Publications of J. H. You
All genres
Journal Article (185)
101.
Journal Article
13, pp. 74 - 80 (2017)
Microstructural stability of spark-plasma-sintered Wf/W composite with zirconia interface coating under high-heat-flux hydrogen beam irradiation. Nuclear Materials and Energy 102.
Journal Article
124, pp. 562 - 566 (2017)
Progress in EU-DEMO in-vessel components integration. Fusion Engineering and Design 103.
Journal Article
124, pp. 964 - 968 (2017)
Advanced materials for a damage resilient divertor concept for DEMO: Powder-metallurgical tungsten-fibre reinforced tungsten. Fusion Engineering and Design 104.
Journal Article
124, pp. 432 - 436 (2017)
ITER-like divertor target for DEMO: Design study and fabrication test. Fusion Engineering and Design 105.
Journal Article
124, pp. 415 - 419 (2017)
Thermal-hydraulic behaviour of the DEMO divertor plasma facing components cooling circuit. Fusion Engineering and Design 106.
Journal Article
124, pp. 437 - 441 (2017)
Analysis of steady state thermal-hydraulic behaviour of the DEMO divertor cassette body cooling circuit. Fusion Engineering and Design 107.
Journal Article
124, pp. 628 - 632 (2017)
Structural analysis of DEMO divertor cassette body and design study based on RCC-MRx. Fusion Engineering and Design 108.
Journal Article
T170, 014042 (2017)
The development and testing of the thermal break divertor monoblock target design delivering 20 MW m-2 heat load capability. Physica Scripta 109.
Journal Article
T170, 014015 (2017)
Quantitative thermal imperfection definition using non-destructive infrared thermography on an advanced DEMO divertor concept. Physica Scripta 110.
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 111.
Journal Article
124, pp. 468 - 472 (2017)
Design options to mitigate deep cracking of tungsten armor. Fusion Engineering and Design 112.
Journal Article
57, 092007 (2017)
Development of advanced high heat flux and plasma-facing materials. Nuclear Fusion 113.
Journal Article
124, pp. 649 - 654 (2017)
Systems engineering approach for pre-conceptual design of DEMO divertor cassette. Fusion Engineering and Design 114.
Journal Article
124, pp. 655 - 658 (2017)
Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette. Fusion Engineering and Design 115.
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 116.
Journal Article
12, pp. 1308 - 1313 (2017)
Tungsten fibre-reinforced composites for advanced plasma facing components. Nuclear Materials and Energy 117.
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 118.
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 119.
Journal Article
124, pp. 364 - 370 (2017)
Progress in the initial design activities for the European DEMO divertor: Subproject "Cassette". Fusion Engineering and Design 120.
Journal Article
112, pp. 527 - 534 (2016)
Issues and strategies for DEMO in-vessel component integration. Fusion Engineering and Design