首页> 外文会议>EPS Conference on Plasma Physics >Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform
【24h】

Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform

机译:欧盟平台托卡马克等离子体的综合均衡重构与MHD稳定性分析

获取原文

摘要

I - Introduction The performance and operational limits of present and future Tokamak plasmas are influenced by the equilibrium profiles, shape and position e.g. vertical position stability in strongly shaped plasmas or onset of disruptive instabilities driven by profile gradients. Free boundary plasma equilibrium profiles can have a strong effect on the interpretation of all physical phenomena occurring in the plasma e.g. core/edge MHD stability characterization, plasma transport and auxiliary heating. It is thus a fundamental task to determine the plasma equilibrium using as many available input experimental data e.g. magnetic diagnostics (magnetic flux and poloidal magnetic field), density and temperature diagnostics and polarimetry diagnostics. In the framework of the EUROfusion Work Package on Code Development for Integrated Modelling, a scientific Kepler [1] workflow for the reconstruction of Tokamak plasma equilibrium was developed (Figure 1). It includes consolidated reconstruction codes such as EQUAL [2], CLISTE [3], EQUINOX [4] and post-processing error bar estimator SDSS [5], all using the same physics and machine data ontology and methods for accessing the data used in the European Integrated Modelling (EU-IM) framework [6]. Presently implemented modules (actors) are interfaced to "data bundles" e.g. magnetic sensors, Thomson scattering diagnostics as well as poloidal field coil data, are packed into a "machine bundle", to facilitate the data exchange in the workflow through selfconsistent datasets. The reconstruction codes feature polynomial or spline (natural or B-spline) representation for the profiles and non-uniform spatially distributed knots for the equilibrium regularisations are implemented. Equilibrium reconstructions relying on magnetics data only (magnetic diagnostic, PF/TF coils and iron core) or with added internal data (motional Stark effect, polarimetry or pressure) may be performed.
机译:I - 简介目前和未来Tokamak等离子体的性能和操作限制受到平衡曲线,形状和位置的影响。垂直位置稳定性在强形等离子体中或由剖面梯度驱动的破坏性不稳定性的发作。自由边界等离子体平衡曲线可以对等离子体中发生的所有物理现象的解释产生强烈影响。核心/边缘MHD稳定性表征,等离子体传输和辅助加热。因此,它是一种基本任务,用于使用尽可能多的可用输入实验数据来确定等离子体平衡。磁性诊断(磁通量和磁场),密度和温度诊断和偏振诊断。在Eurofusion工作包的框架上,在综合建模的代码开发中,开发了一个科学开普勒[1]用于重建Tokamak等离子体均衡的工作流程(图1)。它包括综合重建代码,如相等[2],CLISTE [3],Equinox [4]和后处理错误栏估计器SDSS [5],所有这些都使用相同的物理和机器数据本体和用于访问所用数据的方法欧洲综合建模(EU-IM)框架[6]。目前实现的模块(Actors)与“数据束”接口为例如“数据束”。磁传感器,汤姆森散射诊断以及针状磁场线圈数据包装成“机器束”,以便于通过自信数据集进行工作流程中的数据交换。实现了用于平衡正则求解的轮廓和非均匀空间分布结的重建代码特征多项式或花键(天然或B样条)表示。可以执行依赖于磁性数据的平衡重建(磁性诊断,PF / TF线圈和铁芯)或添加内部数据(运动迹效应,偏振效果或压力)。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号