Investigation of Electron Temperature Profile Details during Plasma Column Displacement and ECRH Power up to 1.5 MW in the T-10 Tokamak

IF 0.9 4区 物理与天体物理 Q4 PHYSICS, FLUIDS & PLASMAS
S. V. Neudachin, A. A. Borschegovskii, I. S. Pimenov, I. N. Roy
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Abstract

The question of the existence of internal transport barriers (ITBs) around low-rational number values of the stability factor q = 1, 2, … in the usual L-mode of tokamaks with central additional heating and positive magnetic shear remains open. To clarify the existence of such ITBs, experiments were carried out with a programmed linear time shift of the plasma column, in which the positions of the electron temperature measurements Te of the emission at the second electron cyclotron harmonic are shifted relative to the plasma column, which allows one to study the Te profile details. A series of experiments with perpendicular input of EC radiation with a power of 0.4 and 0.85 MW at a central ECRH and a fast (60 ms) shift of the column by 0.13a (minor plasma radius a) were carried out on the T-10 tokamak in plasma with a carbon limiter. In both cases, outside the q = 1 surface narrow (about 0.03a wide) and weak (a decrease in the coefficient of electron thermal conductivity χe by approximately two times) ITBs detected, which disappeared when the discharge parameters changed. These ITBs are 2–3 times narrower and an order of magnitude weaker than the ITBs near the surface q = 1, which was previously proposed to explain the RTP tokamak results. ITBs were not detected in the L-mode in experiments with simultaneous generation of a co-current and counter-current in the plasma center by two gyrotrons with a total power of 1.5 MW in a plasma with a tungsten limiter (column shift by 0.1a in 30 ms). This article appears to be the first journal publication on the study of Te profile details with rapid movement of the plasma column.

Abstract Image

T-10托卡马克等离子体柱位移和ECRH功率高达1.5 MW时电子温度分布细节的研究
在具有中心附加加热和正磁切变的常规l型托卡马克中,在稳定因子q = 1,2,…的低有理数附近存在内部输运障碍(ITBs)的问题仍然没有解决。为了澄清这样的ITBs的存在,实验进行了程序化的等离子体柱线性时移,其中电子温度测量在第二电子回旋加速器谐波发射的位置相对于等离子体柱移位,这使得人们可以研究Te剖面的细节。在T-10托卡马克上,用碳限幅器在等离子体中进行了功率分别为0.4和0.85 MW的垂直输入EC辐射和柱快速位移(60 ms) 0.13a(小等离子体半径A)的一系列实验。在这两种情况下,在q = 1表面外都检测到窄(约0.03a宽)和弱(电子导热系数χe降低约2倍)的ITBs,当放电参数改变时,ITBs消失。这些itb比表面q = 1附近的itb窄2-3倍,弱一个数量级,这是先前提出的解释RTP托卡马克结果的方法。在带钨限幅器的等离子体中,用总功率为1.5 MW的两个回旋管同时在等离子体中心产生共电流和逆流(30 ms内柱移0.1a),在l模式下没有检测到ITBs。这篇文章似乎是关于等离子体柱快速移动的剖面细节研究的第一篇期刊出版物。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Plasma Physics Reports
Plasma Physics Reports 物理-物理:流体与等离子体
CiteScore
1.90
自引率
36.40%
发文量
104
审稿时长
4-8 weeks
期刊介绍: Plasma Physics Reports is a peer reviewed journal devoted to plasma physics. The journal covers the following topics: high-temperature plasma physics related to the problem of controlled nuclear fusion based on magnetic and inertial confinement; physics of cosmic plasma, including magnetosphere plasma, sun and stellar plasma, etc.; gas discharge plasma and plasma generated by laser and particle beams. The journal also publishes papers on such related topics as plasma electronics, generation of radiation in plasma, and plasma diagnostics. As well as other original communications, the journal publishes topical reviews and conference proceedings.
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