Publikationen von J.-H. You
Alle Typen
Zeitschriftenartikel (176)
2021
Zeitschriftenartikel
169, 112428 (2021)
Neutronics analysis and activation calculation for tungsten used in the DEMO divertor targets: A comparative study between the effects of WCLL and HCPB blanket, different W compositions and chromium. Fusion Engineering and Design
Zeitschriftenartikel
95, 105437 (2021)
Neutron irradiation hardening across ITER diverter tungsten armor. International Journal of Refractory Metals and Hard Materials
Zeitschriftenartikel
554, 153086 (2021)
Irradiation embrittlement in pure chromium and chromium-tungsten alloy in a view of their potential application for fusion plasma facing components. Journal of Nuclear Materials
Zeitschriftenartikel
14 (23), 8086 (2021)
Hydraulic Characterization of the Full Scale Mock-Up of the DEMO Divertor Outer Vertical Target. Energies
Zeitschriftenartikel
164, 112203 (2021)
Structural lifetime assessment for the DEMO divertor targets: Design-by-analysis approach and outstanding issues. Fusion Engineering and Design
Zeitschriftenartikel
544, 152670 (2021)
High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign. Journal of Nuclear Materials 2020
Zeitschriftenartikel
159, 111784 (2020)
EU-DEMO divertor: Cassette design and PFCs integration at pre-conceptual stage. Fusion Engineering and Design
Zeitschriftenartikel
161, 111919 (2020)
On the numerical assessment of the thermal-hydraulic operating map of the DEMO Divertor Plasma Facing Components cooling circuit. Fusion Engineering and Design
Zeitschriftenartikel
156, 111613 (2020)
On the thermal-hydraulic performances of the DEMO divertor cassette body cooling circuit equipped with a liner. Fusion Engineering and Design
Zeitschriftenartikel
154, 111497 (2020)
The design and optimisation of a monoblock divertor target for DEMO using thermal break interlayer. Fusion Engineering and Design
Zeitschriftenartikel
160, 111831 (2020)
Towards reliable design-by-analysis for divertor plasma facing components – Guidelines for inelastic assessment (part 2: irradiated). Fusion Engineering and Design
Zeitschriftenartikel
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta
Zeitschriftenartikel
158, 111710 (2020)
Insulated fixation system of plasma facing components to the divertor cassette in Eurofusion-DEMO. Fusion Engineering and Design
Zeitschriftenartikel
158, 111721 (2020)
Parametric design study of a substrate material for a DEMO sacrificial limiter. Fusion Engineering and Design
Zeitschriftenartikel
157, 111656 (2020)
Eurofusion-DEMO Divertor – Cassette Design and Integration. Fusion Engineering and Design
Zeitschriftenartikel
39, S. 146 - 147 (2020)
Tailored tungsten lattice structures for plasma-facing components in magnetic confinement fusion devices. Materials Today
Zeitschriftenartikel
2020 (T171), 014015 (2020)
Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups. Physica Scripta
Zeitschriftenartikel
155, 111730 (2020)
Nuclear analyses for the design of the ITER-like plasma facing components vertical targets of the DEMO divertor. Fusion Engineering and Design
Zeitschriftenartikel
157, 111610 (2020)
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target. Fusion Engineering and Design
Zeitschriftenartikel
161, 111886 (2020)
Ultrasonic test results before and after high heat flux testing on W-monoblock mock-ups of EU-DEMO vertical target. Fusion Engineering and Design