Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak

IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
J. D. Weberski, M. W. Bongard, S. J. Diem, R. J. Fonck, J. A. Goetz, M. D. Nornberg, J. A. Reusch, C. E. Schaefer, A. C. Sontag
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引用次数: 0

Abstract

Open field line currents are intrinsic to DC helicity injection plasma startup and pose a challenge for inferring the plasma equilibrium with standard reconstruction analysis. Local helicity injection (LHI) is a type of DC helicity injection which uses small, modular current sources to drive force-free current along helical field lines to produce tokamak plasmas. MHD modeling and magnetic measurements during LHI indicate the injected current streams remain coherent as helical structures on the outboard edge of a core toroidal plasma that is tokamak-like in a toroidally averaged sense. To extract core plasma equilibrium properties, external magnetic diagnostics corrected for contributions from the injected current streams are fitted by a standard Grad-Shafranov equilibrium code. An iterative approach for estimating and subtracting the stream contributions from the diagnostic signals is described and applied to a model equilibrium database to reduce systematic errors introduced by the streams. Convergence is usually attained with 2 to 4 iterations, with derived equilibrium parameters matching the prescribed axisymmetric core values to within estimated experimental uncertainties. Accurate recovery of core parameters occurs when the ratio of the net toroidal windup current from the streams to the core plasma current is less than 0.2, which is typically satisfied in most experiments.

注入电流流对球形托卡马克中局部螺旋注入等离子体的 MHD 平衡重构的影响
开场线电流是直流螺旋注入等离子体启动的固有特性,对用标准重构分析推断等离子体平衡构成挑战。局部螺旋注入(LHI)是直流螺旋注入的一种类型,它使用小型模块化电流源,沿着螺旋场线驱动无力电流,以产生托卡马克等离子体。LHI 期间的 MHD 建模和磁场测量结果表明,注入的电流流在核心环形等离子体的外侧边缘保持相干的螺旋结构,该等离子体在环形平均意义上类似于托卡马克。为了提取核心等离子体的平衡特性,用标准的 Grad-Shafranov 平衡代码拟合了校正注入电流流贡献的外部磁诊断。描述了从诊断信号中估计和减去磁流贡献的迭代方法,并将其应用于模型平衡数据库,以减少磁流带来的系统误差。通常经过 2 到 4 次迭代就能达到收敛,推导出的平衡参数与规定的轴对称核心值相匹配,在估计的实验不确定性范围内。当来自流的净环形卷积电流与堆芯等离子体电流之比小于 0.2 时,堆芯参数就能得到精确恢复,而这在大多数实验中通常都能满足要求。
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来源期刊
Journal of Fusion Energy
Journal of Fusion Energy 工程技术-核科学技术
CiteScore
2.20
自引率
0.00%
发文量
24
审稿时长
2.3 months
期刊介绍: The Journal of Fusion Energy features original research contributions and review papers examining and the development and enhancing the knowledge base of thermonuclear fusion as a potential power source. It is designed to serve as a journal of record for the publication of original research results in fundamental and applied physics, applied science and technological development. The journal publishes qualified papers based on peer reviews. This journal also provides a forum for discussing broader policies and strategies that have played, and will continue to play, a crucial role in fusion programs. In keeping with this theme, readers will find articles covering an array of important matters concerning strategy and program direction.
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