Publikationen von J.-H. You
Alle Typen
Zeitschriftenartikel (176)
61.
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 62.
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 63.
Zeitschriftenartikel
154, 111510 (2020)
Stress analysis of divertor plasma-facing component designs using tungsten particle-reinforced copper composite heat sink. Fusion Engineering and Design 64.
Zeitschriftenartikel
146, Pt. B, S. 1431 - 1436 (2019)
Materials development for new high heat-flux component mock-ups for DEMO. Fusion Engineering and Design 65.
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 66.
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 67.
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 68.
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 69.
Zeitschriftenartikel
59, 066013 (2019)
Overview of the DEMO staged design approach in Europe. Nuclear Fusion 70.
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 71.
Zeitschriftenartikel
146, Pt. B, S. 1591 - 1595 (2019)
Enhancements in the structural integrity assessment of plasma facing components. Fusion Engineering and Design 72.
Zeitschriftenartikel
147, 111234 (2019)
Towards reliable design-by-analysis for divertor plasma facing components – Guidelines for inelastic assessment (part 1: Unirradiated). Fusion Engineering and Design 73.
Zeitschriftenartikel
146, Pt. A, S. 216 - 219 (2019)
Progress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design 74.
Zeitschriftenartikel
146, Pt. B, S. 1657 - 1660 (2019)
High heat flux test results for a thermal break DEMO divertor target and subsequent design and manufacture development. Fusion Engineering and Design 75.
Zeitschriftenartikel
146, Pt. A, S. 942 - 945 (2019)
Progress in the pre-conceptual CAD engineering of European DEMO divertor cassette. Fusion Engineering and Design 76.
Zeitschriftenartikel
146, Pt. B, S. 1610 - 1614 (2019)
Structural verification and manufacturing procedures of the cooling system, for DEMO divertor target (OVT). Fusion Engineering and Design 77.
Zeitschriftenartikel
146, Pt. A, S. 858 - 861 (2019)
Performance assessment of high heat flux W monoblock type target using thin graded and copper interlayers for application to DEMO divertor. Fusion Engineering and Design 78.
Zeitschriftenartikel
136, Pt. A, S. 1214 - 1220 (2018)
Plasma exhaust and divertor studies in Japan and Europe broader approach, DEMO design activity. Fusion Engineering and Design 79.
Zeitschriftenartikel
136, Pt. A, S. 558 - 562 (2018)
FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO. Fusion Engineering and Design 80.
Zeitschriftenartikel
136, Pt. B, S. 1438 - 1443 (2018)
On the thermal-hydraulic optimization of DEMO divertor plasma facing components cooling circuit. Fusion Engineering and Design