Publications of J.-H. You
All genres
Journal Article (150)
141.
Journal Article
348, pp. 94 - 101 (2006)
Determination of elastic modulus and residual stress of plasma-sprayed tungsten coating on steel substrate. Journal of Nuclear Materials 142.
Journal Article
336, pp. 97 - 109 (2005)
Design feasibility study of a divertor component reinforced with fibrous metal matrix composite laminate. Journal of Nuclear Materials 143.
Journal Article
329-333, pp. 702 - 705 (2004)
Structural analysis of a plasma-facing component reinforced with fibrous metal matrix composite laminate. Journal of Nuclear Materials 144.
Journal Article
39, pp. 2121 - 2130 (2004)
Dual scale non-linear stress analysis of a fibrous metal matrix composite. Journal of Materials Science 145.
Journal Article
65 (4), pp. 483 - 492 (2003)
Thermal stress intensity factor of interfacial cracks of a plasma facing component under high heat flux loading. Fusion Engineering and Design 146.
Journal Article
344 (1-2), pp. 201 - 208 (2003)
A comparative study on two elasto-plastic mean field methods. Materials Science and Engineering A: Structural Materials Properties Microstructure and Processing 147.
Journal Article
305 (1), pp. 14 - 20 (2002)
Overall mechanical properties of fiber-reinforced metal matrix composites for fusion applications. Journal of Nuclear Materials 148.
Journal Article
307-311, pp. 74 - 78 (2002)
Prediction of plastic deformation of fiber-reinforced copper matrix composites. Journal of Nuclear Materials 149.
Journal Article
299, pp. 1 - 8 (2001)
Analysis of Singular Interface Stresses in Dissimilar Material Joints for Plasma-Facing Components. Journal of Nuclear Materials 150.
Journal Article
299, pp. 9 - 19 (2001)
Analytical Method for Thermal Stress Analysis of Plasma-Facing Materials. Journal of Nuclear Materials Book Chapter (2)
151.
Book Chapter
3, pp. 554 - 575 (Ed. Greenspan, E.). Elsevier B. V., Amsterdam (2021)
Magnetic Confinement Fusion – Technology: Fusion Core. In: Encyclopedia of Nuclear Energy, Vol. 152.
Book Chapter
Plasma Exposed Materials for Nuclear Fusion Devices. In: Steels and Materials for Power Plants, EUROMAT 99, pp. 400 - 405 (Eds. Neumann, P.; Allen, D.; Tenckhoff, E.). Wiley-VCH, Weinheim (2000)
Conference Paper (3)
153.
Conference Paper
Tungsten Composite Materials for Fusion First Wall applications. In: 26th IAEA Fusion Energy Conference, MPT/P5-3. 26th IAEA Fusion Energy Conference (FEC 2016), Kyoto, October 17, 2016 - October 22, 2016. International Atomic Energy Agency, Vienna (2018)
154.
Conference Paper
Systems Engineering Approach for Pre-Conceptual Design of DEMO Divertor. In: 2018 26th International Conference on Nuclear Engineering, V005T05A027. 26th International Conference on Nuclear Engineering (ICONE26), London, July 22, 2018 - July 26, 2018. The American Society of Mechanical Engineers, New York, NY (2018)
155.
Conference Paper
Microstructural investigations of tungsten manufactured by means of laser beam melting. In: Proceedings of the 6th International Conference on Additive Technologies – iCAT 2016, pp. 61 - 66 (Eds. Drstvensek, I.; Drummer, D.; Schmidt, M.). 6th International Conference on Additive Technologies iCAT 2016, Nürnberg, November 29, 2016 - November 30, 2016. Interesansa – zavod, Ljubljana (2016)
Talk (109)
156.
Talk
Progress in R&D on Plasma-Facing Materials and Components for Fusion Devices. aiv XXV Conference, Naples (submitted)
157.
Talk
Nuclear analysis and assessment of irradiation effects on the Divertor Plasma Facing Components of the DEMO fusion reactor. 16th Kudowa Summer School "Towards Fusion Energy", Kudowa-Zdroj (2022)
158.
Talk
First step in the definition of a systematic evaluation procedure for DEMO high flux divertor target qualification. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)
159.
Talk
Plasma Exhaust and Divertor Designs in Japan and Europe Broader Approach, DEMO Design Activity. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (2021)
160.
Talk
Results of high heat flux overload tests of European DEMO tungsten divertor target mock-ups. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (submitted)