 66.
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 67.
Zeitschriftenartikel
9, S. 127 - 139 (2005)
Characterisation of plasma-sprayed boron carbide and tungsten layers for fusion applications. High Temperature Material Processes 68.
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 69.
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)
70.
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 71.
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 72.
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 73.
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 (43)
74.
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)
75.
Vortrag
Tungsten Fibre-reinforced Copper – A High-conductivity, High-strength Composite Material for Plasma-facing Component Applications. TMS 2021 Virtual Annual Meeting & Exhibition, Virtual (eingereicht)
76.
Vortrag
Tungsten Fibre-reinforced Copper – A High-conductivity, High-strength Composite Material for Plasma-facing Component Applications. TMS2021 - Composite Materials for Nuclear Applications, Virtual (eingereicht)
77.
Vortrag
The quest for a durable high-heat-flux component: requirements and issues. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
78.
Vortrag
Assessment of the High Heat Flux Performance of European DEMO Divertor Mock-ups. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (eingereicht)
79.
Vortrag
Investigation of the thermal performance of newly developed European DEMO divertor target concepts. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (eingereicht)
80.
Vortrag
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (eingereicht)