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Home / Publications / Journals / Fusion Science and Technology / Volume 64 / Number 2 / Pages 277-281

Design and R&D for the C-Mod Outer Divertor Upgrade

Soren Harrison et al.

Fusion Science and Technology / Volume 64 / Number 2 / August 2013 / Pages 277-281

Divertor and High-Heat-Flux Components / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012

Operational requirements and research considerations make a high-temperature, toroidally continuous outer divertor an important upgrade to the Alcator C-Mod tokamak. Leading edge melting of tiles, non-uniform 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. Additionally, future long pulse operation 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 motivation, criteria, design, and R&D for the upgrade are discussed below.

 
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