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Comparison of measured impurity poloidal rotation in DIII-D with neoclassical predictions under low toroidal field conditions

K.H. Burrell, B.A. Grierson, W.M. Solomon, E.A. Belli2014年被引用 8Nuclear FusionIF 3出版社

Predictive understanding of plasma transport is a long-term goal of fusion research. This requires testing models of plasma rotation including poloidal rotation. The present experiment was motivated by recent poloidal rotation measurements on spherical tokamaks (NSTX and MAST) which showed that the poloidal rotation of C+6 is much closer to the neoclassical prediction than reported results in larger aspect ratio machines such as TFTR, DIII-D, JT-60U and JET working at significantly higher toroidal field and ion temperature. We investigated whether the difference in aspect ratio (1.44 on NSTX versus 2.7 on DIII-D) could explain this. We measured C+6 poloidal rotation in DIII-D under conditions which matched, as best possible, those in the NSTX experiment; we matched plasma current (0.65 MA), on-axis toroidal field (0.55 T), minor radius (0.6 m), and outer flux surface shape as well as the density and temperature profiles. DIII-D results from this work also show reasonable agreement with neoclassical theory. Accordingly, the different aspect ratio does not explain the previously mentioned difference in poloidal rotation results.

日本語訳

プラズマ輸送の予測的理解は、核融合研究の長期的な目標である。これには、ポロイダル回転を含むプラズマ回転モデルの検証が必要である。本実験は、球状トカマク(NSTXおよびMAST)における最近のポロイダル回転測定によって動機づけられたものであり、これらの測定では、C+6のポロイダル回転が、TFTR、DIII-D、JT-60U、JETなど、より大きなアスペクト比を有し、著しく高いトロイダル磁場とイオン温度で運転される装置における報告結果よりも、新古典論的予測にはるかに近いことが示された。我々は、アスペクト比の違い(NSTXでは1.44、DIII-Dでは2.7)がこの差異を説明し得るかどうかを調査した。我々は、NSTX実験における条件に可能な限り一致する条件下で、DIII-DにおいてC+6のポロイダル回転を測定した。すなわち、プラズマ電流(0.65 MA)、軸上トロイダル磁場(0.55 T)、小半径(0.6 m)、および外部フラックス面形状を一致させるとともに、密度・温度分布も一致させた。本研究におけるDIII-Dの結果も、新古典論的理論と合理的な一致を示した。したがって、アスペクト比の違いは、ポロイダル回転結果における前述の差異を説明するものではない。

装置

diii-d高精度(タイトル一致)jet低精度(概要文一致)mast低精度(概要文一致)nstx-u低精度(概要文一致)tftr低精度(概要文一致)

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DIII-DImpurityPoloidal rotation
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