Experimental demonstration of tokamak inductive flux saving by transient coaxial helicity injection on national spherical torus experiment

Journal Article · Thu Sep 15 00:00:00 EDT 2011 · Physics of Plasmas

DOI:https://doi.org/10.1063/1.3628540· OSTI ID:22043497

Raman, R; Jarboe, T R; Nelson, B A ^[1]; Mueller, D; Bell, M G; Gerhardt, S; LeBlanc, B; Menard, J; Ono, M; Roquemore, L ^[2]; Soukhanovskii, V ^[3]

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1. University of Washington, Seattle, Washington 98195 (United States)
2. Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)
3. Lawrence Livermore National Laboratory, Livermore, California 94551 (United States)

Discharges initiated by transient coaxial helicity injection in National Spherical Torus Experiment have attained peak toroidal plasma currents up to 300 kA. When induction from the central solenoid is then applied, these discharges develop up to 300 kA additional current compared to discharges initiated by induction only. CHI initiated discharges in NSTX have achieved 1 MA of plasma current using only 258 mWb of solenoid flux whereas standard induction-only discharges require about 50% more solenoid flux to reach 1 MA. In addition, the CHI-initiated discharge has lower plasma density and a low normalized internal plasma inductance of 0.35, as needed for achieving advanced scenarios in NSTX.

• OSTI ID: 22043497
• Journal Information: Physics of Plasmas, Vol. 18, Issue 9; Other Information: (c) 2011 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 1070-664X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CONFINEMENT
ELECTRIC CURRENTS
ELECTRIC DISCHARGES
HELICITY
INDUCTION
INJECTION
NSTX DEVICE
PLASMA
PLASMA DENSITY
SOLENOIDS
SPHERICAL CONFIGURATION
TRANSIENTS