Publikationen von J. H. You
Alle Typen
Zeitschriftenartikel (177)
101.
Zeitschriftenartikel
T170, 014015 (2017)
Quantitative thermal imperfection definition using non-destructive infrared thermography on an advanced DEMO divertor concept. Physica Scripta 102.
Zeitschriftenartikel
122, S. 124 - 130 (2017)
Fracture mechanical analysis of a tungsten monoblock-type plasma-facing component without macroscopic interlayer for high-heat-flux divertor target. Fusion Engineering and Design 103.
Zeitschriftenartikel
124, S. 468 - 472 (2017)
Design options to mitigate deep cracking of tungsten armor. Fusion Engineering and Design 104.
Zeitschriftenartikel
57, 092007 (2017)
Development of advanced high heat flux and plasma-facing materials. Nuclear Fusion 105.
Zeitschriftenartikel
124, S. 649 - 654 (2017)
Systems engineering approach for pre-conceptual design of DEMO divertor cassette. Fusion Engineering and Design 106.
Zeitschriftenartikel
124, S. 655 - 658 (2017)
Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette. Fusion Engineering and Design 107.
Zeitschriftenartikel
124, S. 455 - 459 (2017)
Melt infiltrated tungsten-copper composites as advanced heat sink materials for plasma facing components of future nuclear fusion devices. Fusion Engineering and Design 108.
Zeitschriftenartikel
12, S. 1308 - 1313 (2017)
Tungsten fibre-reinforced composites for advanced plasma facing components. Nuclear Materials and Energy 109.
Zeitschriftenartikel
124, S. 338 - 343 (2017)
Status on the W monoblock type high heat flux target with graded interlayer for application to DEMO divertor. Fusion Engineering and Design 110.
Zeitschriftenartikel
97 (17), S. 1418 - 1435 (2017)
Berkovich nanoindentation study of monocrystalline tungsten: a crystal plasticity study of surface pile-up deformation. Philosophical Magazine 111.
Zeitschriftenartikel
124, S. 364 - 370 (2017)
Progress in the initial design activities for the European DEMO divertor: Subproject "Cassette". Fusion Engineering and Design 112.
Zeitschriftenartikel
112, S. 527 - 534 (2016)
Issues and strategies for DEMO in-vessel component integration. Fusion Engineering and Design 113.
Zeitschriftenartikel
109-111, Pt. A, S. 917 - 924 (2016)
Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components. Fusion Engineering and Design 114.
Zeitschriftenartikel
109-111, Pt. B, S. 1464 - 1474 (2016)
Overview of the design approach and prioritization of R&D activities towards an EU DEMO. Fusion Engineering and Design 115.
Zeitschriftenartikel
109-111, Pt. A, S. 47 - 51 (2016)
Structural design of DEMO Divertor Cassette Body: provisional FEM analysis and introductive application of RCC-MRx design rules. Fusion Engineering and Design 116.
Zeitschriftenartikel
102, S. 50 - 58 (2016)
Sweeping heat flux loads on divertor targets: Thermal benefits and structural impacts. Fusion Engineering and Design 117.
Zeitschriftenartikel
9, S. 598 - 603 (2016)
Cracking behavior of tungsten armor under ELM-like thermal shockloads II: A revised prediction for crack appearance map. Nuclear Materials and Energy 118.
Zeitschriftenartikel
113, S. 162 - 170 (2016)
Structural impact of armor monoblock dimensions on the failure behavior of ITER-type divertor target components: Size matters. Fusion Engineering and Design 119.
Zeitschriftenartikel
109-111, Pt. B, S. 1067 - 1071 (2016)
Limitations of transient power loads on DEMO and analysis of mitigation techniques. Fusion Engineering and Design 120.
Zeitschriftenartikel
109-111, Pt. A, S. 1046 - 1052 (2016)
Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants. Fusion Engineering and Design