Publications of J. H. You
All genres
Journal Article (182)
21.
Journal Article
10, 116516 (2023)
Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing. Materials Research Express 22.
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 23.
Journal Article
194, 113866 (2023)
Analysis of the nuclear loads on Chromium monoblock divertor target for DEMO. Fusion Engineering and Design 24.
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 25.
Journal Article
194, 113699 (2023)
Cyclic medium heat flux testing of a WTa lattice structure on the HIVE facility. Fusion Engineering and Design 26.
Journal Article
188, 113408 (2023)
Thermofluid-dynamic assessment of the EU-DEMO divertor single-circuit cooling option. Fusion Engineering and Design 27.
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 28.
Journal Article
187, 113375 (2023)
Dynamic structural response of DEMO divertor under electromagnetic loading. Fusion Engineering and Design 29.
Journal Article
180, 113164 (2022)
Qualification & testing of joining development for DEMO limiter component. Fusion Engineering and Design 30.
Journal Article
175, 112999 (2022)
Mechanical impact of electromagnetic transients on the European DEMO divertor. Part 1: Vertical displacement event. Fusion Engineering and Design 31.
Journal Article
62, 036017 (2022)
Development and testing of an additively manufactured lattice for DEMO limiters. Nuclear Fusion 32.
Journal Article
177, 113067 (2022)
Integrated design strategy for EU-DEMO first wall protection from plasma transients. Fusion Engineering and Design 33.
Journal Article
566, 153760 (2022)
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. Journal of Nuclear Materials 34.
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 35.
Journal Article
571 (1), 153960 (2022)
Mechanical behaviour of W particulate-reinforced Cu composites: Fracture toughness and R-curves. Journal of Nuclear Materials 36.
Journal Article
62, 026045 (2022)
Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys. Nuclear Fusion 37.
Journal Article
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design 38.
Journal Article
33, 101307 (2022)
High-heat-flux performance limit of tungsten monoblock targets: Impact on the armor materials and implications for power exhaust capacity. Nuclear Materials and Energy 39.
Journal Article
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 40.
Journal Article
184, 113305 (2022)
Crack formation in the tungsten armour of divertor targets under high heat flux loads: A computational fracture mechanics study. Fusion Engineering and Design