Publikationen von J. H. You
Alle Typen
Zeitschriftenartikel (185)
61.
Zeitschriftenartikel
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta 62.
Zeitschriftenartikel
158, 111710 (2020)
Insulated fixation system of plasma facing components to the divertor cassette in Eurofusion-DEMO. Fusion Engineering and Design 63.
Zeitschriftenartikel
158, 111721 (2020)
Parametric design study of a substrate material for a DEMO sacrificial limiter. Fusion Engineering and Design 64.
Zeitschriftenartikel
157, 111656 (2020)
Eurofusion-DEMO Divertor – Cassette Design and Integration. Fusion Engineering and Design 65.
Zeitschriftenartikel
39, S. 146 - 147 (2020)
Tailored tungsten lattice structures for plasma-facing components in magnetic confinement fusion devices. Materials Today 66.
Zeitschriftenartikel
2020 (T171), 014015 (2020)
Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups. Physica Scripta 67.
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 68.
Zeitschriftenartikel
157, 111610 (2020)
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target. Fusion Engineering and Design 69.
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 70.
Zeitschriftenartikel
536, 152204 (2020)
Development of chromium and chromium-tungsten alloy for the plasma facing components: Application of vacuum arc melting techniques. Journal of Nuclear Materials 71.
Zeitschriftenartikel
23, 100742 (2020)
Nuclear loads and nuclear shielding performance of EU DEMO divertor: A comparative neutronics evaluation of two interim design options. Nuclear Materials and Energy 72.
Zeitschriftenartikel
154, 111510 (2020)
Stress analysis of divertor plasma-facing component designs using tungsten particle-reinforced copper composite heat sink. Fusion Engineering and Design 73.
Zeitschriftenartikel
146, Pt. B, S. 1431 - 1436 (2019)
Materials development for new high heat-flux component mock-ups for DEMO. Fusion Engineering and Design 74.
Zeitschriftenartikel
146, Pt. A, S. 701 - 704 (2019)
Neutron diffraction measurement of residual stresses in an ITER-like tungsten-monoblock type plasma-facing component. Fusion Engineering and Design 75.
Zeitschriftenartikel
146, Pt. A, S. 220 - 223 (2019)
Thermal-hydraulic optimisation of the DEMO divertor cassette body cooling circuit equipped with a liner. Fusion Engineering and Design 76.
Zeitschriftenartikel
146, Pt. B, S. 1764 - 1768 (2019)
Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios. Fusion Engineering and Design 77.
Zeitschriftenartikel
146, Pt. A, S. 870 - 873 (2019)
Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test. Fusion Engineering and Design 78.
Zeitschriftenartikel
59, 066013 (2019)
Overview of the DEMO staged design approach in Europe. Nuclear Fusion 79.
Zeitschriftenartikel
138, S. 119 - 124 (2019)
Further improvements in the structural analysis of DEMO Divertor Cassette body and design assessment according to RCC-MRx. Fusion Engineering and Design 80.
Zeitschriftenartikel
146, Pt. B, S. 1591 - 1595 (2019)
Enhancements in the structural integrity assessment of plasma facing components. Fusion Engineering and Design