Publikationen von J. H. You
Alle Typen
Vortrag (122)
201.
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)
202.
Vortrag
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 (eingereicht)
203.
Vortrag
Sacrificial limiter for DEMO wall protection: material concepts, technology and performance under extreme heat loads. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
204.
Vortrag
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 (eingereicht)
205.
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)
206.
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)
207.
Vortrag
Materials and Components for the DEMO Divertor. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (eingereicht)
208.
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)
209.
Vortrag
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)
210.
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)
211.
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)
212.
Vortrag
Systems Engineering Approach for Pre-Conceptual Design of DEMO Divertor. 26th International Conference on Nuclear Engineering (ICONE26), London (2019)
213.
Vortrag
Additive manufacturing of tungsten by means of laser powder bed fusion for plasma-facing component applications. 3rd IAEA Technical Meeting on Divertor Concepts, Vienna (eingereicht)
214.
Vortrag
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. International Conference on Processing & Manufacturing of Advanced Materials (Thermec 2021), Virtual (eingereicht)
215.
Vortrag
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 (eingereicht)
216.
Vortrag
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 (eingereicht)
217.
Vortrag
Status of Preconceptual Design and Technology R&D for the EU DEMO Divertor. 14th International Symposium on Fusion Nuclear Technology (ISFNT-14), Budapest (eingereicht)
218.
Vortrag
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 (eingereicht)
219.
Vortrag
Materials Development for new high heat-flux component mockups for DEMO. 30th Symposium on Fusion Technology (SOFT 2018), Giardini Naxos (eingereicht)
220.
Vortrag
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)