Non-inductively driven tokamak plasmas at near-unity βt in the Pegasus toroidal experiment

A major goal of the spherical tokamak (ST) research program is accessing a state of low internal inductance ℓi, high elongation κ, and high toroidal and normalized beta ( βt and βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S...

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Veröffentlicht in:Physics of plasmas 2018-05, Vol.25 (5)
Hauptverfasser: Reusch, J. A., Bodner, G. M., Bongard, M. W., Burke, M. G., Fonck, R. J., Pachicano, J. L., Perry, J. M., Pierren, C., Rhodes, A. T., Richner, N. J., Rodriguez Sanchez, C., Schlossberg, D. J., Weberski, J. D.
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container_issue 5
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container_title Physics of plasmas
container_volume 25
creator Reusch, J. A.
Bodner, G. M.
Bongard, M. W.
Burke, M. G.
Fonck, R. J.
Pachicano, J. L.
Perry, J. M.
Pierren, C.
Rhodes, A. T.
Richner, N. J.
Rodriguez Sanchez, C.
Schlossberg, D. J.
Weberski, J. D.
description A major goal of the spherical tokamak (ST) research program is accessing a state of low internal inductance ℓi, high elongation κ, and high toroidal and normalized beta ( βt and βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S603 (2006)] provides non-solenoidally driven plasmas that exhibit these characteristics. LHI utilizes compact, edge-localized current sources for plasma startup and sustainment. It results in hollow current density profiles with low ℓi. The low aspect ratio ( R0/a∼1.2) of Pegasus allows access to high κ and high normalized plasma currents ( IN=Ip/aBT>14). Magnetic reconnection during LHI provides auxiliary ion heating. Together, these features provide access to very high βt plasmas. Equilibrium analyses indicate that βt up to ∼100% is achieved. These high βt discharges disrupt at the ideal no-wall β limit at βN∼7.
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A. ; Bodner, G. M. ; Bongard, M. W. ; Burke, M. G. ; Fonck, R. J. ; Pachicano, J. L. ; Perry, J. M. ; Pierren, C. ; Rhodes, A. T. ; Richner, N. J. ; Rodriguez Sanchez, C. ; Schlossberg, D. J. ; Weberski, J. D.</creator><creatorcontrib>Reusch, J. A. ; Bodner, G. M. ; Bongard, M. W. ; Burke, M. G. ; Fonck, R. J. ; Pachicano, J. L. ; Perry, J. M. ; Pierren, C. ; Rhodes, A. T. ; Richner, N. J. ; Rodriguez Sanchez, C. ; Schlossberg, D. J. ; Weberski, J. D. ; Univ. of Wisconsin, Madison, WI (United States)</creatorcontrib><description>A major goal of the spherical tokamak (ST) research program is accessing a state of low internal inductance ℓi, high elongation κ, and high toroidal and normalized beta ( βt and βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S603 (2006)] provides non-solenoidally driven plasmas that exhibit these characteristics. 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source AIP Journals Complete; Alma/SFX Local Collection
subjects 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
beta limit
equilibrium reconstruction
helicity injection
magnetic reconnection
spherical tokamaks
tokamaks
title Non-inductively driven tokamak plasmas at near-unity βt in the Pegasus toroidal experiment
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