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Full wave simulations of fast wave efficiency and power losses in the scrape-off layer of tokamak plasmas in mid/high harmonic and minority heating regimes

N. Bertelli, E.F. Jaeger, J.C. Hosea, C.K. Phillips, L. Berry, P.T. Bonoli, S.P. Gerhardt, D. Green, B. LeBlanc, R.J. Perkins2016年被引用 24Nuclear FusionIF 3出版社

Several experiments on different machines and in different fast wave (FW) heating regimes, such as hydrogen minority heating and high harmonic fast waves (HHFW), have found strong interaction between radio-frequency (RF) waves and the scrape-off layer (SOL) region. This paper examines the propagation and the power loss in the SOL by using the full wave code AORSA, in which the edge plasma beyond the last closed flux surface (LCFS) is included in the solution domain and a collisional damping parameter is used as a proxy to represent the real, and most likely nonlinear, damping processes. 2D and 3D AORSA results for the National Spherical Torus eXperiment (NSTX) have shown a strong transition to higher SOL power losses (driven by the RF field) when the FW cut-off is removed from in front of the antenna by increasing the edge density. Here, full wave simulations have been extended for 'conventional' tokamaks with higher aspect ratios, such as the DIII-D, Alcator C-Mod, and EAST devices. DIII-D results in HHFW regime show similar behavior found in NSTX and NSTX-U, consistent with previous DIII-D experimental observations. In contrast, a different behavior has been found for C-Mod and EAST, which operate in the minority heating regime.

日本語訳

異なる機械および異なる高速波(FW)加熱領域、例えば水素少数派加熱や高調波高速波(HHFW)において、無線周波数(RF)波とスクレイプオフ層(SOL)領域との間に強い相互作用が見出されている。本論文では、全波コードAORSAを用いてSOLにおける伝播と電力損失を考察する。このコードでは、最終閉鎖磁気面(LCFS)を超えた端部プラズマが解領域に含まれ、衝突減衰パラメータが実際の、そしておそらく非線形の減衰過程の代理として用いられている。NSTX(National Spherical Torus eXperiment)に対する2次元および3次元のAORSA結果は、端部密度を増加させることでFWカットオフがアンテナ前方から除去されると、SOL電力損失(RF場によって駆動される)への移行が強まることを示している。ここでは、全波シミュレーションを、DIII-D、Alcator C-Mod、EASTなどのような高アスペクト比を有する「従来型」トカマクへ拡張している。HHFW領域におけるDIII-Dの結果は、NSTXおよびNSTX-Uで見られたものと同様の挙動を示し、これは以前のDIII-D実験観測と一致している。対照的に、少数派加熱領域で動作するC-ModおよびEASTでは、異なる挙動が見出されている。

装置

alcator-c-mod中精度(概要文一致)diii-d中精度(概要文一致)east中精度(概要文一致)nstx-u中精度(概要文一致)

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Fusion Advanced Studies TorusScrape-off layer
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