Publications of J. H. You
All genres
Journal Article (173)
21.
Journal Article
175, 112999 (2022)
Mechanical impact of electromagnetic transients on the European DEMO divertor. Part 1: Vertical displacement event. Fusion Engineering and Design 22.
Journal Article
62, 036017 (2022)
Development and testing of an additively manufactured lattice for DEMO limiters. Nuclear Fusion 23.
Journal Article
177, 113067 (2022)
Integrated design strategy for EU-DEMO first wall protection from plasma transients. Fusion Engineering and Design 24.
Journal Article
566, 153760 (2022)
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. Journal of Nuclear Materials 25.
Journal Article
3 (4), pp. 421 - 434 (2022)
Thermomechanical Analysis of a PFC Integrating W Lattice Armour in Response to Different Plasma Scenarios Predicted in the EU-DEMO Tokamak. Journal of Nuclear Engineering 26.
Journal Article
571 (1), 153960 (2022)
Mechanical behaviour of W particulate-reinforced Cu composites: Fracture toughness and R-curves. Journal of Nuclear Materials 27.
Journal Article
62, 026045 (2022)
Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys. Nuclear Fusion 28.
Journal Article
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design 29.
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 30.
Journal Article
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 31.
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 32.
Journal Article
96, 124065 (2021)
Typology of defects in DEMO divertor target mockups. Physica Scripta 33.
Journal Article
61, 126057 (2021)
Power exhaust concepts and divertor designs for Japanese and European DEMO fusion reactors. Nuclear Fusion 34.
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 35.
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 36.
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 37.
Journal Article
169, 112661 (2021)
Structural integrity of DEMO divertor target assessed by neutron tomography. Fusion Engineering and Design 38.
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 39.
Journal Article
95, 105437 (2021)
Neutron irradiation hardening across ITER diverter tungsten armor. International Journal of Refractory Metals and Hard Materials 40.
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