TY - JOUR
T1 - Design of the C-mod advanced outer divertor
AU - Vieira, Rui
AU - Harrison, Soren
AU - Michael, Philip C.
AU - Beck, William
AU - Zhou, Lihua
AU - Doody, Jeffrey
AU - Labombard, Brian
AU - Lipschultz, Bruce
AU - Granetz, Robert
AU - Ellis, Robert
AU - Zhang, Han
AU - Titus, Peter
PY - 2014/6
Y1 - 2014/6
N2 - 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 °C-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 is discussed.
AB - 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 °C-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 is discussed.
KW - C-Mod
KW - design
KW - outer divertor
KW - tokamak
UR - http://www.scopus.com/inward/record.url?scp=84902381204&partnerID=8YFLogxK
U2 - 10.1109/TPS.2014.2321292
DO - 10.1109/TPS.2014.2321292
M3 - Article
AN - SCOPUS:84902381204
SN - 0093-3813
VL - 42
SP - 1796
EP - 1801
JO - IEEE transactions on plasma science
JF - IEEE transactions on plasma science
IS - 6
ER -