Publikationen von J.-H. You
Alle Typen
Zeitschriftenartikel (176)
2024
Zeitschriftenartikel
201, 114268 (2024)
Galvanic process for Cu-infiltration of W fibre-reinforced heat sinks. Fusion Engineering and Design
Zeitschriftenartikel
262, 119453 (2024)
Bimodal structured chromium-tungsten composite as plasma-facing materials: Sinterability, mechanical properties, and deuterium retention assessment. Acta Materialia
Zeitschriftenartikel
200, 114240 (2024)
Hypothetical porous medium concept as a virtual swirl tape: A novel modelling technique towards efficient CFD simulation of swirl tape cooling pipe. Fusion Engineering and Design
Zeitschriftenartikel
38, 101591 (2024)
Progress in the development of industrial scale tungsten fibre-reinforced composite materials. Nuclear Materials and Energy 2023
Zeitschriftenartikel
34, 101446 (2023)
Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors. Nuclear Materials and Energy
Zeitschriftenartikel
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design
Zeitschriftenartikel
191, 113742 (2023)
Pre-conceptual design of a PFC equipped with a W lattice armour for first wall limiters in the EU-DEMO fusion reactor. Fusion Engineering and Design
Zeitschriftenartikel
190, 113522 (2023)
Ferromagnetic forces acting on the EU-DEMO divertor. Fusion Engineering and Design
Zeitschriftenartikel
37, 101506 (2023)
Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy
Zeitschriftenartikel
194, 113829 (2023)
Structural assessment investigations of the DEMO Divertor shielding components with reference to RCC-MRx. Fusion Engineering and Design
Zeitschriftenartikel
262, 119453 (2023)
Bimodal structured chromium-tungsten composite as plasma-facing materials: Sinterability, mechanical properties, and deuterium retention assessment. Acta Materialia
Zeitschriftenartikel
194, 113917 (2023)
Systems engineering procedure for requirements management of divertor system of tokamak reactors. Fusion Engineering and Design
Zeitschriftenartikel
188, 113426 (2023)
Creep fatigue analysis of DEMO divertor components following the RCC-MRx design code. Fusion Engineering and Design
Zeitschriftenartikel
36, 101465 (2023)
Microstructural evolution of tungsten under thermal loads: A comparative study between cyclic high heat flux loading and isochronous furnace heating. Nuclear Materials and Energy
Zeitschriftenartikel
10, 116516 (2023)
Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing. Materials Research Express
Zeitschriftenartikel
13 (3), 1715 (2023)
Neutronics Assessment of the Spatial Distributions of the Nuclear Loads on the DEMO Divertor ITER-like Targets: Comparison between the WCLL and HCPB Blanket. Applied Sciences
Zeitschriftenartikel
194, 113866 (2023)
Analysis of the nuclear loads on Chromium monoblock divertor target for DEMO. Fusion Engineering and Design
Zeitschriftenartikel
35, 101433 (2023)
Assessment of flow-assisted corrosion rate of copper alloy cooling tube for application in fusion reactors. Nuclear Materials and Energy
Zeitschriftenartikel
194, 113699 (2023)
Cyclic medium heat flux testing of a WTa lattice structure on the HIVE facility. Fusion Engineering and Design
Zeitschriftenartikel
188, 113408 (2023)
Thermofluid-dynamic assessment of the EU-DEMO divertor single-circuit cooling option. Fusion Engineering and Design