Publikationen von J.-H. You
Alle Typen
Poster (127)
401.
Poster
Design options to avoid deep cracking of tungsten armor at 20 MW/m2. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (eingereicht)
402.
Poster
Advanced Tungsten-Based Materials as an Option for a Fusion Reactor. 26th IAEA Fusion Energy Conference (FEC 2016), Kyoto (eingereicht)
403.
Poster
Systems engineering approach for pre-conceptual design of DEMO divertor cassette. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (2016)
404.
Poster
Issues involved in the choice of low operating temperature for DEMO Eurofer divertor cassette. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (2016)
405.
Poster
Power exhaust in a nuclear fusion reactor and the possibility to use W-Cu composites as heat sink materials for highly loaded plasma facing components. 6th Colloquium of the Munich School of Engineering: "New Concepts in Energy Science and Engineering", Garching (eingereicht)
406.
Poster
Melt infiltrated W-Cu composites as advanced heat sink materials for plasma facing components. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (eingereicht)
407.
Poster
Development of a graded W/CuCrZr divertor for DEMO reactor. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (2016)
408.
Poster
Analysis of steady state thermal-hydraulic behaviour of the DEMO divertor cassette body cooling circuit. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (2016)
409.
Poster
Progress in the initial design activities for the European DEMO divertor. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (eingereicht)
410.
Poster
Structural Design of DEMO Divertor Cassette Body: FEM Analysis and RCCMRx Design Rules Application. 12th International Symposium on Fusion Nuclear Technology (ISFNT-12), Jeju Island, Korea (2015)
411.
Poster
How does tungsten get cracked under ELM-like transient thermal loads? A fracture mechanics study. 17th International Conference on Fusion Reactor Materials (ICFRM-17), Aachen (eingereicht)
412.
Poster
Limitations of Transient Power Loads on DEMO and Analysis of Mitigation Techniques. 12th International Symposium on Fusion Nuclear Technology (ISFNT-12), Jeju Island, Korea (2015)
413.
Poster
Manufacturing W fibre-reinforced Cu composite pipes for application as heat sink in divertor targets of future nuclear fusion reactors. DPG-Frühjahrstagung der Sektion Atome, Moleküle, Quantenoptik und Plasmen (SAMOP), Hannover (eingereicht)
414.
Poster
Tungsten Fibre-Reinforced Composites for Advanced Plasma Facing Components. 22nd International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 22), Rome (eingereicht)
415.
Poster
European roadmap and progress on the mission for solution on heat-exhaust systems. 1st IAEA Technical Meeting on Divertor Concepts, Vienna (2015)
416.
Poster
Results of high heat flux testing of W/CuCRZr multilayer composites with percolating microstructure for plasma-facing components. 28th Symposium on Fusion Technology (SOFT 2014)
, San Sebastian (eingereicht)
417.
Poster
Graded W/CuCrZr Composites for Water-Cooled Heat Sink Applications. 16th International Conference on Fusion Reactor Materials (ICFRM-16), Beijing (2013)
418.
Poster
Recent progress on the metallurgy and testing of W wire-reinforced W composites. IEA W Satellite Meeting at 16th International Conference on Fusion Reactor Materials (ICFRM-16), Beijing (2013)
419.
Poster
A solution for operation embrittlement of tungsten components: tungsten fibre-reinforced tungsten. 11th International Symposium on Fusion Nuclear Technology (ISFNT-11), Barcelona (2013)
420.
Poster
Atomistic Modelling of Crystal Plasticity of Tungsten. 14th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-14), Jülich (2013)