TRANSP predictive modeling of EAST steady state plasmas
POSTER
Abstract
The EAST tokamak is starting operation with major upgrades to the heating, current drive, and diagnostic systems [1]. We use the plasma transport code TRANSP to predict performance [2] with nearly steady state non-inductive current conditions at plasma current near 500~kA and toroidal field near 2.3~T. The heating power is assumed to start with $\simeq$4~MW of beam injection and continue with $\simeq$3 MW of ICRH. Current drive of $\simeq$2~MW of LHCD is assumed. The GLF23 [3] predictive model incorporated in TRANSP is used to predict temperatures, and TGLF [4] to predict temperatures, toroidal rotation, and electron density profiles. We explore scans in parameters such as I$_p$, B$_0$, and boundary assumptions to maintain non-inductive and high performance. \\[4pt] [1] G.Wan, {\it et al.,} 41$^{st}$ EPS Conf, Berlin (2014) O2.104;\\[4pt] [2] R.V.Budny, Nucl. Fusion {\bf 52} (2012) 013001;\\[0pt] [3] R.Waltz, {\it et al.,} Phys. Plasmas {\bf 4} (1997) 2482;\\[0pt] [4] G.M.Staebler, {\it et al.,} Phys. Plasmas {\bf 14} (2007) 055909
Authors
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R.V. Budny
PPPL
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W.M. Solomon
PPPL
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B.A. Grierson
Princeton Plasma Physics Laboratory, PPPL
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X. Yuan
PPPL
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C.E. Kessel
Princeton Plasma Physics Lab, Princeton Plasma Physics Laboratory, PPPL
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S. Ding
Institute of Plasma Physics, Chinese Academy of Sciences, IPP-Hefei, CN