Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment

Journal of Nuclear Materials

Volumn 363-365, Issue 1-3, 2007, Pages 196-200

  Maingi, R ^a   Bush, C E ^a   Kaita, R ^b   Kugel, H W ^b   Roquemore, A L ^b   Paul, S F ^b   Soukhanovskii, V A ^c  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b PRINCETON PLASMA PHYSICS LABORATORY   (United States)

^c LAWRENCE LIVERMORE NATIONAL LABORATORY   (United States)

Author keywords

D0500; Detachment; Divertor plasma; NSTX; P0500; P0600; Sol plasma; Target profiles

Indexed keywords

ELECTRIC DISCHARGES; HEAT FLUX; HYDROGEN;

D0500; DIVERTOR PLASMA; NATIONAL SPHERICAL TORUS EXPERIMENT; P0500; P0600; PLASMA CURRENT; SOL PLASMA;

FUSION REACTOR DIVERTORS;

EID: 34248597834     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2007.01.063     Document Type: Article

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