Publikationen von J.-H. You
Alle Typen
Zeitschriftenartikel (168)
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
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
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
Zeitschriftenartikel
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
Zeitschriftenartikel
187, 113375 (2023)
Dynamic structural response of DEMO divertor under electromagnetic loading. Fusion Engineering and Design 2022
Zeitschriftenartikel
180, 113164 (2022)
Qualification & testing of joining development for DEMO limiter component. Fusion Engineering and Design
Zeitschriftenartikel
175, 112999 (2022)
Mechanical impact of electromagnetic transients on the European DEMO divertor. Part 1: Vertical displacement event. Fusion Engineering and Design
Zeitschriftenartikel
62, 036017 (2022)
Development and testing of an additively manufactured lattice for DEMO limiters. Nuclear Fusion
Zeitschriftenartikel
177, 113067 (2022)
Integrated design strategy for EU-DEMO first wall protection from plasma transients. Fusion Engineering and Design
Zeitschriftenartikel
566, 153760 (2022)
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. Journal of Nuclear Materials
Zeitschriftenartikel
3 (4), S. 421 - 434 (2022)
Thermomechanical Analysis of a PFC Integrating W Lattice Armour in Response to Different Plasma Scenarios Predicted in the EU-DEMO Tokamak. Journal of Nuclear Engineering