Publikationen von J. H. You
Alle Typen
Zeitschriftenartikel (173)
21.
Zeitschriftenartikel
175, 112999 (2022)
Mechanical impact of electromagnetic transients on the European DEMO divertor. Part 1: Vertical displacement event. Fusion Engineering and Design 22.
Zeitschriftenartikel
62, 036017 (2022)
Development and testing of an additively manufactured lattice for DEMO limiters. Nuclear Fusion 23.
Zeitschriftenartikel
177, 113067 (2022)
Integrated design strategy for EU-DEMO first wall protection from plasma transients. Fusion Engineering and Design 24.
Zeitschriftenartikel
566, 153760 (2022)
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. Journal of Nuclear Materials 25.
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 26.
Zeitschriftenartikel
571 (1), 153960 (2022)
Mechanical behaviour of W particulate-reinforced Cu composites: Fracture toughness and R-curves. Journal of Nuclear Materials 27.
Zeitschriftenartikel
62, 026045 (2022)
Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys. Nuclear Fusion 28.
Zeitschriftenartikel
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design 29.
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 30.
Zeitschriftenartikel
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 31.
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 32.
Zeitschriftenartikel
96, 124065 (2021)
Typology of defects in DEMO divertor target mockups. Physica Scripta 33.
Zeitschriftenartikel
61, 126057 (2021)
Power exhaust concepts and divertor designs for Japanese and European DEMO fusion reactors. Nuclear Fusion 34.
Zeitschriftenartikel
169, 112493 (2021)
Comparison between finite element and experimental evidences of innovative W lattice materials for sacrificial limiter applications. Fusion Engineering and Design 35.
Zeitschriftenartikel
168, 112368 (2021)
Hydraulic assessment of an upgraded pipework arrangement for the DEMO divertor plasma facing components cooling circuit. Fusion Engineering and Design 36.
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 37.
Zeitschriftenartikel
169, 112661 (2021)
Structural integrity of DEMO divertor target assessed by neutron tomography. Fusion Engineering and Design 38.
Zeitschriftenartikel
169, 112428 (2021)
Neutronics analysis and activation calculation for tungsten used in the DEMO divertor targets: A comparative study between the effects of WCLL and HCPB blanket, different W compositions and chromium. Fusion Engineering and Design 39.
Zeitschriftenartikel
95, 105437 (2021)
Neutron irradiation hardening across ITER diverter tungsten armor. International Journal of Refractory Metals and Hard Materials 40.
Zeitschriftenartikel
554, 153086 (2021)
Irradiation embrittlement in pure chromium and chromium-tungsten alloy in a view of their potential application for fusion plasma facing components. Journal of Nuclear Materials