Publications of J. H. You
All genres
Talk (123)
221.
Talk
Materials R&D for a 2nd ITER Divertor and beyond: an overview of available concepts and new material classes. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (2019)
222.
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)
223.
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)
224.
Talk
Systems Engineering Approach for Pre-Conceptual Design of DEMO Divertor. 26th International Conference on Nuclear Engineering (ICONE26), London (2019)
225.
Talk
Additive manufacturing of tungsten by means of laser powder bed fusion for plasma-facing component applications. 3rd IAEA Technical Meeting on Divertor Concepts, Vienna (submitted)
226.
Talk
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. International Conference on Processing & Manufacturing of Advanced Materials (Thermec 2021), Virtual (submitted)
227.
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)
228.
Talk
Tungsten fibre-reinforced tungsten composite – extrinsic toughening of a new high performance material. 10th International Conference on High Temperature Ceramic Matrix Composites (HT-CMC10), Bordeaux (submitted)
229.
Talk
Status of Preconceptual Design and Technology R&D for the EU DEMO Divertor. 14th International Symposium on Fusion Nuclear Technology (ISFNT-14), Budapest (submitted)
230.
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)
231.
Talk
Materials Development for new high heat-flux component mockups for DEMO. 30th Symposium on Fusion Technology (SOFT 2018), Giardini Naxos (submitted)
232.
Talk
Neutron diffraction measurement of residual stresses in an ITER-like tungsten-monoblock type plasma-facing component. 30th Symposium on Fusion Technology (SOFT 2018), Giardini Naxos (2018)
233.
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)
234.
Talk
Defect inspection and high-heat-flux testing of nuclear fusion reactor components. 50. Tagung des DVM-Arbeitskreises Bruchmechanik und Bauteilsicherheit, Paderborn (submitted)
235.
Talk
The development and testing of the thermal break divertor monoblock target design delivering 20 MW/m2 heat load capability. 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16), Neuss (submitted)
236.
Talk
Strategy and results of high heat flux testing of European DEMO divertor mock-ups. 2nd IAEA Technical Meeting on Divertor Concepts, Suzhou (submitted)
237.
Talk
Modelling the thermophysical and -mechanical properties of tungsten fibre-reinforced copper metal matrix composites by means of mean field homogenisation. 8th Forum on New Materials (CIMTEC 2018), Perugia (submitted)
238.
Talk
Realization of high heat flux W monoblock type target with graded interlayer for application to DEMO divertor. 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16), Neuss (submitted)
239.
Talk
Advanced Materials for Plasma-facing Components of Fusion Power Plants? Tungsten Fibre-reinforced Composites. 20. Werkstofftechnisches Kolloquium (WTK 2018), Technische Universität Chemnitz (submitted)
240.
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)