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LOCUST-GPU predictions of fast-ion transport and power loads due to ELM-control coils in ITER

S.H. Ward, R. Akers, L. Li, Y.Q. Liu, A. Loarte, S.D. Pinches, A. R. Polevoi, R.G.L. Vann, M.A. Van Zeeland2022年被引用 2Nuclear FusionIF 3出版社

The graphics processing unit (GPU) version of the Lorentz-orbit code for use in stellarators and tokamaks (LOCUST) has been applied to study the fast-ion transport and loss caused by resonant magnetic perturbations in the high-performance Q = 10 ITER baseline scenario. The unique computational efficiency of the code is exploited to calculate the impact of the application of ITER's edge-localised mode (ELM) control coil system on neutral beam heating efficiency, as well as producing detailed predictions of the resulting plasma-facing component power loads, for a variety of operational parameters—the applied fundamental toroidal mode number n0, mode spectrum and absolute toroidal phase of the imposed perturbation. The feasibility of continually rotating the perturbations is assessed and shown to be effective at reducing the time-averaged power loads. Through careful adjustment of the relative phase of the applied perturbation in the three rows of coils, peak power loads are found to correlate with reductions in neutral beam injection (NBI) heating efficiency for n0 = 3 fields. Adjusting the phase this way can increase total NBI system efficiency by approximately 2%–3% and reduce peak power loads by up to 0.43 MW m−2. From the point of view of fast-ion confinement, n0 = 3 ELM control fields are preferred overall to n0 = 4 fields. In addition, the implementation of 3D magnetic fields in LOCUST is also verified by comparison with the SPIRAL code for a DIII-D discharge with ITER-similar shaping and n0 = 3 perturbation.

日本語訳

グラフィックス処理ユニット(GPU)版の、ステラレーターおよびトカマク用ローレンツ軌道コード(LOCUST)を適用し、高性能Q = 10のITERベースラインシナリオにおける共鳴磁場摂動によって引き起こされる高速イオン輸送と損失を研究した。このコードの独自の計算効率を活用し、ELM制御コイルシステムの適用が中性粒子ビーム加熱効率に与える影響を計算するとともに、様々な運転パラメータ(印加摂動の基本トロイダルモード数n0、モードスペクトル、絶対トロイダル位相)に対するプラズマ対向部品への電力負荷の詳細な予測を行った。摂動を連続的に回転させる実現可能性を評価し、時間平均電力負荷の低減に有効であることを示した。3列のコイルにおける印加摂動の相対位相を注意深く調整することにより、ピーク電力負荷がn0 = 3の場における中性粒子ビーム加熱効率の低下と相関することが見出された。この方法で位相を調整することにより、総NBIシステム効率を約2〜3%向上させ、ピーク電力負荷を最大0.43 MW m⁻²低減できる。高速イオン閉じ込めの観点からは、n0 = 3のELM制御場がn0 = 4の場よりも全体的に優れている。さらに、LOCUSTにおける3次元磁場の実装は、ITER類似の形状とn0 = 3の摂動を有するDIII-D放電について、SPIRALコードとの比較により検証された。

装置

iter高精度(タイトル一致)diii-d低精度(概要文一致)

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ITERFusion Advanced Studies TorusEdge localized modeEnergetic ionIon transport
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