Overview of the TCV digital real-time plasma control system and its applications

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-09-13 DOI:10.1016/j.fusengdes.2024.114640

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Abstract

Real-time plasma control systems are at the heart of operation of modern tokamaks. The control system of the TCV tokamak has recently seen a major upgrade in terms of its hardware and software components. Control algorithms are entirely programmed and tested in MATLAB/Simulink(R), executable code is automatically generated and interfaced to run-time parameters and signals through introspection using the MARTe2 software framework. The primary control system (used for coil currents, plasma current, position, shape and density control) has been upgraded by installing new analog signal inputs/output hardware, connected to two real-time computers that can operate in parallel. In addition, an EtherCAT-based real-time industrial network has been deployed to operate distributed low Input/Output count subsystems, greatly boosting the system flexibility and reach. The majority of TCV’s real-time codes have been ported to this new approach, such as the real-time equilibrium reconstruction (LIUQE), real-time Magneto-Hydro-Dynamics mode analysis algorithms, and a real-time plasma supervision, actuator management and plasma event monitor, including real-time plasma analysis using neural networks, and plasma disruption avoidance control schemes.

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TCV 数字实时等离子体控制系统及其应用概述

实时等离子体控制系统是现代托卡马克运行的核心。TCV 托卡马克的控制系统最近在硬件和软件组件方面进行了重大升级。控制算法完全在 MATLAB/Simulink(R)中编程和测试，可执行代码自动生成，并通过使用 MARTe2 软件框架的自省功能与运行时的参数和信号连接。主控制系统（用于线圈电流、等离子体电流、位置、形状和密度控制）已经升级，安装了新的模拟信号输入/输出硬件，并与两台可并行运行的实时计算机相连。此外，还部署了基于 EtherCAT 的实时工业网络，以运行分布式低输入/输出数子系统，从而大大提高了系统的灵活性和覆盖范围。TCV 的大部分实时代码都已移植到这种新方法中，例如实时平衡重构（LIUQE）、实时磁流体动力学模式分析算法、实时等离子体监督、致动器管理和等离子体事件监控，包括使用神经网络的实时等离子体分析和等离子体中断避免控制方案。

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来源期刊

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.