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Illustrating the physics of core tungsten (W) transport in a long-pulse steady-state H-mode discharge on EAST

Shengyu Shi, Jiale Chen, Xiang Jian, Tomáš Odstrčil, Bourdelle Clarrisse, Muquan Wu, Mingfu Wu, Yanmin Duan, Yan Chao, Ling Zhang2022年Nuclear FusionIF 3出版社

The behavior of core tungsten (W) in a pure radio-frequency-heated long-pulse steady-state H-mode discharge in the Experimental Advanced Superconducting Tokamak (EAST) with an ITER-like divertor (ILD) is analyzed using experimental diagnostic data and modeled using a combination of drift-kinetic neoclassical and gyro-fluid turbulent software. In the steady state, the experimental core line-averaged W concentration (CW) is about 2 × 10−5, which is evaluated using the intensity of the W unresolved transition array (W-UTA) spectral structure in the region of 45–70 Å (which is composed of W27+–W45+ line emissions) through spectroscopy in the extreme ultraviolet region. W produces a peak of the radiated power density profile around a normalized radius of ρ ∼ 0.3. Therefore, W does not centrally accumulate in the experiment. A time slice of the steady-state is modeled, which accounts for both the neoclassical and turbulent transport components of W based on the self-consistent background plasma profiles simulated by TGYRO (Candy et al 2009 Phys. Plasmas16 060704). It is found that turbulent transport dominates over neoclassical transport for W. In addition, the turbulent diffusion coefficient is large enough to offset the sum of the neoclassical and turbulent pinch (convection) velocities, so that the W density profile for a zero particle flux is not strongly peaked. By combining TGLF (Staebler et al 2017 Nucl. Fusion57 066046) and NEO (Belli and Candy 2008 Plasma Phys. Control. Fusion50 095010; 2012 Plasma Phys. Control. Fusion54 015015) for the W transport coefficient with the impurity transport code STRAHL (Dux 2006 STRAHL User Manual), the experimental CW and the information radiated by W can be reproduced closely. In addition, the effect of toroidal rotation on the W transport is also clarified.

日本語訳

実験的アドバンスト超伝導トカマク(EAST)におけるITER類似ダイバータ(ILD)を備えた純粋な高周波加熱長時間パルス定常Hモード放電におけるコアタングステン(W)挙動を、実験的診断データとドリフト運動論的縮約輸送モデルを用いて解析した。定常状態では、極端紫外領域の分光法により45–70 ÅのWアンリゾルブド遷移系列(W-UTA)の強度から評価したコアライン平均W濃度(CW)は約2×10⁻⁵であり、W放射パワー密度分布は規格化半径ρ∼0.3付近でピークを示し、コアへのW蓄積は観測されなかった。この定常状態の時間スライスについて、TGYRO(Candy et al. 2009 Phys. Plasmas 16 060704)により自己無撞着に計算された背景プラズマプロファイルに基づき、Wの新古典輸送と乱流輸送の両方を考慮したモデリングを行った。その結果、W輸送は乱流輸送が新古典輸送を支配することが明らかになった。さらに、TGLF(Staebler et al. 2017 Nucl. Fusion 57 066046)とNEO(Belli and Candy 2008 Plasma Phys. Control. Fusion 50 095010; 2012 Plasma Phys. Control. Fusion 54 015015)を用いてW輸送係数を計算し、不純物輸送コードSTRAHL(Dux 2006 STRAHL User Manual)に組み込んで実験結果を再現したところ、乱流拡散係数が新古典・乱流対流(ピンチ)速度の和を打ち消すのに十分な大きさを持ち、その結果W密度分布がゼロ粒子束条件で強くピーク化しないことが示された。これにより、実験で観測されたCWとW放射パワー密度分布を良好に再現できた。さらに、トロイダル回転がW輸送に及ぼす影響も明らかにされた。

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east高精度(タイトル一致)iter中精度(概要文一致)

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