Experimental demonstration of tokamak inductive flux saving by transient coaxial helicity injection on national spherical torus experiment
Abstract
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.
- Authors:
-
- University of Washington, Seattle, Washington 98195 (United States)
- Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)
- Lawrence Livermore National Laboratory, Livermore, California 94551 (United States)
- Publication Date:
- OSTI Identifier:
- 22043497
- Resource Type:
- Journal Article
- Journal Name:
- Physics of Plasmas
- Additional Journal Information:
- Journal Volume: 18; Journal Issue: 9; Other Information: (c) 2011 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 1070-664X
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CONFINEMENT; ELECTRIC CURRENTS; ELECTRIC DISCHARGES; HELICITY; INDUCTION; INJECTION; NSTX DEVICE; PLASMA; PLASMA DENSITY; SOLENOIDS; SPHERICAL CONFIGURATION; TRANSIENTS
Citation Formats
Raman, R, Jarboe, T R, Nelson, B A, Mueller, D, Bell, M G, Gerhardt, S, LeBlanc, B, Menard, J, Ono, M, Roquemore, L, and Soukhanovskii, V. Experimental demonstration of tokamak inductive flux saving by transient coaxial helicity injection on national spherical torus experiment. United States: N. p., 2011.
Web. doi:10.1063/1.3628540.
Raman, R, Jarboe, T R, Nelson, B A, Mueller, D, Bell, M G, Gerhardt, S, LeBlanc, B, Menard, J, Ono, M, Roquemore, L, & Soukhanovskii, V. Experimental demonstration of tokamak inductive flux saving by transient coaxial helicity injection on national spherical torus experiment. United States. https://doi.org/10.1063/1.3628540
Raman, R, Jarboe, T R, Nelson, B A, Mueller, D, Bell, M G, Gerhardt, S, LeBlanc, B, Menard, J, Ono, M, Roquemore, L, and Soukhanovskii, V. 2011.
"Experimental demonstration of tokamak inductive flux saving by transient coaxial helicity injection on national spherical torus experiment". United States. https://doi.org/10.1063/1.3628540.
@article{osti_22043497,
title = {Experimental demonstration of tokamak inductive flux saving by transient coaxial helicity injection on national spherical torus experiment},
author = {Raman, R and Jarboe, T R and Nelson, B A and Mueller, D and Bell, M G and Gerhardt, S and LeBlanc, B and Menard, J and Ono, M and Roquemore, L and Soukhanovskii, V},
abstractNote = {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.},
doi = {10.1063/1.3628540},
url = {https://www.osti.gov/biblio/22043497},
journal = {Physics of Plasmas},
issn = {1070-664X},
number = 9,
volume = 18,
place = {United States},
year = {Thu Sep 15 00:00:00 EDT 2011},
month = {Thu Sep 15 00:00:00 EDT 2011}
}
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