Design of the C-Mod Advanced Outer Divertor
Fusion Engineering（2014）
摘要
Operational requirements and research considerations make a high-temperature, toroidally continuous outer divertor an important aspect for future operation of the Alcator C-Mod tokamak. Leading edge melting of tiles, nonuniform heat loads, large electromagnetic forces, and localized impurity sources limit the performance of bulk plasmas. These issues can be addressed by the installation of a well-aligned, toroidally continuous outer divertor. In addition, future proposed long pulse operation of C-Mod will cause the temperature of the outer divertor to reach bulk temperatures as high as 500-600°C. This future operational requirement combined with the strong temperature dependence of plasma surface interactions (especially fuel retention), makes a controllable, high-temperature outer divertor desirable and necessary. The design and development of the C-Mod Advanced Outer Divertor (AOD) is discussed.
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关键词
plasma-wall interactions,tokamak,electromagnetic forces,plasma surface interactions,high-temperature toroidally continuous outer divertor,design,tokamak devices,localized impurity sources,c-mod advanced outer divertor,fusion reactor design,c-mod,plasma toroidal confinement,tokamak.,temperature 500 degc to 600 degc,bulk plasmas,fusion reactor divertors,toroidally continuous outer divertor,fuel retention,alcator c-mod tokamak,plasma impurities,heat loads,leading edge melting,outer divertor,fusion reactor operation,nonuniform heat loads,plasma boundary layers,heating,assembly,temperature measurement
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