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Potential and limits of water-cooled Pb–17Li blankets and divertors for a fusion power plant

M.A Fütterer, L Barleon, L Giancarli, A.Li Puma, G Vella2000年Fusion Engineering and DesignIF 1.7出版社

AbstractBlankets and divertors are key components of a fusion power plant. They have a large impact on the overall plant design, its performance and availability, and on the cost of electricity. The water-cooled Pb–17Li (WCLL) blanket uses reduced activation ferritic–martensitic steel as structural material. It was previously validated under numerous aspects such as TBR, mechanical and thermo-mechanical stability, thermal–hydraulics, MHD, safety and others. This was done assuming the specifications for a European DEMOnstration reactor which were fixed back in 1989. A WCLL blanket would best be combined with a water-cooled divertor so that a single coolant could be used for the entire reactor. Several divertor designs were proposed recently. This paper investigates the applicability of the WCLL blanket concept and a water-cooled divertor in attractive power reactors with increased power densities compared with DEMO.

日本語訳

ブランケットとダイバータは、核融合発電所の主要構成要素である。これらは、プラント全体の設計、その性能、および発電コストに大きな影響を与える。水冷Pb–17Li(WCLL)ブランケットは、低放射化フェライト・マルテンサイト鋼を構造材料として使用する。これは以前、TBR、機械的・熱機械的安定性、熱流動、MHD、安全性など、多くの側面において検証済みである。これは、1989年に固定された欧州DEMO炉の仕様を前提として行われたものである。WCLLブランケットは、単一の冷却材を炉全体に使用できるように、水冷ダイバータと組み合わせるのが最適である。近年、いくつかのダイバータ設計が提案されている。本論文では、DEMOと比較して出力密度が増大した魅力的な発電炉における、WCLLブランケット概念と水冷ダイバータの適用可能性を調査する。

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