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Estimation of SOL/Divertor Plasma Heating by Electron Cyclotron Radiation from Core Plasma in ITER

机译:电子转速辐射升降溶质溶液溶液溶液升降

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1. Introduction. Coupling of the plasma located1 inside the separatrix (the core plasma) with that-outside (SOL and divertor plasma) is usually taken into account via an exchange of boundary conditions (at the separatrix) between the transport codes for respective parts of plasma. In ITER tokamak, this pertains to the Automated System for Transport Analyses(ASTRA) [1] and the SOLPS4.3 [2] code. Since the mean free path(m.f.p.) of neutral atoms in ITER plasma is rather short and the intensity of the electron cyclotron (EC) waves with m.f.p. comparable with the minor radius of the plasma column is high [3]-[5], the EC radiation emitted by the core plasma could contribute to nonlocal coupling of the core and the SOL+divertor plasmas. Recent calculations [6] of the local electron energy balance for parameters needed for the steady-state operation of ITER [7] were based on a self-consistent model employing ID transport and 2D equilibrium models (1.5D approximation). That modeling included calculation of the electron cyclotron radiation (ECR) power density profile using the CYNEQ code [4],[6],[8] incorporated into the ASTRA framework. However, modeling, [6] did not allow for the absorption of the EC waves in the SOL+divertor region, despite the total power of EC radiation (on the top of the ECRH/ECCD power) in the vacuum vessel can amount, in the regime [7], to as much as -30 MW.
机译:1.简介。在分离器(核心等离子体)内部的等离子体的耦合通常通过交换用于各自的等离子体的传输码之间的边界条件(在分离器处)来考虑。在ITER Tokamak中,这与用于运输分析(Astra)[1]和Solps4.3 [2]代码的自动化系统涉及自动化系统。由于浸泡等离子体中的中性原子的平均自由路径(m.f.p)相当短,并且电子回旋/(EC)与m.p的强度。与等离子体柱的次要半径相当高[3] - [5],由核心等离子体发出的EC辐射可以有助于核心和溶胶+边缘等离子体的非局部耦合。近期迭代稳态操作所需参数的最近计算[6]基于采用ID传输和2D平衡模型(1.5D近似)的自我一致的模型。这种建模包括使用Cyneq码[4],[6],[8]结合到Astra框架中的电子回旋辐射(ECR)功率密度剖面的计算。然而,尽管EC辐射(在ECRH / ECCD电源的顶部)中的总功率可以量,但是,建模,[6]不允许在溶胶+偏移器区域中吸收EC波在SOL + VERECTOR区域中的eC波。制度[7],到达-30兆瓦。

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