Publikationen von J.-H. You
Alle Typen
Zeitschriftenartikel (187)
21.
Zeitschriftenartikel
37, 101506 (2023)
Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy 22.
Zeitschriftenartikel
194, 113829 (2023)
Structural assessment investigations of the DEMO Divertor shielding components with reference to RCC-MRx. Fusion Engineering and Design 23.
Zeitschriftenartikel
194, 113917 (2023)
Systems engineering procedure for requirements management of divertor system of tokamak reactors. Fusion Engineering and Design 24.
Zeitschriftenartikel
188, 113426 (2023)
Creep fatigue analysis of DEMO divertor components following the RCC-MRx design code. Fusion Engineering and Design 25.
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 26.
Zeitschriftenartikel
10, 116516 (2023)
Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing. Materials Research Express 27.
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 28.
Zeitschriftenartikel
194, 113866 (2023)
Analysis of the nuclear loads on Chromium monoblock divertor target for DEMO. Fusion Engineering and Design 29.
Zeitschriftenartikel
35, 101433 (2023)
Assessment of flow-assisted corrosion rate of copper alloy cooling tube for application in fusion reactors. Nuclear Materials and Energy 30.
Zeitschriftenartikel
194, 113699 (2023)
Cyclic medium heat flux testing of a WTa lattice structure on the HIVE facility. Fusion Engineering and Design 31.
Zeitschriftenartikel
188, 113408 (2023)
Thermofluid-dynamic assessment of the EU-DEMO divertor single-circuit cooling option. Fusion Engineering and Design 32.
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 33.
Zeitschriftenartikel
187, 113375 (2023)
Dynamic structural response of DEMO divertor under electromagnetic loading. Fusion Engineering and Design 34.
Zeitschriftenartikel
180, 113164 (2022)
Qualification & testing of joining development for DEMO limiter component. Fusion Engineering and Design 35.
Zeitschriftenartikel
175, 112999 (2022)
Mechanical impact of electromagnetic transients on the European DEMO divertor. Part 1: Vertical displacement event. Fusion Engineering and Design 36.
Zeitschriftenartikel
62, 036017 (2022)
Development and testing of an additively manufactured lattice for DEMO limiters. Nuclear Fusion 37.
Zeitschriftenartikel
177, 113067 (2022)
Integrated design strategy for EU-DEMO first wall protection from plasma transients. Fusion Engineering and Design 38.
Zeitschriftenartikel
566, 153760 (2022)
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. Journal of Nuclear Materials 39.
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 40.
Zeitschriftenartikel
571 (1), 153960 (2022)
Mechanical behaviour of W particulate-reinforced Cu composites: Fracture toughness and R-curves. Journal of Nuclear Materials