Fusion Science & Technology · 2015 · 27 citations · 6 references
EngineeringManufacturing EngineeringNuclear EngineeringFusion EngineeringHeat TransferManufacturing ProcessesBlanket EngineeringFusion Reactor MaterialsMagnetic Confinement FusionReactor Core DesignThermal DesignBlanket DesignBlanket Module DesignCold Flow TechnologyCooling Channel DesignPower Plant DesignPressure LossesThermal-hydraulic Design
The dual-coolant lead-lithium (DCLL) blanket concept, which is considered as a candidate for fusion power plants and possibly for a demonstration reactor (DEMO), is being investigated within the framework of the European Power Plant Physics and Technology (PPPT) study. One of major issues of the DCLL concept development is the design of the flow channel inserts (FCIs), which are essential for the reduction of magneto-hydrodynamic (MHD) pressure losses. Due to the tight schedule for the short-term PPPT DEMO, a low-temperature DCLL concept with a liquid metal outlet temperature below 500 °C has been proposed. This allows the use of a simpler type of FCI (taking into account the LM corrosion issues), e.g. Eurofer-Alumina-Eurofer sandwich FCI, instead of the SiCf/SiC version for high temperature case, the production thereof is challenging. This paper discusses the technological study on manufacturing of some FCI design variants and post-examination of the samples.
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Development of the Lead Lithium (DCLL) Blanket Concept
S. Malang, M. S. Tillack, C.P.C. Wong et al. · Fusion Science & Technology · 2011 · 97 citations
Development of insulating coatings for liquid metal blankets
S. Malang, H.U. Borgstedt, E.H. Farnum et al. · Fusion Engineering and Design · 1995 · 65 citations · Full text
Natural Sciences, Materials Engineering, Materials Science +12
ITER-Test blanket module functional materials
C.P.C. Wong, Akihiko Kimura, Yutai Katoh et al. · Journal of Nuclear Materials · 2007 · 60 citations