Design Window Analysis for the Helical DEMO Reactor FFHR-d1
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概要
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Conceptual design activity for the LHD-type helical DEMO reactor FFHR-d1 has been conducted at the National Institute for Fusion Science under the Fusion Engineering Research Project since FY2010. In the first step of the conceptual design process, design window analysis was conducted using the system design code HELIOSCOPE by the "Design Integration Task Group". On the basis of a parametric scan with the core plasma design based on the DPE (Direct Profile Extrapolation) method, a design point having a major radius of 15.6 m and averaged magnetic field strength at the helical coil winding center of 4.7 T was selected as a candidate. The validity of the design was confirmed through the analysis by the related task groups (in-vessel component, blanket, and superconducting magnet).
- 社団法人 プラズマ・核融合学会の論文
著者
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SAGARA Akio
National Insitute for Fusion Science
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MIYAZAWA Junichi
National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292, Japan
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Hamaguchi Shinji
National Institute For Fusion Science
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YANAGI Nagato
National Institute for Fusion Science
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TAMURA Hitoshi
National Institute for Fusion Science
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GOTO Takuya
National Institute for Fusion Science, Toki 509-5292 Japan
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TANAKA Teruya
National Institute for Fusion Science
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GOTO Takuya
National Institute for Fusion Science
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MIYAZAWA Junichi
National Institute for Fusion Science
関連論文
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