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

Journal Article · Mon Mar 01 04:00:00 EST 2010 · Physical Review Letters

DOI:https://doi.org/10.1103/PhysRevLett.104.095003· OSTI ID:1018272

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

---

1. University of Washington, Seattle
2. Princeton Plasma Physics Laboratory (PPPL)
3. Oak Ridge National Laboratory (ORNL)
4. Columbia University
5. Lawrence Livermore National Laboratory (LLNL)

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.

• Research Organization: Oak Ridge National Laboratory (ORNL)
• Sponsoring Organization: SC USDOE - Office of Science (SC)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1018272
• Journal Information: Physical Review Letters, Journal Name: Physical Review Letters Journal Issue: 9 Vol. 104; ISSN 0031-9007
• Country of Publication: United States
• Language: English