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Thermal-hydraulic analysis of the dual-cooled waste transmutation blanket for the FDS

Y Ke, H.Y Wang, Y.C Wu2002年Fusion Engineering and DesignIF 1.7出版社

AbstractA conceptual structure design and the thermal-hydraulic analysis of the pressurized helium gas and LiPb eutectic dual-cooled waste transmutation blanket for the Fusion-Driven Sub-critical System (FDS), which is being designed for multi-purposes (transmuting nuclear wastes from fission power plants, breeding fissionable nuclear fuel for fission power plants and breeding tritium for sustainable operation) based on the Tokamak fusion core with the minor radius of 1 m, the major radius of 4 m, the elongation of 1.7 and the responding neutron wall loading of 0.5 MW/m2, have been presented.

日本語訳

核融合駆動型サブクリティカルシステム(FDS)用の加圧ヘリウムガスとLiPb共晶の二重冷却廃棄物転換ブランケットの概念構造設計と熱水力解析を提示した。FDSは、マイナー半径1m、メジャー半径4m、伸長比1.7、対応する中性子壁負荷0.5 MW/m²のトカマク核融合炉心に基づき、多目的(核分裂発電所からの核廃棄物の転換、核分裂発電所のための核分裂性核燃料の増殖、持続可能な運転のためのトリチウム増殖)で設計されている。

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