
Publikationen von J. H. You
Alle Typen
Zeitschriftenartikel (148)
1.
Zeitschriftenartikel
175, 112999 (2022)
Mechanical impact of electromagnetic transients on the European DEMO divertor. Part 1: Vertical displacement event. Fusion Engineering and Design 2.
Zeitschriftenartikel
62, 036017 (2022)
Development and testing of an additively manufactured lattice for DEMO limiters. Nuclear Fusion 3.
Zeitschriftenartikel
177, 113067 (2022)
Integrated design strategy for EU-DEMO first wall protection from plasma transients. Fusion Engineering and Design 4.
Zeitschriftenartikel
62, 026045 (2022)
Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys. Nuclear Fusion 5.
Zeitschriftenartikel
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design 6.
Zeitschriftenartikel
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 7.
Zeitschriftenartikel
96, 124065 (2021)
Typology of defects in DEMO divertor target mockups. Physica Scripta 8.
Zeitschriftenartikel
61, 126057 (2021)
Power exhaust concepts and divertor designs for Japanese and European DEMO fusion reactors. Nuclear Fusion 9.
Zeitschriftenartikel
169, 112493 (2021)
Comparison between finite element and experimental evidences of innovative W lattice materials for sacrificial limiter applications. Fusion Engineering and Design 10.
Zeitschriftenartikel
168, 112368 (2021)
Hydraulic assessment of an upgraded pipework arrangement for the DEMO divertor plasma facing components cooling circuit. Fusion Engineering and Design 11.
Zeitschriftenartikel
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 12.
Zeitschriftenartikel
169, 112661 (2021)
Structural integrity of DEMO divertor target assessed by neutron tomography. Fusion Engineering and Design 13.
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 14.
Zeitschriftenartikel
95, 105437 (2021)
Neutron irradiation hardening across ITER diverter tungsten armor. International Journal of Refractory Metals and Hard Materials 15.
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 16.
Zeitschriftenartikel
14 (23), 8086 (2021)
Hydraulic Characterization of the Full Scale Mock-Up of the DEMO Divertor Outer Vertical Target. Energies 17.
Zeitschriftenartikel
164, 112203 (2021)
Structural lifetime assessment for the DEMO divertor targets: Design-by-analysis approach and outstanding issues. Fusion Engineering and Design 18.
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 19.
Zeitschriftenartikel
159, 111784 (2020)
EU-DEMO divertor: Cassette design and PFCs integration at pre-conceptual stage. Fusion Engineering and Design 20.
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