Fusion Science & Technology · 2005 · 32 citations · 9 references
EngineeringMaterials EngineeringNuclear EngineeringEnergy MaterialsFusion EngineeringNuclear MaterialsBlanket EngineeringFusion Reactor MaterialsInsulation MaterialsInsulation SystemsNuclear FusionTokamak EngineeringBlanket DesignBlanket MaterialsNuclear Mechanical PropertiesTritium Breeding BlanketsTritium Permeation
In order to clarify key engineering issues and to enhance key R&D activities for D-T fusion blankets, many design activities on innovative liquid blanket systems are on going as collaboration studies in Japan. Recently an improved long-life Flibe blanket has been proposed, and the self-cooled Li/V blanket design has started. For Flibe systems, much progress has been made on tritium permeation barrier, energy conversion system, free surface designs, and thermofluid loop experiments. For Li/V systems, evaluation studies have proceeded on Be-free nuclear properties and allowable crack fraction on multilayered MHD insulation coatings.
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Development of coatings for fusion power applications
Dale Smith, J. Konys, T. Muroga et al. · Journal of Nuclear Materials · 2002 · 92 citations
Blanket and divertor design for force free helical reactor (FFHR)
A. Sagara, O. Motojima, K. Y. Watanabe et al. · Fusion Engineering and Design · 1995 · 85 citations
Magneto-Hydro-Dynamic Pressure Drop of Lithium Flow in Rectangular Ducts
Keiji MIYAZAKI, Shoji Inoue, Nobuo Yamaoka et al. · Fusion Technology · 1986 · 57 citations
Deuterium/tritium behavior in Flibe and Flibe-facing materials
R.A. Anderl, Satoshi Fukada, G.R. Smolik et al. · Journal of Nuclear Materials · 2004 · 42 citations