索菲亚:托卡马克模拟器

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
F. Janky , A. Dnestrovskii , S.Y. Medvedev , V. Nemytov , B. Vincent , P.F. Buxton , T. Erskine , J. Sinha , O. Asunta , ST40 team
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引用次数: 0

摘要

索菲亚是托卡马克能源有限公司开发的托卡马克模拟器。SOPHIA将传输代码ASTRA与平衡求解器SPIDER、等离子体控制系统以及致动器和合成诊断模型相结合。SOPHIA的主要目标是帮助会议领导和负责物理学家在给定托卡马克系统以及等离子体控制系统的实验定义参考波形和设置的模拟中预测实验结果,从而为实验做准备。索菲亚读取这些波形和设置直接从会议领导人使用的应用程序来准备真正的实验,脉冲计划编辑器(PSE)。作为实验输入接口的补充,SOPHIA模拟结果使用与真实实验结果相同的格式和MDSplus数据结构进行存储,从而可以使用与真实实验数据分析相同的TE应用程序- MDSplus Shot Viewer和ST40 Physics Viewer。因此,SOPHIA与ST40实验完全集成,只需点击一个按钮即可触发SOPHIA仿真,实际上通常应该在每次放电之前运行。目前,索菲亚可以在几种模式下使用。在等离子体模拟方面,可以使用ASTRA代码中的预测输运计算,或者根据汤姆逊散射系统测量的选定放电的实验数据固定压力分布。在等离子体控制系统(PCS)方面,可以选择使用PCS内部等离子体位置估计器模块PFIT,就像在实际实验中一样,并从SPIDER内部的合成诊断(如Rogowski线圈电流,环路电压或局部磁传感器)生成其磁传感器输入。或者,可以将SPIDER直接计算的确切等离子体参数传递给控制器,例如等离子体径向和垂直位置,x点位置,到最后封闭磁通表面的间隙和等离子体电流,绕过PCS内部PFIT代码。索菲亚的模拟器框架是在Simulink和MATLAB环境下开发的,与C和Fortran代码进行了有效的内存耦合:它可以直接在MATLAB中运行,也可以作为C编译的可执行文件运行。等离子体控制系统包括控制器、监督和执行器模型(执行器模型是索菲亚的一部分,而不是pc的一部分)与实验中使用的完全相同。这扩展了索菲亚应用程序,以解决复杂的控制问题,其中多物理场和系统的多输入/输出性质是固有的等离子体动力学。更重要的是,SOPHIA与PSE管理器和其他操作中使用的应用程序的集成,使SOPHIA特别适合培训新的会议领导者和ST40操作员。它加快了学习曲线,增加了准备新实验的信心。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
SOPHIA: A tokamak simulator
SOPHIA is a tokamak simulator developed at Tokamak Energy Ltd. SOPHIA combines a transport code ASTRA coupled with an equilibrium solver SPIDER, a plasma control system and models of the actuators and synthetic diagnostics. The main goal of SOPHIA is to help session leaders and physicists in charge prepare for the experiment by predicting experimental outcome in a simulation given their experiment-defining reference waveforms and settings for the tokamak systems as well as the plasma control system. SOPHIA reads these waveforms and settings directly from the application used by session leaders to prepare real experiments, the Pulse Schedule Editor (PSE). Complimentary to its experimental input interface, SOPHIA simulation outcome is stored using a format and MDSplus data structure identical to that of real experimental results, enabling the use of the same TE applications as for real experimental data analysis – MDSplus Shot Viewer and ST40 Physics Viewer. Thus, SOPHIA is fully integrated with the ST40 experiment and SOPHIA simulation can simply be triggered with a click of a button, and in fact should generally be run prior to every discharge. Currently, SOPHIA can be used in several modes. On the plasma simulation side, one can use the predictive transport calculations in ASTRA code or else fix the pressure profile based on experimental data from a selected discharge, measured by Thomson scattering system. On the plasma control system (PCS) side, there is an option to use PCS internal plasma position estimator module, PFIT, just as in real experiments, and generate its magnetic sensor input from synthetic diagnostics inside SPIDER such as Rogowski coil currents, loop voltages or local magnetic sensors. Alternatively, one can pass on to the controllers the exact plasma parameters that SPIDER computes directly, such as plasma radial and vertical position, X-point locations, gaps to last closed flux surface and plasma current, bypassing the PCS internal PFIT code. SOPHIA’s simulator framework is developed in Simulink and MATLAB environment with effective memory coupling with C and Fortran codes: it can be run directly in MATLAB or as an executable compiled from C. Plasma control system, which includes controllers, supervision and actuator models (actuator models are part of SOPHIA, not part of PCS) is exactly the same as used in the experiments. This extends SOPHIA application to tackle complex control problems where the multi-physics and multiple input/output nature of the system is inherent to the plasma dynamics. Even more, SOPHIA’s integration with PSE manager and other applications used in operations, makes SOPHIA particularly well suited for training new session leaders and the ST40 operators. It speeds up learning curve and increases confidence in preparation for new experiments.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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