Publikationen von J.-H. You
Alle Typen
Zeitschriftenartikel (176)
2023
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
Zeitschriftenartikel
571 (1), 153960 (2022)
Mechanical behaviour of W particulate-reinforced Cu composites: Fracture toughness and R-curves. Journal of Nuclear Materials
Zeitschriftenartikel
62, 026045 (2022)
Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys. Nuclear Fusion
Zeitschriftenartikel
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design
Zeitschriftenartikel
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
Zeitschriftenartikel
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design
Zeitschriftenartikel
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 2021
Zeitschriftenartikel
96, 124065 (2021)
Typology of defects in DEMO divertor target mockups. Physica Scripta
Zeitschriftenartikel
61, 126057 (2021)
Power exhaust concepts and divertor designs for Japanese and European DEMO fusion reactors. Nuclear Fusion
Zeitschriftenartikel
169, 112493 (2021)
Comparison between finite element and experimental evidences of innovative W lattice materials for sacrificial limiter applications. Fusion Engineering and Design
Zeitschriftenartikel
168, 112368 (2021)
Hydraulic assessment of an upgraded pipework arrangement for the DEMO divertor plasma facing components cooling circuit. Fusion Engineering and Design
Zeitschriftenartikel
167, 112227 (2021)
Thermal-hydraulic study of the DEMO divertor cassette body cooling circuit equipped with a liner and two reflector plates. Fusion Engineering and Design
Zeitschriftenartikel
169, 112661 (2021)
Structural integrity of DEMO divertor target assessed by neutron tomography. Fusion Engineering and Design