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Comparative divertor-transport study for helical devices

机译:螺旋装置的偏滤器-运输比较研究

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Using the island divertors (IDs) of W7-AS and W7-X and the helical divertor (HD) of LHD as examples, the paper presents a comparative divertor transport study for three typical helical devices of different machine sizes following two distinct divertor concepts, aiming at identifying common physics issues/effects for mutual validation and combined studies. Based on EMC3/EIRENE simulations supported by experimental results, the paper first reviews and compares the essential transport features of the W7-AS ID and the LHD HD in order to build a base and framework for a predictive study of W7-X. The fundamental role of low-order magnetic islands in both divertor concepts is emphasized. Preliminary EMC3/EIRENE simulation results for W7-X are presented and discussed with respect to W7-AS and LHD in order to show how the individual field and divertor topologies affect the divertor transport and performance. For instance, a high recycling regime, which is absent from W7-AS and LHD, is predicted to exist for W7-X. The paper focuses on identifying and understanding the role of divertors for high density plasma operations in helical devices. In this regard, special attention is paid to investigating the divertor function for controlling intrinsic impurities. Impurity transport behaviour and wall-sputtering processes of CX-neutrals are studied under different divertor plasma conditions. A divertor retention effect on intrinsic impurities at high SOL collisonalities is predicted for all the three devices. The required SOL plasma conditions and the underlying mechanisms are analysed in detail. Numerical results are discussed in conjunction with the experimental observations for high density divertor plasmas in W7-AS and LHD. Different SOL transport regimes are numerically identified for the standard divertor configuration of W7-X and the possible consequences on high density plasmas are assessed. All the EMC3-EIRENE simulations presented in this paper are based on vacuum fields and comparisons with local diagnostics are made for low-β plasmas.
机译:以W7-AS和W7-X的孤岛偏滤器(ID)和LHD的螺旋偏滤器(HD)为例,根据两个不同的偏滤器概念,对三种不同机器尺寸的典型螺旋装置进行了比较偏滤器传输研究,旨在确定共同的物理问题/效应,以便进行相互验证和组合研究。基于实验结果支持的EMC3 / EIRENE仿真,本文首先回顾并比较了W7-AS ID和LHD HD的基本传输特性,以便为W7-X的预测研究建立基础和框架。强调了低阶磁岛在两个偏滤器概念中的基本作用。针对W7-AS和LHD,针对W7-X提供了初步的EMC3 / EIRENE仿真结果,并进行了讨论,目的是展示各个场和分流器拓扑如何影响分流器的传输和性能。例如,W7-X预计将存在W7-AS和LHD不存在的高回收率制度。本文着重于识别和理解分流器在螺旋装置中高密度等离子体操作中的作用。在这方面,要特别注意研究用于控制固有杂质的偏滤器功能。研究了在不同的偏滤器等离子体条件下,CX中性物的杂质迁移行为和壁溅射过程。对于所有三种器件,都预测了在高SOL Collisonality下对固有杂质的滤光片保留效果。详细分析了所需的SOL等离子体条件及其潜在机理。结合W7-AS和LHD中高密度偏滤器等离子体的实验观察结果,讨论了数值结果。针对W7-X的标准偏滤器配置,在数值上确定了不同的SOL传输方式,并评估了对高密度等离子体的可能后果。本文介绍的所有EMC3-EIRENE模拟都是基于真空场,并且针对低β等离子体与本地诊断进行了比较。

著录项

  • 来源
    《Nuclear fusion》 |2009年第9期|30-40|共11页
  • 作者单位

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    National Institute for Fusion Science, Toki, Japan;

    National Institute for Fusion Science, Toki, Japan;

    National Institute for Fusion Science, Toki, Japan;

    National Institute for Fusion Science, Toki, Japan;

    National Institute for Fusion Science, Toki, Japan;

    National Institute for Fusion Science, Toki, Japan;

    Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Germany;

    National Institute for Fusion Science, Toki, Japan;

    National Institute for Fusion Science, Toki, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    stellarators, torsatrons, heliacs, bumpy tori, and other toroidal confinement devices; power exhaust; divertors; plasma simulation;

    机译:恒星器;旋风加速器;螺旋桨;颠簸的花托和其他环形限制装置;动力排气转向器等离子体模拟;
  • 入库时间 2022-08-18 00:45:12

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