Publications of J.-H. You
All genres
Journal Article (186)
2023
Journal Article
194, 113829 (2023)
Structural assessment investigations of the DEMO Divertor shielding components with reference to RCC-MRx. Fusion Engineering and Design
Journal Article
194, 113917 (2023)
Systems engineering procedure for requirements management of divertor system of tokamak reactors. Fusion Engineering and Design
Journal Article
188, 113426 (2023)
Creep fatigue analysis of DEMO divertor components following the RCC-MRx design code. Fusion Engineering and Design
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
Journal Article
10, 116516 (2023)
Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing. Materials Research Express
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
Journal Article
194, 113866 (2023)
Analysis of the nuclear loads on Chromium monoblock divertor target for DEMO. Fusion Engineering and Design
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
Journal Article
194, 113699 (2023)
Cyclic medium heat flux testing of a WTa lattice structure on the HIVE facility. Fusion Engineering and Design
Journal Article
188, 113408 (2023)
Thermofluid-dynamic assessment of the EU-DEMO divertor single-circuit cooling option. Fusion Engineering and Design
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
Journal Article
187, 113375 (2023)
Dynamic structural response of DEMO divertor under electromagnetic loading. Fusion Engineering and Design 2022
Journal Article
180, 113164 (2022)
Qualification & testing of joining development for DEMO limiter component. Fusion Engineering and Design
Journal Article
175, 112999 (2022)
Mechanical impact of electromagnetic transients on the European DEMO divertor. Part 1: Vertical displacement event. Fusion Engineering and Design
Journal Article
62, 036017 (2022)
Development and testing of an additively manufactured lattice for DEMO limiters. Nuclear Fusion
Journal Article
177, 113067 (2022)
Integrated design strategy for EU-DEMO first wall protection from plasma transients. Fusion Engineering and Design
Journal Article
566, 153760 (2022)
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. Journal of Nuclear Materials
Journal Article
3 (4), pp. 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
Journal Article
571 (1), 153960 (2022)
Mechanical behaviour of W particulate-reinforced Cu composites: Fracture toughness and R-curves. Journal of Nuclear Materials
Journal Article
62, 026045 (2022)
Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys. Nuclear Fusion