Publications of J.-H. You
All genres
Journal Article (173)
1.
Journal Article
38, 101591 (2024)
Progress in the development of industrial scale tungsten fibre-reinforced composite materials. Nuclear Materials and Energy 2.
Journal Article
34, 101446 (2023)
Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors. Nuclear Materials and Energy 3.
Journal Article
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design 4.
Journal Article
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 5.
Journal Article
190, 113522 (2023)
Ferromagnetic forces acting on the EU-DEMO divertor. Fusion Engineering and Design 6.
Journal Article
37, 101506 (2023)
Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy 7.
Journal Article
194, 113829 (2023)
Structural assessment investigations of the DEMO Divertor shielding components with reference to RCC-MRx. Fusion Engineering and Design 8.
Journal Article
262, 119453 (2023)
Bimodal structured chromium-tungsten composite as plasma-facing materials: Sinterability, mechanical properties, and deuterium retention assessment. Acta Materialia 9.
Journal Article
194, 113917 (2023)
Systems engineering procedure for requirements management of divertor system of tokamak reactors. Fusion Engineering and Design 10.
Journal Article
188, 113426 (2023)
Creep fatigue analysis of DEMO divertor components following the RCC-MRx design code. Fusion Engineering and Design 11.
Journal Article
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 12.
Journal Article
10, 116516 (2023)
Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing. Materials Research Express 13.
Journal Article
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 14.
Journal Article
194, 113866 (2023)
Analysis of the nuclear loads on Chromium monoblock divertor target for DEMO. Fusion Engineering and Design 15.
Journal Article
35, 101433 (2023)
Assessment of flow-assisted corrosion rate of copper alloy cooling tube for application in fusion reactors. Nuclear Materials and Energy 16.
Journal Article
194, 113699 (2023)
Cyclic medium heat flux testing of a WTa lattice structure on the HIVE facility. Fusion Engineering and Design 17.
Journal Article
188, 113408 (2023)
Thermofluid-dynamic assessment of the EU-DEMO divertor single-circuit cooling option. Fusion Engineering and Design 18.
Journal Article
192, 113604 (2023)
Parametric FE model for the thermal and hydraulic optimization of a Plasma Facing Component equipped with sacrificial lattice armours for First Wall limiter application in EU-DEMO fusion reactor. Fusion Engineering and Design 19.
Journal Article
187, 113375 (2023)
Dynamic structural response of DEMO divertor under electromagnetic loading. Fusion Engineering and Design 20.
Journal Article
180, 113164 (2022)
Qualification & testing of joining development for DEMO limiter component. Fusion Engineering and Design