Demonstration of Tokamak Ohmic Flux Saving by Transient Coaxial Helicity Injection in the National Spherical Torus Experiment

Journal Article · Fri Mar 05 04:00:00 EST 2010 · Physical Review Letters

DOI:https://doi.org/10.1103/PHYSREVLETT.104.095003· OSTI ID:21386834

Raman, R; Nelson, B A; Jarboe, T R ^[1]; Mueller, D; Gerhardt, S; Kugel, H W; LeBlanc, B; Menard, J; Ono, M; Paul, S; Roquemore, L ^[2]; Maingi, R ^[3]; Sabbagh, S ^[4]; Soukhanovskii, V ^[5]

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1. University of Washington, Seattle, Washington (United States)
2. Princeton Plasma Physics Laboratory, Princeton, New Jersey (United States)
3. Oak Ridge National Laboratory, Oak Ridge, Tennessee (United States)
4. Columbia University, New York, New York (United States)
5. Lawrence Livermore National Laboratory, Livermore, California (United States)

Transient coaxial helicity injection (CHI) started discharges in the National Spherical Torus Experiment (NSTX) have attained peak currents up to 300 kA and when coupled to induction, it has produced up to 200 kA additional current over inductive-only operation. CHI in NSTX has shown to be energetically quite efficient, producing a plasma current of about 10 A/J of capacitor bank energy. In addition, for the first time, the CHI-produced toroidal current that couples to induction continues to increase with the energy supplied by the CHI power supply at otherwise similar values of the injector flux, indicating the potential for substantial current generation capability by CHI in NSTX and in future toroidal devices.

• OSTI ID: 21386834
• Journal Information: Physical Review Letters, Journal Name: Physical Review Letters Journal Issue: 9 Vol. 104; ISSN 0031-9007; ISSN PRLTAO
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BEAM INJECTION
CAPACITORS
CLOSED PLASMA DEVICES
CURRENTS
ELECTRIC CURRENTS
ELECTRICAL EQUIPMENT
EQUIPMENT
HELICITY
INDUCTION
NSTX DEVICE
PARTICLE PROPERTIES
PLASMA
SPHEROMAK DEVICES
THERMONUCLEAR DEVICES
TOKAMAK DEVICES