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ダイバータープラズマの特徴的温度領域におけるタングステン不純物輸送の系統的評価

Systematic study of tungsten impurity transport in representative regimes of divertor plasma

矢本 昌平*; 星野 一生; 本間 裕貴*; 畑山 明聖*; Bonnin, X.*; Coster, D.*; Schneider, R.*

Yamoto, Shohei*; Hoshino, Kazuo; Homma, Yuki*; Hatayama, Akiyoshi*; Bonnin, X.*; Coster, D.*; Schneider, R.*

To understand the impurity transport in fusion edge plasma, systematic study of the dependence of tungsten impurity transport on the background plasma conditions are needed. In this study, as the first step, the dependence of the impurity transport on the upstream plasma density has been studied by impurity transport code IMPGYRO for the fixed background plasma profiles obtained from SOLPS code in a model Tokamak geometry of JT-60U tungsten experiments. The density profiles of tungsten are compared between the low background deuterium density (Case A: n$$_{D+}$$ = $$2.0 times 10^{19}$$ m$$^{-3}$$ at core side boundary) and the high background deuterium density (Case B: n$$_{D+}$$ = $$3.0 times 10^{19}$$ m$$^{-3}$$ at core side boundary). The impurity density profile in the SOL is more localized at the low field side for Case B. These features are possibly explained by the force balance between the thermal force and the friction force.

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