作者: M Kotschenreuther , S Mahajan , B Covele , P Valanju
DOI: 10.1088/0029-5515/54/7/072006
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摘要: It is found that the X-Divertor (XD) configuration [1-3] can be made with conventional PF coil set on ITER[4], where all coils are outside TF coils. Desirable configurations possible currents below present maximum design limits ITER, and baseline divertor cassette used. XD could used to assist in high-power operation but some further issues need examination. Note increased major radius of Super (SXD) [5-8] not a feature geometry. In addition, we an for K-DEMO [9], demonstrate it also attain advanced tokamak reactors The results given here far more encouraging than recent calculations by Lackner Zohm [10] Snowflake [11,12], required high represent technological challenge. magnetic field structure outboard SOL [13] recently created reproduces what was presented earlier papers [1-3]. Consequently, same advantages accrue, no close-in employed.