Publikationen von J. H. You
Alle Typen
Zeitschriftenartikel (176)
81.
Zeitschriftenartikel
136, Pt. B, S. 1588 - 1592 (2018)
Computational thermofluid-dynamic analysis of DEMO divertor cassette body cooling circuit. Fusion Engineering and Design 82.
Zeitschriftenartikel
136, Pt. A, S. 729 - 741 (2018)
DEMO design activity in Europe: Progress and updates. Fusion Engineering and Design 83.
Zeitschriftenartikel
135, Part A, S. 154 - 164 (2018)
A hybrid analysis procedure enabling elastic design rule assessment of monoblock-type divertor components. Fusion Engineering and Design 84.
Zeitschriftenartikel
200, S. 555 - 564 (2018)
Cyclic plastic behavior of unidirectional SiC fibre-reinforced copper composites under uniaxial loads: An experimental and computational study. Composite Structures 85.
Zeitschriftenartikel
14, S. 1 - 7 (2018)
Structural impact of creep in tungsten monoblock divertor target at 20 MW/m2. Nuclear Materials and Energy 86.
Zeitschriftenartikel
16, S. 163 - 167 (2018)
The effects of heat treatment at temperatures of 1100 °C to 1300 °C on the tensile properties of high-strength drawn tungsten fibres. Nuclear Materials and Energy 87.
Zeitschriftenartikel
15, S. 1 - 12 (2018)
Crack bridging in as-fabricated and embrittled tungsten single fibre-reinforced tungsten composites shown by a novel in-situ high energy synchrotron tomography bending test. Nuclear Materials and Energy 88.
Zeitschriftenartikel
498, S. 468 - 475 (2018)
The thermo-mechanical behaviour of W-Cu metal matrix composites for fusion heat sink applications: The influence of the Cu content. Journal of Nuclear Materials 89.
Zeitschriftenartikel
712, S. 738 - 746 (2018)
Evolution of mechanical performance with temperature of W/Cu and W/CuCrZr composites for fusion heat sink applications. Materials Science and Engineering A: Structural Materials Properties Microstructure and Processing 90.
Zeitschriftenartikel
136, Pt. B, S. 1593 - 1596 (2018)
Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO. Fusion Engineering and Design 91.
Zeitschriftenartikel
16, S. 1 - 11 (2018)
European divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy 92.
Zeitschriftenartikel
13, S. 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 93.
Zeitschriftenartikel
124, S. 562 - 566 (2017)
Progress in EU-DEMO in-vessel components integration. Fusion Engineering and Design 94.
Zeitschriftenartikel
124, S. 964 - 968 (2017)
Advanced materials for a damage resilient divertor concept for DEMO: Powder-metallurgical tungsten-fibre reinforced tungsten. Fusion Engineering and Design 95.
Zeitschriftenartikel
124, S. 432 - 436 (2017)
ITER-like divertor target for DEMO: Design study and fabrication test. Fusion Engineering and Design 96.
Zeitschriftenartikel
124, S. 415 - 419 (2017)
Thermal-hydraulic behaviour of the DEMO divertor plasma facing components cooling circuit. Fusion Engineering and Design 97.
Zeitschriftenartikel
124, S. 437 - 441 (2017)
Analysis of steady state thermal-hydraulic behaviour of the DEMO divertor cassette body cooling circuit. Fusion Engineering and Design 98.
Zeitschriftenartikel
124, S. 628 - 632 (2017)
Structural analysis of DEMO divertor cassette body and design study based on RCC-MRx. Fusion Engineering and Design 99.
Zeitschriftenartikel
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 100.
Zeitschriftenartikel
T170, 014015 (2017)
Quantitative thermal imperfection definition using non-destructive infrared thermography on an advanced DEMO divertor concept. Physica Scripta