Publikationen von J.-H. You
Alle Typen
Zeitschriftenartikel (182)
2025
Zeitschriftenartikel
65, 026041 (2025)
Strain mapping and defects inspection of divertor targets by Bragg edge neutron imaging and neutron tomography. Nuclear Fusion
Zeitschriftenartikel
211, 114809 (2025)
Assessment of dynamic response of a DEMO divertor under electromagnetic impact loads. Part 1: A computational methodology for a cost-effective analysis. Fusion Engineering and Design 2024
Zeitschriftenartikel
201, 114268 (2024)
Galvanic process for Cu-infiltration of W fibre-reinforced heat sinks. Fusion Engineering and Design
Zeitschriftenartikel
262, 119453 (2024)
Bimodal structured chromium-tungsten composite as plasma-facing materials: Sinterability, mechanical properties, and deuterium retention assessment. Acta Materialia
Zeitschriftenartikel
204, 114514 (2024)
Brazing alloys characterization for EU-DEMO Divertor Target. Fusion Engineering and Design
Zeitschriftenartikel
203, 114467 (2024)
Selection of EU-DEMO divertor operating conditions: water cooling thermal-hydraulic parameters and power exhaust capabilities. Fusion Engineering and Design
Zeitschriftenartikel
39, 101687 (2024)
Long-pulse high heat flux testing of tungsten monoblock target mock-ups for investigation of creep fatigue interaction. Nuclear Materials and Energy
Zeitschriftenartikel
200, 114240 (2024)
Hypothetical porous medium concept as a virtual swirl tape: A novel modelling technique towards efficient CFD simulation of swirl tape cooling pipe. Fusion Engineering and Design
Zeitschriftenartikel
38, 101591 (2024)
Progress in the development of industrial scale tungsten fibre-reinforced composite materials. Nuclear Materials and Energy
Zeitschriftenartikel
41, 101769 (2024)
Enhanced thermomechanical fatigue resistance in W10Re alloys: Microstructural and surface engineering approaches. Nuclear Materials and Energy
Zeitschriftenartikel
47 (10), S. 3813 - 3831 (2024)
Multiaxial fatigue rule applied to disc specimens with variable thickness subjected to an equibiaxial stress state. Fatigue and Fracture of Engineering Materials and Structures 2023
Zeitschriftenartikel
34, 101446 (2023)
Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors. Nuclear Materials and Energy
Zeitschriftenartikel
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design
Zeitschriftenartikel
191, 113742 (2023)
Pre-conceptual design of a PFC equipped with a W lattice armour for first wall limiters in the EU-DEMO fusion reactor. Fusion Engineering and Design
Zeitschriftenartikel
190, 113522 (2023)
Ferromagnetic forces acting on the EU-DEMO divertor. Fusion Engineering and Design
Zeitschriftenartikel
37, 101506 (2023)
Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy
Zeitschriftenartikel
194, 113829 (2023)
Structural assessment investigations of the DEMO Divertor shielding components with reference to RCC-MRx. Fusion Engineering and Design
Zeitschriftenartikel
194, 113917 (2023)
Systems engineering procedure for requirements management of divertor system of tokamak reactors. Fusion Engineering and Design
Zeitschriftenartikel
188, 113426 (2023)
Creep fatigue analysis of DEMO divertor components following the RCC-MRx design code. Fusion Engineering and Design
Zeitschriftenartikel
36, 101465 (2023)
Microstructural evolution of tungsten under thermal loads: A comparative study between cyclic high heat flux loading and isochronous furnace heating. Nuclear Materials and Energy