Publikationen von J. H. You
Alle Typen
Zeitschriftenartikel (176)
121.
Zeitschriftenartikel
9, S. 171 - 176 (2016)
European DEMO divertor target: Operational requirements and material-design interface. Nuclear Materials and Energy 122.
Zeitschriftenartikel
98-99, S. 1263 - 1266 (2015)
Design study of ITER-like divertor target for DEMO. Fusion Engineering and Design 123.
Zeitschriftenartikel
98-99, S. 1310 - 1313 (2015)
Results of high heat flux testing of W/CuCrZr multilayer composites with percolating microstructure for plasma-facing components. Fusion Engineering and Design 124.
Zeitschriftenartikel
135, S. 64 - 80 (2015)
Experimental and computational study of damage behavior of tungsten under high energy electron beam irradiation. Engineering Fracture Mechanics 125.
Zeitschriftenartikel
457, S. 256 - 265 (2015)
Influence of heat flux loading patterns on the surface cracking features of tungsten armor under ELM-like thermal shocks. Journal of Nuclear Materials 126.
Zeitschriftenartikel
2, S. 1 - 11 (2015)
Cracking behavior of tungsten armor under ELM-like thermal shock loads: A computational study. Nuclear Materials and Energy 127.
Zeitschriftenartikel
90, S. 88 - 96 (2015)
Low cycle fatigue behavior of ITER-like divertor target under DEMO-relevant operation conditions. Fusion Engineering and Design 128.
Zeitschriftenartikel
465, S. 702 - 709 (2015)
Mechanics of tungsten blistering II: Analytical treatment and fracture mechanical assessment. Journal of Nuclear Materials 129.
Zeitschriftenartikel
101, S. 1 - 8 (2015)
Interpretation of the deep cracking phenomenon of tungsten monoblock targets observed in high-heat-flux fatigue tests at 20 MW/m2. Fusion Engineering and Design 130.
Zeitschriftenartikel
96-97, S. 361 - 364 (2015)
European roadmap to the realization of fusion energy: Mission for solution on heat-exhaust systems. Fusion Engineering and Design 131.
Zeitschriftenartikel
55, 113026 (2015)
A review on two previous divertor target concepts for DEMO: mutual impact between structural design requirements and materials performance. Nuclear Fusion 132.
Zeitschriftenartikel
5, S. 7 - 18 (2015)
Copper matrix composites as heat sink materials for water-cooled divertor target. Nuclear Materials and Energy 133.
Zeitschriftenartikel
89 (11), S. 2716 - 2725 (2014)
Fracture mechanical analysis of tungsten armor failure of a water-cooled divertor target. Fusion Engineering and Design 134.
Zeitschriftenartikel
T159, 014031 (2014)
Enhanced toughness and stable crack propagation in a novel tungsten fibre-reinforced tungsten composite produced by chemical vapour infiltration. Physica Scripta 135.
Zeitschriftenartikel
49 (10), S. 3705 - 3715 (2014)
Plastic material parameters and plastic anisotropy of tungsten single crystal: a spherical micro-indentation study. Journal of Materials Science 136.
Zeitschriftenartikel
89 (4), S. 294 - 301 (2014)
Damage and fatigue crack growth of Eurofer steel first wall mock-up under cyclic heat flux loads. Part 2: Finite element analysis of damage evolution. Fusion Engineering and Design 137.
Zeitschriftenartikel
89 (4), S. 284 - 288 (2014)
Damage and fatigue crack growth of Eurofer steel first wall mock-up under cyclic heat flux loads. Part 1: Electron beam irradiation tests. Fusion Engineering and Design 138.
Zeitschriftenartikel
84, S. 318 - 326 (2014)
Mechanism of plastic damage and fracture of a particulate tungsten-reinforced copper composite: A microstructure-based finite element study. Computational Materials Science 139.
Zeitschriftenartikel
440 (1-3), S. 272 - 277 (2013)
Strength and conductivity of unidirectional copper composites reinforced by continuous SiC fibers. Journal of Nuclear Materials 140.
Zeitschriftenartikel
443 (1-3), S. 386 - 392 (2013)
Impact of long-term thermal exposure on a SiC fiber-reinforced copper matrix composite. Journal of Nuclear Materials