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“Snowflake” divertor configuration in NSTX

“Snowflake” divertor configuration in NSTX,10.1016/j.jnucmat.2010.07.047,Journal of Nuclear Materials,V. A. Soukhanovskii,Joonwook Ahn,R. E. Bell,D. A

“Snowflake” divertor configuration in NSTX  
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V. A. Soukhanovskii, Joonwook Ahn, R. E. Bell, D. A. Gates, S. Gerhardt, R. Kaita, E.. Kolemen, H. W. Kugel, B. P. LeBlanc, Rajesh Maingi, R. J. Maqueda, Adam G McLeanhttp://academic.research.microsoft.com/io.ashx?type=5&id=26224167&selfId1=0&selfId2=0&maxNumber=12&query=
Steady-state handling of divertor heat flux is a critical issue for present and future conventional and spherical tokamaks with compact high power density divertors. A novel “snowflake” divertor (SFD) configuration that takes advantage of magnetic properties of a second-order poloidal null has been predicted to have a larger plasma-wetted area and a larger divertor volume, in comparison with a standard first-order poloidal X-point divertor configuration. The SFD was obtained in 0.8MA, 4–6MW NBI-heated H-mode discharges in NSTX using two divertor magnetic coils. The SFD led to a partial detachment of the outer strike point even in low-collisionality scrape-off layer plasma obtained with lithium coatings in NSTX. Significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with good core confinement and MHD properties.
Journal: Journal of Nuclear Materials - J NUCL MATER , vol. 415, no. 1, pp. S365-S368, 2011
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