DocumentCode
1608471
Title
Design of the C-Mod Advanced Outer Divertor
Author
Vieira, Ricardo ; Harrison, S. ; Michael, P. ; Beck, W. ; Zhou, Liang ; Doody, J. ; LaBombard, B. ; Lipschultz, B. ; Granetz, R. ; Ellis, Ryan ; Zhang, Haijun ; Titus, P.
Author_Institution
Massachusetts Inst. of Technol., Cambridge, MA, USA
fYear
2013
Firstpage
1
Lastpage
6
Abstract
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.
Keywords
Tokamak devices; electromagnetic forces; fusion reactor divertors; plasma impurities; plasma toroidal confinement; Alcator C-Mod tokamak; C-mod Advanced Outer Divertor; bulk plasmas; electromagnetic forces; fuel retention; heat loads; plasma surface interactions; temperature 500 degC to 600 degC; toroidally continuous outer divertor; Assembly; Connectors; Heating; Plasma temperature; Temperature measurement; Tiles; C-Mod; Tokamak; design; outer divertor;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location
San Francisco, CA
Print_ISBN
978-1-4799-0169-2
Type
conf
DOI
10.1109/SOFE.2013.6635486
Filename
6635486
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