Publications of J.-H. You
All genres
Journal Article (176)
101.
Journal Article
122, pp. 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 102.
Journal Article
124, pp. 468 - 472 (2017)
Design options to mitigate deep cracking of tungsten armor. Fusion Engineering and Design 103.
Journal Article
57, 092007 (2017)
Development of advanced high heat flux and plasma-facing materials. Nuclear Fusion 104.
Journal Article
124, pp. 649 - 654 (2017)
Systems engineering approach for pre-conceptual design of DEMO divertor cassette. Fusion Engineering and Design 105.
Journal Article
124, pp. 655 - 658 (2017)
Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette. Fusion Engineering and Design 106.
Journal Article
124, pp. 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 107.
Journal Article
12, pp. 1308 - 1313 (2017)
Tungsten fibre-reinforced composites for advanced plasma facing components. Nuclear Materials and Energy 108.
Journal Article
124, pp. 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 109.
Journal Article
97 (17), pp. 1418 - 1435 (2017)
Berkovich nanoindentation study of monocrystalline tungsten: a crystal plasticity study of surface pile-up deformation. Philosophical Magazine 110.
Journal Article
124, pp. 364 - 370 (2017)
Progress in the initial design activities for the European DEMO divertor: Subproject "Cassette". Fusion Engineering and Design 111.
Journal Article
112, pp. 527 - 534 (2016)
Issues and strategies for DEMO in-vessel component integration. Fusion Engineering and Design 112.
Journal Article
109-111, Pt. A, pp. 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 113.
Journal Article
109-111, Pt. B, pp. 1464 - 1474 (2016)
Overview of the design approach and prioritization of R&D activities towards an EU DEMO. Fusion Engineering and Design 114.
Journal Article
109-111, Pt. A, pp. 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 115.
Journal Article
102, pp. 50 - 58 (2016)
Sweeping heat flux loads on divertor targets: Thermal benefits and structural impacts. Fusion Engineering and Design 116.
Journal Article
9, pp. 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 117.
Journal Article
113, pp. 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 118.
Journal Article
109-111, Pt. B, pp. 1067 - 1071 (2016)
Limitations of transient power loads on DEMO and analysis of mitigation techniques. Fusion Engineering and Design 119.
Journal Article
109-111, Pt. A, pp. 1046 - 1052 (2016)
Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants. Fusion Engineering and Design 120.
Journal Article
109-111, Pt. B, pp. 1598 - 1603 (2016)
Conceptual design studies for the European DEMO divertor: Rationale and first results. Fusion Engineering and Design