Publications of J.-H. You
All genres
Journal Article (186)
2022
Journal Article
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design
Journal Article
33, 101307 (2022)
High-heat-flux performance limit of tungsten monoblock targets: Impact on the armor materials and implications for power exhaust capacity. Nuclear Materials and Energy
Journal Article
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design
Journal Article
184, 113305 (2022)
Crack formation in the tungsten armour of divertor targets under high heat flux loads: A computational fracture mechanics study. Fusion Engineering and Design 2021
Journal Article
96, 124065 (2021)
Typology of defects in DEMO divertor target mockups. Physica Scripta
Journal Article
61, 126057 (2021)
Power exhaust concepts and divertor designs for Japanese and European DEMO fusion reactors. Nuclear Fusion
Journal Article
169, 112493 (2021)
Comparison between finite element and experimental evidences of innovative W lattice materials for sacrificial limiter applications. Fusion Engineering and Design
Journal Article
168, 112368 (2021)
Hydraulic assessment of an upgraded pipework arrangement for the DEMO divertor plasma facing components cooling circuit. Fusion Engineering and Design
Journal Article
167, 112227 (2021)
Thermal-hydraulic study of the DEMO divertor cassette body cooling circuit equipped with a liner and two reflector plates. Fusion Engineering and Design
Journal Article
169, 112661 (2021)
Structural integrity of DEMO divertor target assessed by neutron tomography. Fusion Engineering and Design
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