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Remote diagnostics for determination of plasma shift in large aspect ratio tokamaks

机译:远程诊断,用于确定大宽高比的等离子体偏移

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摘要

In this contribution we presented a new simple technique for determination of tokamak plasma displacement based on poloidal flux measurement. This instrument consists of a two semicircle loops which installed toroidally on inner and outer sides of tokamak chamber and connected with each other. Really, this instrument detects the difference of poloidal flux on the High Field Side (HFS) and Low Field Side (LFS) of tokamak chamber, which we needed in calculating of the Plasma displacement. Main benefit of our proposed instrument is its simplicity. Based on this technique we determined the plasma position, and to compare the result obtained using this technique, an array of four magnetic probes and two flux loops are also designed, constructed and installed on outer surface of the IR-T1 tokamak and plasma position obtained from them. Results are in good agreement with analytical solution of equilibrium problem.
机译:在这一贡献中,我们提出了一种基于针状磁通量测量来确定托卡马克等离子体位移的新简单技术。该仪器由两个半圆形环组成,两个半圆环安装在托卡纳克室内和外侧的环形和外侧,彼此连接。实际上,该仪器检测到托卡马克室的高场侧(HFS)和低场侧(LFS)上的面色焊剂差异,我们在计算等离子体位移时需要。我们提出的仪器的主要好处是其简单性。基于该技术,我们确定了等离子体位置,并比较了使用该技术获得的结果,还设计了一系列四个磁探针和两个磁通环,构造和安装在IR-T1 Tokamak的外表面上和获得的等离子体位置从他们。结果与平衡问题分析解决方案吻合良好。

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