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Overview of physics results from MAST

机译:MAST的物理学结果概述

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Major developments on the Mega Amp Spherical Tokamak (MAST) have enabled important advances in support of ITER and the physics basis of a spherical tokamak (ST) based component test facility (CTF), as well as providing new insight into underlying tokamak physics. For example, L-H transition studies benefit from high spatial and temporal resolution measurements of pedestal profile evolution (temperature, density and radial electric field) and in support of pedestal stability studies the edge current density profile has been inferred from motional Stark effect measurements. The influence of the q-profile and E x B flow shear on transport has been studied in MAST and equilibrium flow shear has been included in gyro-kinetic codes, improving comparisons with the experimental data. H-modes exhibit a weaker q and stronger collisionality dependence of heat diffusivity than implied by IPB98(y,2) scaling, which may have important implications for the design of an ST-based CTF. ELM mitigation, an important issue for ITER, has been demonstrated by applying resonant magnetic perturbations (RMPs) using both internal and external coils, but full stabilization of type-I ELMs has not been observed. Modelling shows the importance of including the plasma response to the RMP fields. MAST plasmas with q > 1 and weak central magnetic shear regularly exhibit a long-lived saturated ideal internal mode. Measured plasma braking in the presence of this mode compares well with neo-classical toroidal viscosity theory. In support of basic physics understanding, high resolution Thomson scattering measurements are providing new insight into sawtooth crash dynamics and neo-classical tearing mode critical island widths. Retarding field analyser measurements show elevated ion temperatures in the scrape-off layer of L-mode plasmas and, in the presence of type-I ELMs, ions with energy greater than 500 eV are detected 20 cm outside the separatrix. Disruption mitigation by massive gas injection has reduced divertor heat loads by up to 70%.
机译:Mega Amp球形托卡马克(MAST)的重大发展使ITER和基于球形托卡马克(ST)的组件测试设备(CTF)的物理基础得到了支持,并为基础的托卡马克物理提供了新的见识。例如,L-H过渡研究得益于基座轮廓演变(温度,密度和径向电场)的高时空分辨率测量,并且为了支持基座稳定性研究,已经从运动Stark效应测量中推断出了边缘电流密度轮廓。在MAST中已经研究了q剖面和E x B流动剪切对输运的影响,并且在陀螺动力学代码中包括了平衡流动剪切,从而改善了与实验数据的比较。 H模式显示比IPB98(y,2)缩放所暗示的更弱的q和更强的热扩散碰撞性依赖性,这可能对基于ST的CTF的设计具有重要意义。通过使用内部和外部线圈同时施加共振磁扰动(RMP),可以证明ELM缓解是ITER的重要问题,但尚未观察到I型ELM的完全稳定。建模显示了包括对RMP场的等离子体响应的重要性。 q> 1且中心磁剪弱的MAST等离子体通常表现出长寿命的饱和理想内部模式。在这种模式下测得的等离子制动与新古典环形粘度理论相比非常好。为了支持对基本物理学的理解,高分辨率汤姆森散射测量为锯齿碰撞动力学和新古典撕裂模式临界岛宽提供了新的见解。缓场分析仪的测量结果表明,L型等离子体的刮除层中的离子温度升高,并且在存在I型ELM的情况下,在分离线外20 cm处检测到能量大于500 eV的离子。通过大量注入气体来减轻干扰,已将滤清器的热负荷降低了多达70%。

著录项

  • 来源
    《Nuclear fusion》 |2011年第9期|p.177-186|共10页
  • 作者单位

    EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, UK;

    EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, UK;

    Associazione EURATOM-ENEA sulla Fusione, Frascati, Rome, Italy;

    EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, UK;

    EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, UK;

  • 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
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