Heating and Current Drive A.R. Polevoi, S.Yu. Medvedev, G.T.A. Huijsmans, S.H. Kim, A. Loarte, E. Fable, A.A. Ivanov, A.Y. Kuyanov. ITER Organization, Route de Vinon-sur-Verdon, 13067 St Paul Lez Durance, France 2 Keldysh Institute of Applied Mathematics, Miusskaya 4, 125047 Moscow, Russia CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France Max-Planck Inst. für Plasmaphysik, Boltzmanstraße 2, D-85748 Garching, Germany NRC "Kurchatov Institute", Kurchatov sq. 1, 123098 Moscow, Russia The parametric Operational Space (OS) for Steady-State (SS) operation [1] in ITER has been reassessed by global analysis taking into account the baseline design of the Neutral Beam Injection (NBI) and EC H&CD systems and their foreseen upgrades (up to PNBI = 49.5 MW and with PEC = 30 MW, where up to 40 MW upgrade is possible). The analysis has been carried out for so-called Type-II SS scenarios, which exclusively use NBI and EC for heating and current drive H&CD and for which no internal transport barriers are assumed [2, 3]. The obtained OSs determine the choice of plasma current, density, H&CD specifications (power levels, injection geometries, etc.) and required energy confinement to achieve a given fusion gain, Q=Pfus/(PEC+PNB). From these OSs a set of Operational Points (OP) with fusion gain Q=5 with various H&CD specifications have been selected for more detailed MHD stability and 1.5-D transport and current drive analysis including sensitivity studies. Self-consistent 1.5-D transport simulations have been carried out for these selected OPs during the steady-state current flat-top phase. The 1.5-D simulations take into account the contribution of the fast particles pressure as well as bootstrap and externally driven currents. Sensitivity studies to current and pressure profiles have been performed by variation of NBI & EC specifications and the consequences for ideal MHD stability evaluated including diamagnetic effects. These studies allow the determination of the optimum operational conditions for the achievement of MHD stable plasmas to demonstrate the Q = 5 steady-state goal in ITER in terms of plasma current, density, NBI and EC specifications, as well as the capability of the H&CD systems to ensure MHD stability and the assessment of other integration issues, such as divertor power load control. The capability of the ITER CS/PF magnets’ system to support these scenarios is found to be adequate [4] and will be described in the paper.

中文翻译：

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用 NBI 和 EC 加热和电流驱动重新评估 ITER 中的稳态运行

加热和电流驱动 AR Polevoi, S.Yu。梅德韦杰夫、GTA Huijsmans、SH Kim、A. Loarte、E. Fable、AA Ivanov、AY Kuyanov。ITER 组织, Route de Vinon-sur-Verdon, 13067 St Paul Lez Durance, France 2 Keldysh Institute of Applied Mathematics, Miusskaya 4, 125047 Moscow, Russia CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France普朗克研究所 für Plasmaphysik, Boltzmanstraße 2, D-85748 Garching, Germany NRC "Kurchatov Institute", Kurchatov sq. 1, 123098 Moscow, Russia 已重新评估 ITER 中稳态 (SS) 操作 [1] 的参数操作空间 (OS)通过全局分析，考虑中性射束注入 (NBI) 和 EC H&CD 系统的基线设计及其可预见的升级（最高 PNBI = 49.5 MW，PEC = 30 MW，其中最高可升级 40 MW）。该分析是针对所谓的 II 型 SS 情景进行的，这些情景专门使用 NBI 和 EC 进行加热和电流驱动 H&CD，并且假设没有内部传输障碍 [2, 3]。获得的 OS 决定了等离子体电流、密度、H&CD 规格（功率水平、注入几何形状等）的选择以及实现给定聚变增益所需的能量限制，Q=Pfus/(PEC+PNB)。从这些操作系统中选择了一组融合增益 Q=5 且具有各种 H&CD 规格的操作点 (OP)，用于更详细的 MHD 稳定性和 1.5-D 传输和电流驱动分析，包括灵敏度研究。在稳态电流平顶阶段对这些选定的 OP 进行了自洽 1.5-D 传输模拟。1. 5-D 模拟考虑了快速粒子压力以及自举和外部驱动电流的贡献。对电流和压力曲线的敏感性研究已经通过 NBI 和 EC 规范的变化以及对理想 MHD 稳定性评估的结果（包括抗磁效应）进行。这些研究允许确定实现 MHD 稳定等离子体的最佳操作条件，以证明 ITER 在等离子体电流、密度、NBI 和 EC 规格以及 H&CD 能力方面的 Q = 5 稳态目标系统以确保 MHD 稳定性和其他集成问题的评估，例如偏滤器功率负载控制。