Publications of B. Böswirth
All genres
Talk (54)
101.
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)
102.
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)
103.
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)
104.
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)
105.
Talk
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 (submitted)
106.
Talk
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 (submitted)
107.
Talk
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 (submitted)
108.
Talk
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 (submitted)
109.
Talk
Tungsten-copper composite materials for plasma-facing component heat sink applications. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
110.
Talk
Status of technology R&D and the results of pre-conceptual evaluation of the EU DEMO divertor target concepts. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (submitted)
111.
Talk
Tungsten-Copper Composites as Advanced Heat Sink Materials for Plasma-Facing Components – Performance of Mock-ups under High Heat Flux Loading. International Conference on Processing and Manufacturing of Advanced Materials Processing, Fabrication, Properties, Applications (THERMEC 2018), Paris (submitted)
112.
Talk
Design and test of W7-X water-cooled Divertor Scraper. 27th IEEE Symposium on Fusion Engineering (SOFE 2017), Shanghai (submitted)
113.
Talk
Behaviour of mm-thick W coatings on CFC for JT-60SA under high heat fluxes. 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16), Neuss (submitted)
114.
Talk
Strategy and results of high heat flux testing of European DEMO divertor mock-ups. 2nd IAEA Technical Meeting on Divertor Concepts, Suzhou (submitted)
115.
Talk
Status and recent research at the neutral beam facility GLADIS. 6th International Workshop on Plasma Material Interaction Facilities for Fusion Research (PMIF 2017), Tsukuba (2017)
116.
Talk
Starting the WEST platform: testing ITER-like divertor target plasma facing units in a tokamak environment. 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16), Neuss (2017)
117.
Talk
Novel Plasma-Facing Components for DEMO Divertor: Impact of Materials on Design Concepts and High-Heat-Flux Performance. 18th International Conference on Fusion Reactor Materials (ICFRM-18), Aomori (submitted)
118.
Talk
Novel Composites and Advanced Design Concepts for DEMO Divertor Targets. 8th Forum on New Materials (CIMTEC 2018), Perugia (submitted)
119.
Talk
Potential approach of IR analysis for HHF quality assessment of ITER tungsten divertor targets. 22nd ITPA Meeting on SOL/Divertor Physics, Frascati (submitted)
120.
Talk
Potential approach of IR-analysis for HHF quality assessment of ITER tungsten divertor targets. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (submitted)