Edge localized modes: recent experimental findings and related issues

Edge localized modes: recent experimental findings and related issues
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DOI:
10.1088/0741-3335/49/7/s03
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发表时间:
2007-07
影响因子:
2.2
通讯作者:
K. Kamiya;N. Asakura;J. Boedo;T. Eich;G. Federici;M. Fenstermacher;K. Finken;A. Herrmann;J. Te
K. Kamiya;N. Asakura;J. Boedo;T. Eich;G. Federici;M. Fenstermacher;K. Finken;A. Herrmann;J. Te
中科院分区:
物理与天体物理2区
文献类型:
--
作者:
K. Kamiya;N. Asakura;J. Boedo;T. Eich;G. Federici;M. Fenstermacher;K. Finken;A. Herrmann;J. Te

文献摘要

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综述了ASDEX-Upgrade、DIII-D、JET、JT-60 U和MAST等托卡马克装置的边缘局域模(ELM)测量,包括利用扫描探针、径向干涉仪弦、BES和切向观察快选通相机等高精度快速时间分辨诊断技术在等离子体边缘区进行实验观测的进展。ELM动力学数据表明,大部分的ELM粒子和能量传输应占主导地位的离子对流物理和相关的时间尺度。此外,最近对许多托卡马克的诊断升级揭示了ELM灯丝结构及其向径向、极向和环向的复杂运动。除了I型ELMy H模式操作的替代方案(所谓的小/无ELM区域)之外,控制I型ELM的方法也是当前托卡马克研究的一个关键领域,在没有大的ELM诱导的瞬态热/粒子通量到偏滤器靶的情况下,该托卡马克表现出高约束(与I型ELMy H模式等离子体在类似参数下的约束相当)。虽然可以容忍的ELM制度,在现有的设备,其应用到ITER是不确定的。这些制度对进一步的实验和偏滤器靶和主室壁的功率沉积的问题进行了讨论。
Edge localized mode (ELM) measurements in many tokamaks, including ASDEX-Upgrade, DIII-D, JET, JT-60U and MAST, are reviewed, which includes progress in experimental observations at the plasma edge region by means of fast-time resolved diagnostics with high precision, such as scanning probe, radial interferometer chord, BES and tangentially viewing fast-gated camera at the midplane. ELM dynamics data show that the majority of the ELM particle and energy transport should be dominated by ion convection physics and associated timescales. Furthermore, recent diagnostic upgrades on many tokamaks reveal the ELM filament structure and their complex motion towards radial, poloidal and toroidal directions. Approaches to control the Type-I ELMs, in addition to the alternative scenarios to Type-I ELMy H-mode operation (so-called, small/no ELM regimes) are also a key area of research for current tokamaks, which demonstrated a high confinement (being comparable to that of Type-I ELMy H-mode plasmas at similar parameters) in the absence of large, ELM induced, transient heat/particle fluxes to the divertor targets. Although tolerable ELM regimes are obtained in existing devices, their application to ITER is uncertain. Issues of these regimes towards further experiments and power deposition on divertor targets and main chamber wall are discussed.