Design and Integration of ITER Divertor Components
Takeshi Hirai, V. Barabash, F. Escourbiac, A. Fedosov, L. Ferrand, S. Gicquel, T. Jokinen, V. Komarov, A. Martin, M. Merola |
p1 |
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Tungsten as a Structural Divertor Material
Michael Rieth, Dave Armstrong, Bernhard Dafferner, Sylvia Heger, Andreas Hoffmann, Mirjam Diana Hoffmann, Ute Jäntsch, Christian Kübel, Edeltraud Materna-Morris, Jens Reiser, Magnus Rohde, Torsten Scherer, Verena Widak, Horst Zimmermann |
p11 |
|
Microstructural Control for Improving Properties of V-4Cr-4Ti Alloys
Takeo Muroga, Takuya Nagasaka, Peng Fei Zheng, J.M. Chen |
p22 |
|
SiC/SiC Composites Irradiation Behaviour in Fusion Reactor Environment Conditions
C.H. Chen, J.J. Kai, F.R. Chen, Y. Katoh |
p27 |
|
Experimental Development at a Pilot Plant Scale of a Reduced Activation Ferritic/Martensitic RAFM Steel, Asturfer®
Ana Morán, Rubén Coto, Javier Belzunce, Jose Manuel Artímez |
p36 |
|
Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor
Qun Ying Huang, Sheng Gao, Zhi Qiang Zhu, Zhi Hui Guo, Xin Zhen Ling, Zi Lin Yan, Masatoshi Kondo, Valentyn Tsisar, Takeo Muroga, Yi Can Wu |
p41 |
|
Utilization of Hydride Materials in Nuclear Reactors
Kenji Konashi, Michio Yamawaki |
p51 |
|
Progressive Development for Structural Integrity Quantification of Nuclear Grade Graphite in Very High Temperature Gas Cooled Reactor Core Environments
Shuo Cheng Tsai, Yi Tsang Hsieh, Ji Jung Kai, Fu Rong Chen |
p59 |
|
Multiscale Modelling of the Influence of Damage on the Thermal Properties of Ceramic Matrix Composites
Jalal El Yagoubi, Jacques Lamon, Jean Christophe Batsale |
p65 |
|
General Corrosion Properties of Modified PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water Reactor
Yoshihisa Nakazono, Takeo Iwai, Hiroaki Abe |
p72 |
