Publications of J.-H. You
All genres
Journal Article (176)
2021
Journal Article
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
Journal Article
95, 105437 (2021)
Neutron irradiation hardening across ITER diverter tungsten armor. International Journal of Refractory Metals and Hard Materials
Journal Article
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
Journal Article
14 (23), 8086 (2021)
Hydraulic Characterization of the Full Scale Mock-Up of the DEMO Divertor Outer Vertical Target. Energies
Journal Article
164, 112203 (2021)
Structural lifetime assessment for the DEMO divertor targets: Design-by-analysis approach and outstanding issues. Fusion Engineering and Design
Journal Article
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
Journal Article
159, 111784 (2020)
EU-DEMO divertor: Cassette design and PFCs integration at pre-conceptual stage. Fusion Engineering and Design
Journal Article
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
Journal Article
156, 111613 (2020)
On the thermal-hydraulic performances of the DEMO divertor cassette body cooling circuit equipped with a liner. Fusion Engineering and Design
Journal Article
154, 111497 (2020)
The design and optimisation of a monoblock divertor target for DEMO using thermal break interlayer. Fusion Engineering and Design
Journal Article
160, 111831 (2020)
Towards reliable design-by-analysis for divertor plasma facing components – Guidelines for inelastic assessment (part 2: irradiated). Fusion Engineering and Design
Journal Article
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta
Journal Article
158, 111710 (2020)
Insulated fixation system of plasma facing components to the divertor cassette in Eurofusion-DEMO. Fusion Engineering and Design
Journal Article
158, 111721 (2020)
Parametric design study of a substrate material for a DEMO sacrificial limiter. Fusion Engineering and Design
Journal Article
157, 111656 (2020)
Eurofusion-DEMO Divertor – Cassette Design and Integration. Fusion Engineering and Design
Journal Article
39, pp. 146 - 147 (2020)
Tailored tungsten lattice structures for plasma-facing components in magnetic confinement fusion devices. Materials Today
Journal Article
2020 (T171), 014015 (2020)
Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups. Physica Scripta
Journal Article
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
Journal Article
157, 111610 (2020)
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target. Fusion Engineering and Design
Journal Article
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