氖注入条件下ITER射频特定钨侵蚀与全局输运

中文摘要 AI 辅助

离子回旋射频加热（ICRH）是ITER中关键的辅助加热系统，但高功率射频运行可通过天线结构及邻近等离子体 facing 组件上的整流射频鞘电位增强等离子体-材料相互作用。我们首次将STRIPE（模拟射频杂质产生与发射输运）框架预测性应用于评估在ITER相关氖注入条件下，来自ITER ICRH天线的射频鞘驱动钨（W）侵蚀及全局杂质输运。STRIPE耦合了SOLPS-ITER等离子体背景、全波射频鞘计算、几何特定离子能量-角度分布、溅射物理及三维杂质输运。模拟预测天线限制器侧壁上的射频鞘电位为1至3千伏，使总钨侵蚀相对于热鞘条件增加约64倍，产生每秒3.34e18个钨原子的总源。侵蚀由射频修正的离子能量-角度分布及局部等离子体通量共同决定，而非仅由鞘电压决定。约10%的溅射钨被局部再沉积，产生每秒3.01e18个钨原子的净源。射频诱导的天线源仍比热偏滤器源小约三个数量级，且比集成热主室源小两个多数量级。100毫秒后，约22%的可移动钨库存位于SOLPS覆盖的约束等离子体区域内，对应环形钨浓度为1.70e-6。这些结果表明，在所考虑条件下，ITER ICRH天线不太可能主导总钨源预算，并展示了耦合建模射频波、鞘、溅射、再沉积及全局杂质输运的必要性。

英文摘要

Ion cyclotron radio-frequency heating (ICRH) is a key auxiliary heating system in ITER, but high-power RF operation can enhance plasma-material interactions through rectified RF sheath potentials on antenna structures and nearby plasma-facing components. We present the first predictive application of the STRIPE (Simulated Transport of RF Impurity Production and Emission) framework to assess RF sheath-driven tungsten (W) erosion and global impurity transport from the ITER ICRH antenna under ITER-relevant neon-seeded conditions. STRIPE couples SOLPS-ITER plasma backgrounds, full-wave RF sheath calculations, geometry-specific ion energy-angle distributions, sputtering physics, and three-dimensional impurity transport. Simulations predict RF sheath potentials of 1 to 3 kV on antenna limiter sidewalls, increasing gross W erosion by about a factor of 64 relative to thermal sheath conditions and producing a gross source of 3.34e18 W atoms per second. Erosion is governed by RF-modified ion energy-angle distributions together with local plasma flux rather than sheath voltage alone. About 10 percent of sputtered W is locally redeposited, giving a net source of 3.01e18 W atoms per second. The RF-induced antenna source remains about three orders of magnitude smaller than the thermal divertor source and more than two orders of magnitude smaller than the integrated thermal main-chamber source. After 100 ms, about 22 percent of the mobile W inventory resides within the SOLPS-covered confined-plasma region, corresponding to an annular W concentration of 1.70e-6. These results indicate that the ITER ICRH antenna is unlikely to dominate the total W source budget under the conditions considered and demonstrate the need for coupled modeling of RF waves, sheaths, sputtering, redeposition, and global impurity transport.

发表机构

• Max-Planck-Institut für Plasmaphysik（德国马克斯·普朗克等离子体物理研究所）

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